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| | number = ML19305D973 | | | number = ML19305D973 |
| | issue date = 04/03/1980 | | | issue date = 04/03/1980 |
| | title = Annual Environ Operating Rept (Radiological) for 1979. | | | title = Annual Environ Operating Rept (Radiological) for 1979 |
| | author name = Gilbert J, Hopper D, Smith E | | | author name = Gilbert J, Hopper D, Smith E |
| | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
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| =Text= | | =Text= |
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| ANNUAL EN7IRONMENTAL OPERATING REPORT
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| RADICLOGICAL RE? ORT NORTH 10;NA P0k7.R STATION JAN. 1,1979 - DEC. 31,1979 i
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| i Prepared by: . , 16 h.D. Gilbert -Assistant Health
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| * Phy ics Supegvisor
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| Approved by: . iD OL
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| * D.M. Hopper - Supervisor Health Supervisor C '
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| ff. .' <
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| E.R.Scith,Jr. - Superintendent Technical Services'
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| W.R.Cartwright - Station Manager -
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| 800.4170052 .
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| THIS REPORT IS SUBMITTED AS REQUIRED BY APPENDIX B TO ;
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| OPERATING LICENSE, ENVIRONMENTAL TECHNICAL SPECIFICATIONS FOR NORTH ANNA POWER STATION UNITS 1 AND 2, VIRGINIA ELECTRIC AND PCWER CCMPANY DOCKET NOS. 50-338, 50-339 i
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| SECTION 5.6.1.1 j 4
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| O FIRST QUARTER
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| T TELEDYNE -
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| IwL-7043-444 ISOTOPES
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| VIRGINIA ELECTRIC AND POWER COMPANY P.O. BOX 402 !
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| MINERAL, VIRGINIA 23117
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| NORTH ANNA POWER STATION !
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| l ENVIRONMENTAL RALIOLOGICAL MONITORING PRCGRM1
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| 1979 t
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| DESCRIPTION OF THE OPERATIONAL PRCGRMI AND QUARTERLY REPORTS AND ANALYSIS
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| I Prepared by
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| TELEDYNE ISCTCPES 50 VAN BUREN AVENUE '
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| WESTWCCD, NEW JERSEY 07675
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| -__ _____ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _
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| T TELEDYNE. l ISOTOPES ,
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| - TABLE OF CONTENTS Page ;
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| l 11 LIST OF TABLES 11 LIST OF FIGURES !
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| 1 ,
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| INTRODUCTION 2
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| THE RADIOLOGICAL E.WIRONMENTAL PROGRAM 11 ;
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| ABSTRACTS OF ANALYTICAL PROCEDURES 14 ABSTRACTS OF RADI0 ASSAY PROCEDURES 18 QUALITY CONTROL OF ANALYSIS
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| ==SUMMARY==
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| OF QUARTERLY RESULTS AND DISCUSSION -
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| 19 EXCEPTIONS AND SPECIAL EVEV.TS ,
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| 20 AIRBORNE EXPOSURE PATHWAY
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| DIRECT EXPOSURE PATHWAY 26 -
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| 29 WATERBORNE EXPOSURE PATHWAY 35 INGESTION EXPOSURE PATHWAY 38A CONCLUSIONS 40 ,
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| REFERENCES
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| ^~1 APPENDIX A 2TA TABLES-FIRST QUARTER 1979
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| 'TTELEDYNE ISOTOPES
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| LIST OF TABLES Page TABLE 1 Operational Radiological Environmental Monitoring Program 5 l
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| TABLE 2 Sampling Station Identification and Location 8 TABLE 3 Lower Limits of Detection (LLD) IS TABLE 4 REMP Summary - Airborne Exposure 22 TAB 12 S RDiP St.DotARY - Direct Exposure 30 TABLE 6 RDtP Summary - Waterborne Exposure 33 TABLE 7 RDtP SUlotARY - Ingestion Exposure 37 TABLE 8 Radiation Dose to the Individual from Natural and Aritifical 39 ;
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| Sources ,
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| LIST OF FIGURES
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| FIGURE 1 Map of Sampling Stations in Vicinity of NAPS 9 FIGURE 2 Map of the Environmental Sampling Stations 10 FIGURE 3 Airborne Exposure - Gross Beta and Ce-144 (1977-1979) 21 FIGURE 4 Direct Exposure - Environmental TLD (1977-1979) 27 FIGURE S Waterborne Exposure - Tritium (1977-1979) 30 t
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| FIGURE 6 Ingestion Exposure - Sr-90 (1977-1979) 36
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| TTELEDYNE ,
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| ISOTOPES INTRODUCTION Outlined in this document is the description of the operational environmental radiological monitoring program conducted by Virginia Electric and Power Company for the North Anna Power Station, and a su= mary of the data generated to satisfy the monitoring requirements. This program is ,
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| based on the technical specifications requiring the collection and anlaysis of various sample media to provide information en the type and quantity of radioactivity in certain indicator organisms or critical pathways. The operational program became mandatory on April S,1978 upon granting of the operating license for the North Anna Power Station Unit 1.
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| Vigrinia Electric and Power Company is responsible for the col- ;
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| lection of the samples required for the program and Teledyne Isotopes is '
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| responsible for the analysis of each sample and submission of the reports of analysis. Quarterly summaries of the data reported for each sample type ,
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| will be appended to this document for the period of January 1,1979 through
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| December 31, 1979.
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| These quarterly data summaries will include a summary of the radioactivities repor:ed for each sample type and pathway and a tabulation of the mean, range, and detections / total for each sample type and radionuclide.
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| From the data summaries, a radiological environmental monitoring program table as specified in Regulatory Guide 4.8 (Ref.1) will be prepared and used as
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| * the basis for evaluating the radiation exposures resulting from the North
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| (. Anna, Power Station operations.
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| Baseline levels of radioactivity in the environs of the North Anna Power Station have been established during the preoperational phase ,
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| randucted from July 1,1974 through December 31, 1977 (Ref. 2-6). On April ;
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| b, 1978 the oper< . ting license for the North Anna Power Station - Unit 1 was granted requiring the transition from the preoperational to the operational phase of the radiological environmental scnitoring program.
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| The operational phase of the program is described in Appendix 3 l to the Operating License (Ref. 7) and the required analysis and specifica- >
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| tions (Table 1) were phased into the program during the January 1- March 31, i
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| 1978 quarter.
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| The overall objectives (Ref. 7) of the operational radiological environmental monitoring program are to identify changes of radioactivity .
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| * in the vicinity of the North Anna Power Station and to provide information on the types and quantity of radiation in certain critical pathways and indicator organisms as a basis for evaluating radiation exposure from sta-tion operation.
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| 'pPnnELEC7(NE ISOTOPES l
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| DESCRIPTION OF THE CPERATIONAL PROGRAM THE RADIOLOGICAL ENVIRONMENTAL PRCGRAM The description of the operational radiological environmental ana-lysis program is presented in this section. Personnel of VEPCO collect the samples specified in Table 1 and ship them to Teledyne Isotopes for the analytical phase of the program. Interim data reports are submitted by Teledyne Isotopes as the analyses are completed, normally within 33 days of the date of receipt of samples (Ref. 9). Summary reports are issued quarterly by Teledyne Isotopes,rusually within 45 days after the end of the quarter. The quarterly reports will be appended to this report and will contain (1) computer compilations of the analytical data from the ,
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| interim data reports, (2) summaries of the environmental radiological ana-lysis for each media listing the mean and range of detected radionuclides and the ratio of detected radionuclides to total measurements, (3) data interpretations for each media and analysis based on the summary table prepared in accordance with Regulatory Guide 4.8 (Ref.1) .
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| The radiological environmental program outlined in Table 1 con-taine the technical specification requirements for the North Anna Power Station (Ref. 7 ).
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| Sampling station identifications and relative positions to the
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| - effluent release point are listed in Table 2 (Ref. 8 ) and shown on Figure 1 and Figure 2 (maps indicating the environmental sampling stations) .
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| The operational environmental radiological program requires measurements on the following media.
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| Airborne Particulates
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| Particulate filters are collected weekly from air sampling '
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| stations 1, 3, 5, 7, 21, 22, 23, 24 and. analyted for gross beta activity. Quarterly composites of t:iese particulate air samples are analyted for Sr-89, Sr-70 (:econd quarter 8only) , and gamma emit-ting nuclides by high resolution ge(Li) gamma spectremetry. Air sampling stations are located on Figures 1 and 2 and ilsted in Table 1.
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| Lapse time recorders are used*to calculate actual air volumes.
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| i Radiogas (Radiciodine)
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| Charcoal cartridges are collected from sampling stations 3, {
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| 21, 23, 24 weekly.. The cartridges are analyted for radiciodine ,
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| by distillation and beta counting. Charcoal cartridge sampling -
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| locations.are shown on Figures 1 and 2. f
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| TTELEDYNE ISOTOPES Direct Radiation Environmental direct radiation levels are monitored by therm-oluminescent dosimeters (TLD) using a multi-area, phosphor teflon CaSO 4
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| :Dy dosimeter. Dosimeters are placed at each location and ex-changes are made quarterly. TLDs are located at stations 1, 3, 4, 5, 6, 7, 21, 22, 23, and 24 (see Table 1 and Figures 1 and 2) . *
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| Milk Milk samples are collected' monthly from locations'22, 13, 14 and analyzed for I-131 by chemical separation and gamma isotopic emit-ters by high resolution Ge(Li) gam =a spectrometry. Quarterly milk samples are analy:ed for Sr-89, Sr-90. Milk sampling locations are listed in Table 1 and shown in Figures 1 and 2.
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| Well Water Water samples are collected quarterly from the Environmental Laboratory well and analy:ed for tritium and for gamma emitting nu-clides by high resolution Ge(Li) gamma spectrometry. The second quarter samples are also analy:ed for Sr-89, Sr-90.
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| Surface Water
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| A sample of surface water (North Anna River) is collected quar-terly from Station 11 for tritium and ga=ma isotopic nuclides. Surface
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| , water samples are also collected monthly from Station 03 (Discharge) and Station 09 (Reservoir) and analy:ed for tritium, iodine-131, and gamma isotopes. The secend quarter surface water samples or composites are also analy:ed for Sr-89, Sr-90.
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| Fish Fish are collected annually near the beginning of the season from t.wo locations and analy:ed for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. Fish sampling sites are at i locations 8 and 9 on Figure 1.
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| Terrestrial Vegetation
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| Samples of green leafy vegetation (cultivated or weeds) are collected annually during the harvest from two locations, Stations 21 and 23. These samples are analy:ed for gamma emitting nuclides by high resolution Ge(L1) gamma spectrometry.
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| Soil Soil samples are collected from locations near the airborne stations every three years and analy:cd for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. The stations are 1, 3, 4, 5, 6, 7, 21, 22, 23, and 24 Stations 1, 21, 22, 23 and 24 are also analy:ed for Fr 30 Sr-90.
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| i TTELEDYNE ISOTOPES
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| Sediment / Silt Silt samples from Stations 8, 9, and 11 along with a shore-line sample from the vicinity of Station 9 are collected semiannually and analyzed for gamma emitting nuclides by high resolution Ge(Li)'
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| gamma spectrometry. Sediment / silt samples are analy:ed annually for Sr-89, Sr-90.
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| l l TABLE 1
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| l NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
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| EXPOSURE PATilWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY
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| A;iD/0R SAP.PLE HAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS AIRBORf;E Pa.ticulates Site or site boundary: 1,21, Continuous sampler Weeki'y gross beta on
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| * 22, 23 (2/3 running time each filter, quarterly.
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| . Comnunities: 3,5,7 cycle), changes gamma isotopic on each Control: 24 weekly location composite, Sr-89-90 on second m Radiolodine 3.21,23,24 quarter composite, I-131 on radiolodine
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| weekly.
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| Soll "
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| 1,3,4,5,6,7,21,22,23,24 Once per 3 years Ganvna isotopic on each,
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| , Sr 89-90 on 1,21.22, 23, 24 (on collection)
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| DIRECT 1,3,4,5,6,7,21,22~23,24 -
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| Quarterly Gamna dose quarterly l!ATERDORNE Reservoir: 9 Monthly Gammafsotopicradio-Discharge: 8 todine 11-3 quarterly composite, Sr 89-90 second quarter composite
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| North Anna River:d ll Quarterly Gamma isotopic,11-3 on Ground (well): lA collection, Sr 89-90 second quarter sample
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| TABLE 1 .
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| NORTil ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND' TYPE AND FREQUENCY AllD/0R SAMPLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS
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| AQUATIC Reservoir: 9 Semiannually Gama isotopic on Sedistent Discharge: 8 collection Sr 89-90 North Anna River: 11 annually Shoreline Vicinity of: 9 IllGESTION milk Nearest Dairies: 12, 13, 14 Honthly a
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| Radiotodine a ,e, g ,,,
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| isotopic monthly, Sr 89-90 quarterly
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| * Non-dairy activity b Calculated dose ~Radiolodine '', Gama D h b dependent isotopic Sr 89-90 Fish Reservoir: 9 Annually, near Gama isotopic
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| ." Bass, or sunfish Discharge: 8 beginning of season or crappie and catfish)
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| Green Leafy 21, 23 Annually during Gama i:otopic on vegetation, .
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| harvest e collection cultivated or -
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| weeds. Ilaturally ,
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| occurring
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| . NORTH ANNA POWER STATION ,
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| OPERATIONAL RADIOLOGICAL EtNIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLIt!G AND TYPE AND FREQUENCY AllD/0R SAMFLE HAP NUMBER DESIGNAfl0N COLLECTION FREQUENCY OF ANALYSIS
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| : a. Once each month I and 2 mrem thyroid isodose llnes will be calculated using the previous month's release data tused on the cow-milk-child pathway. Should a dairy be located within the 1 mrem isodose line the sampling and analysis frequency fe .adioiodine will be modified to semimonthly for the month following the month for which the calcul**'.,.. was made. A similar sampling program will be for the 2 mrem isodose line except on a weekly frequ~..cy.
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| : b. Monthly updates of the current year's annual accumulated calculated thyroid 15 mrem isodose lines based on the
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| " goat-milk-child and the cow-milk-child pathway will be done. Should the isodose line extend beyond the site boundary, a survey to locate goats or cows within the isodose line will be carried out within 30 days. Should goats or cows be observed, ef forts to obtain samples from the owners of the animals will be put forth. If serrples are obtainable, a sampling program similar to ".a" above will be initiated. If samples are unobtainable, the annual report will document such and include the calculated doses.
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| : c. Monthly updates of an annual 15 mrem isodose line (using release data and maximum organ dose in each of the 16 sectors) based on the grass-cattle-beef-man pathway will be done. Should the isodose line extend beyond the site boundary, sampling and analyses will be modified to monthly for the current year.
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| : d. Samples will.be taken from the Environmental Laboratory well.
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| : e. Radioiodine analyses will be done by chemical separation.
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| s TABLE 2 POINT _
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| SAMPLING STATION IDENTIFICATION AND RELATIVE POSITTON To dFFLUENT RELEASE
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| 1 DEGREES AND DISTANCE COMPASS DIRECTION REMARKS STATION HILES NUH8ER LOCATION 0.2 42 NE 01 On Site 5.3 225 SSW 02 Fredericks liall 243 WSW g 7'1
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| * 03 Nineral 287 WNW 5.1 04 Wares Crossroads 20 HNE Good llope Church 4.2 05 11 SSE 3.2 05A Sturgeon's Creek 4.7 115 ESE 06 Levy.
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| 7.3 167 SSE 07 Sumpass 3.1 148 SSE Disclearge Lagoons 04 CONTROL 2.2 320 NW
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| ~ Lake Anna, upstream 09
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| * 128 SSE l 5.8 North Anna River, downstream
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| !! 330 NW 8.3 llolladay Dairy 12 205 SSW ,
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| 5.6 13 Fredericks 11 11 202 SSW 3.2 Trice Dairy 14 301 WNW 1.0 21 Route 685 242 WSW J.0 22 Route 7-0 l
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| 0.9 154 SSE Aspen ll!!1s CONTROL 23 325 NW 22.0 Orange 24
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| .
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| TTELEDYNE ISOTOPES ABSTRACTS CF THE ANALYTICAL PROCEDURES The following r.re abstracts of the radionuclide separation, puri-fication, and measurement techniques used by Teledyne Isotopes. These tech-niques have been developed to' meet the detection sen.sitivities (Table 3) and associated accuracies required by the nuclear industry in compliance with technical specifications.
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| t Air Particulates ,
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| t Cross Beta Transfer filter to a 2-inch diameter planchet and assay in a Beck-
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| * man Sharp Wide Beta II automatic alpha / beta counter. !
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| ,
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| Gamma Isotopic Analysis _
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| Composite station filters are combined quarterly and radioassayed on a high resolution, high efficiency Ge(Li) detector.
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| .
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| Radiogas
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| ,
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| Iodine-131 Two procedures are used for the analysis of charcoal cartridges for iodine-131. ,
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| METHOD 1. If the charcoal used is NOT impregnated with elemental iodine, iodide carrier is added and leached with NaCH. The stable iodide and I-131 is then stripped and extracted as iodine and precipitated as PdI2 '
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| meunted on a nylon planchet, and assayed by low level beta counting.
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| METHCD 2. If the charcoal used in the filters is impregnated with iodine, the chemical yield of the distillation procedure cannot be determined and the samples are analy:ed by high resolution ga=ma spectrometry (Ge(Li)) by integration of the I-131 photopeak. >a%
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| a Direct Radiation (TLD)
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| CaSO :Dy ther=oluminescent dosimetur packets consisting of the 4
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| four-area RadiGuard badge are placed at monit; ring locations. At the end of 1 the monitoring period, the dosimeters are returned to Teledyne Isotopes for readout. Results are reported in mR for the collection period or mR/ cc11ection time period.
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| Milk. +
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| Iodine-131 Stable iodide carrier is added to an aliquot of milk and the io-dide and I-131 is reme ad by anion exchange resin. The iodine is stripped l
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| 11
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| .____ - .. __ . .
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| TTELEDYNE ISOTOPES with NaOH solution, treated with hydroxylamine hydrochloride and NANO3 , and '
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| extracted into CHC1 3 as fm Mne (I,) . It is then back extracted Into NaHS03 solution and precipitated as PdI 2 . The precipitate is mounted on a nylon planchet for low level beta counting.
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| Strontium-89/ Strontium-90 To 1 liter of milk add strontium carrier and TCA solution. Stir solution and allow precipitation to settle overnight. Filter, wash, and dis-card precipitate. To the filtrate and oxalic acid, followed by NH 4CH until the solution is alkaline in order to precipitate calcium and strontium oxalates.
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| This precipitate is filtered and ashed, and the ash is dissolved in nitric .
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| [
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| acid. Fe(OH)3 ' scavenges are performed and stable yttrium carrier added, followed by a 5 to 7 day period for Y-90 ingrowth. The yttrium is precipi- ,
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| tated as the hydroxide, redissolved and precipitated as the oxalate, and '
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| then mounted on a nylon planchet and counted in a low level beta counter.
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| The strontium is precipitated from the sample as SrCO , mounted on a nylon planchet and counted in a low level beta counter for dr-89 and/or the Y-90 ingrowth. i
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| '
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| Gamma Isotopic Analysis Transfer 1 liter of milk to a 1-liter wrap-around Marinelli count-
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| -
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| ing beaker and radioassay on a high resolution Ge(Li) detector.
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| Well Water Tr.' tium
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| -
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| ,
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| .
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| An aliquot of sample is converted to hydrogen gas by reduction in a hot :ina furnace, mixed with methane counting gas and radioassayed utili:ing an internal low level gas proportional counter. Very low levels of activity i can be detrcted due to the sophistication of the counting equipment, the -
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| electrcnics, and the shielding.
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| - Gamma Isotopic Analysis One liter of sample is transferred to a 1-liter Marinelli wrap- ,
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| around counting beaker and counted on a Ge(L1) detector. !
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| ;
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| Surface Water -
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| ,
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| i Tritium An aliquot of sample is converted to hydrogen by gas reduction in a hot :ine furnace, mixed with methane counting gas and is radioassayed util-1:ing an internal low level gas proportional counter. Very low levels of ac- i
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| .
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| tivity can be detected'due to the sophistication of the counting equipment, 1 the electronics, and the shielding.
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| i
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| !
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| l
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| !
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| i 12 l
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| {
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| >
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| -. _ _ _ ____- _ _ _ _ __
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| . _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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| l
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| , - - - . _ . - . _ _ _ _ . _ . __
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| TTELEDYNE ISOTOPES ,
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| Gamma Isotopic Analysis one liter of sample is transferred to a 1-liter Marinelli wrap-around counting beaker and counted on' a Ge(Li) detector. j
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| .
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| Fish Gamma Isotopic Analysis ;
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| Remove the edible portions by filleting the fish and homogeni-ing ,
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| in a high speed blender or dice into small pieces. Transfer the blended or diced portions to a 300 m1 bottle, record the weight, and radioassay on a high resolution Ge(Li) detector.
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| !
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| Vegetation / Terrestrial (Green Leafy)
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| Gamma Isotopic Analysis !
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| Completely fill a 300 mi bottle with a green leafy vegetation.
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| Record sample weight and radioassay on a Ge(Li) detector. Calculate the ob-served gamma esitting nuclides in pCi/gm wet.
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| i
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| . Soil and Sediment / Silt Gamma Isoteoic Analysis Fill a 300 m1 bottle with soil, record the sample weight, and !
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| radioassay on a high resolution Ge(Li) detector. ,
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| !
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| Strontium-89/Stronium-90 Weigh an aliquot of dry soil or sediment and transfer to a 1-liter f
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| ;
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| beaker. Add strontium carrier and concentrated HNO3 ; then heat the sample for 2 hours to leach strontium from the soil. Filter the resulting solution, <
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| wash the precipitation with hot water, and discard the residue. Evaporate ;
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| the filtrate to a few milliliters and add NH 4CH until alkaline. Add' sat- 1 urated Na,CO solution to precipitate SrC03, and centrifuge and discard l
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| ;
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| supernate! dissolve precipitate in HNO3 and evaporate to almost dryness.
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| Proceed with Sr-39, Sr-90 purification procedures using fuming nitric acid, l an Fe(CH)3 scavenge, etc.
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| i
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| !
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| i 1
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| l 13 i
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| _ _ _ . _ _ _ _ _ .
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| . . - _ . _. . . - . _.
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| _ . - . _ _ .
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| TTELEDYNE l ISOTOPES l
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| l ABSTRACTS OF THE RADI0 ASSAY PROCEDURES l
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| '
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| The lower limits of detection for radionuclides by the radioassay procedures are listed in Table 3.
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| * Gross Beta Evaporated or solid phase aliquots are transferred to a 2-inch diameter stainless steel planchet and counted in a low level gas flow thin window Geiger counter.
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| Ge(Li) Gamma Soectrometry Based upon the specific media to be analyted, samples are counted in 1-liter wrap-around Marinelli type containers, 300 mi bottles or 2-inch filter paper source geometries on 55 cc Ge(Li) detectors coupled to multi-channel spectrometers. All resultant spectra are maintained on magnetic tape for computer analysis and for future reference.
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| Strontium-89/Strentium-90 After decomposition and radiochemical separation and purfication, mounts of Sr-89 and Y-90 are counted in a low level gas flow thin window Geiger counter. Nuclide purity is established by counting over at least one half-life for Y-90 and by multiple counts for Sr-89.
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| ,
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| Tritium An aliquot of distilled sample is added to scintillation cocktail and counted in a liquid scintillation spectrometer, or converted to the gaseous phase and counted in an internal gas proportional counter depending on sensitivity requirements.
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| Iodine-131 Mounts are counted in a low level gas flow thin window Geiger coun-ter. Nuclide purity is established by counting over at least one half-life.
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| Positive detections of I-131 are also verified by ecunting on a beta-gamma coincidence spectremeter. -
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| Rare Gases Purified fractions are assayed in internal gas proportional counters.
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| ,
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| .
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| ;
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| h I
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| t
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| ,
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| 14 l
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| i
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| . - .
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| . . . - . . . .. . . .
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| T TELEDYNE ISOTOPES TABLE 3 LOWER LIMITS OF DETECTION
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| * *
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| * LLD 6 Sampled Volume Sample Analysis Reporting Units Required
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| : 1. Airborne Particulate 3 Gross Alpha 2.5x10[3 pC1/m 125 m Gross Beta 7.6 x 10 pCi/m Ge(Li) Gamma Isotopic See Table 3.2 1625 u 3 ,
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| : 2. Airborne Iodine ~
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| ,
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| Charcoal Cargridge I-131 ** 2.4 x 10 pC1/m 125 m
| |
| : 3. Direct Radiation '
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| TLD Environmental Badge 2 mR 2 2 mR
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| : 4. Milk !
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| Sr-90 0.8 pCi/1 4 liters I-131 by Chemical Separation 0.5 pCi/1 Ge(Li) Gamma Isotopic (Cs-137) See Table 3.2 Cs-137 Chemical Separation 3 pCi/1
| |
| .
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| : 5. Well Water Gross Alpha 0.5 pCi/1 2 liters ;
| |
| Gross Beta 0.5 pCi/1 Tritium (gas count) 100 pCi/1 Ge(Li) Gamma Isotopic See Table 3.2 ,
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| .
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| : 6. Surface Water Gross Beta 0.5 pC1/1 2 liters Tritium (gas count) 100 pCi/1 ,
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| Ge(Li) Gamma Isotopic See Table 3.2 -
| |
| : 7. Fish: Flesh Gross Beta plue K-40 0.1 pCi/gm wet (2) 1 Kg Ge(Li) Gamma Isotopic See Table 3.2 Sr-89 *0.8 pCi/gm i Sr-90 *0.5 pCi/gm
| |
| : 8. Vegetation (corn, leaf, food, ;
| |
| terrestrial, aquatic) l Ge(Li) Gamma Isotopic See Table 3.2 (2) 1 Kg Sr-89 0.8 pCi/gm -
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| Sr-90 0.5 pCi/gm
| |
| : 9. Soil Ge(Li) Gamma Isotopic See Table 3.2 1 Kg
| |
| : 10. Silt i Ge(Li) Gamma isotopic See Table 3.2 (2) 1 Kg Sr-89 0.3 pCi/gm Sr-90 0.5 pCi/gm 15 l
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| | |
| . _ _ _
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| i t
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| 'PPTELEDYNE '
| |
| ^
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| M90 TOPES
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| >
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| TABLE 3.2 LOWER LIMITS OF DETECTION BY HIGH RESOLUTION Ge(Li) G#NA SPECTRCSCOPY ENVIRONMENTAL SMtPLES ,
| |
| * Water (1 liter) Soil 6 Vegetation Filters Nuclide pCi/1 (400 gm) pCi/gm pCi/ total filter Be-7 8E+01 2E-01 2E+01 K-40 2E,+02 SE-01 SE+01 Cr-51 SE+01 2E-01 8E+01 Mn-54 8 2E-02 2 Co-58 8 2E-02 2 Fe-59 1E+01 4E-02 3 ;
| |
| Co-60 8 2E-02 2
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| {
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| Zr-95 1E+01 4E-02 3 l
| |
| '
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| Ru-103 8 2E-02 2 ,
| |
| Ru-106 8E+01 2E-01 8E+01 1-131 10 3E-02 2 . ,
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| Cs-134 9 2E-02 2 ;
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| Cs-137 9 2E-02 2 Ba-140 3E+01 8E-02 6
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| '
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| La-410 2E+01 4E-02 2E+01 Ce-141 2E+01 4E-02 3
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| '
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| Ce-144 SE+01 2E-01 2E+01 Ra-226 6E+01 1E-01 1E+01
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| ,
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| Th-22S 1E+01 2E-02 1E+01 16
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| ,
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| .
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| TTELEDYNE
| |
| --
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| ISOTOPES TABLE 3 LOWER LIMITS OF DETECTION
| |
| * Detectito in limits as stated are per gram of ashed material. The actual detectic, 11eirF in pCi/gm (wet) will vary by a factor of 10-100, depending on the wes .arsus ash weight factor.
| |
| ** Analysis by chemical separation and beta counting of PdI2 . The non-impregnated with elemental iodine charcoal cartridges must be used when chemical separation is required.
| |
| '" The LLD values listed in this table are at the mid-collection time. Samples must be counted within one half-life after collection for these LLD values to be applicable.
| |
| LLD =
| |
| 3.29 h _
| |
| 4.66 (Ref. 10) 2.22 (V)(c)(DF) 2.22 (V)(c}(DF)(Y)
| |
| { i where S= background = cpm at = counting time = min.
| |
| 2.22 = conversion factor =
| |
| V= volume or weight of sample c= counter efficiency i
| |
| DF = decay factor of the radionuclide from mid-collection to mid-count time Y= chemical yield LLD = lower limit of detection at the mid-collection time i
| |
| 17
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| -_ _ - _ _ _ _ _ _ _
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| .
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| TTELEDYNE ISOTOPES i
| |
| QUALITY CONTROL OF ANALYSIS Important elements of the Quality Control Program at Teledyne Iso-topes are (1) Sample and Analysis Control and (2) Laboratory Procedure Con-trol.
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| '
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| Details of these elements of the Quality Control Program are provided in separate documents and issued to our customers on a proprietary basis.
| |
| : 1. Sample and Analysis Control All samples arriving at our laboratories are assigned a T.I. code number and are processed by the procedures described in our " Quality Control i
| |
| Manual" (Ref. 9 ) . Copy No. 14, latest revision date of 01/1S/78, of the manual has been issued to the Virginia Electric and Power Company. .
| |
| l The Quality Control Manual contains (a) Specifications for the handling and processing of samples and the documentation required for calculating and reporting the ,
| |
| results of the analysis.
| |
| ;
| |
| l (b) The organi:ation chart of the Environmental Analysis Group at Teledyne Isotopes and the resumes of supervisory personnel.
| |
| (c) References to the routine stability checks of backgrounds and ,
| |
| standards required for the calibration of the counting instru- !
| |
| ments used for radioassaying of samples. l (d) References 'to the operational checks on blanks, spikes, splits, l and cross checks of samples. l (e) A section on accuracy checks containing summaries of inter-l comparison data with EPA cross check programs
| |
| :
| |
| I
| |
| : 2. Laboratory Procedure Centrol Approved laboratory procedures are followed ,at Teledyne Isotopes for the analysis of each sa=ples media for specific radionuclides. Copies ;
| |
| of the following procedures were issued to the Virginia Electric and Power Company: Determination of Radiostrontium, Determination of Radiciodine, Detection of Gross Alpha and/or Gross Beta, Determination of Gamma Spectra, Determination of Tritium.
| |
| !
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| !
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| l l
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| 13 l
| |
| 1 i
| |
| | |
| _
| |
| | |
| ==SUMMARY==
| |
| OF QUARTERLY RESULTS AND DISCUSSION FIRST QUARTER 1979
| |
| .
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| .
| |
| :
| |
| !
| |
| _
| |
| | |
| TTELEDYNE s ISO 1DPES EXCEPTIONS AND SPECIAL EVE.YTS (JANUARY 1,1979 - MARCH 31,1979) ,
| |
| L EXCEPTIONS
| |
| !
| |
| During the first quarter of 1979 one group of air particulate (AP) filters (collected during the week of 02/27-03/06) was lost in transit. A.P. filters were shipped via U.S. Air Mail and the same carrier was probably used for the lost filters. Maximum in-transit times are 5-6 days for filters shipped by U.S. Air Hall. These filters are now shipped via UPS.
| |
| Charcoal filters are shipped by UPS and the maximum in-transit time has been S-6 days. No charcoal filters have been lost in transit.
| |
| Reducing the time between collection and shipment of charcoal filters is recommended for best analysis of the I-131 and charcoal filters should be shipped on the collection date or no more than one day after collection.
| |
| '
| |
| No precipitation sample was received during February 1979.
| |
| SPECIAL EVENTS ,
| |
| - During the first quarter of 1979 no unususi events occurred that could I
| |
| ,
| |
| be interpreted as possibly related to the operations of the North Anna ;
| |
| Power Station. The last atmospheric nuclear test was conducted by the Peoples Republic of China on December 13, 1973 at Lop Nor in Central Asia and no worldwide fallout from this test was detected in the vicinity of the North ,
| |
| Anna Power Station.
| |
| i i
| |
| e
| |
| !
| |
| h l
| |
| 19-A
| |
| | |
| ._ - . - _ _ _ _.
| |
| TTELEDYNE ISCTTOPES SUSNARY OF QUARTERLY RESULTS AND DISCUSSION AIRBORNE EXPOSURE PATHWAY :
| |
| (JANUARY 1,1979-MARCH 31,1979)
| |
| AIR PARTICULATE FILTERS (STATIONS 1-7, 21-24)
| |
| Air particulate filters collected weekly from eleven stations were analy:ed , weekly for gross beta activity and a composite was analy:ed quarterly for gamma emitting nuclides. Summari:ed in Table 4 are the measured gross beta activities and Be-7, the only gamma activity detected.
| |
| The gross beta activity during this quarter is lower than measurements (See Fig. 3) since 1977. Concurrent with the low gross beta activity, the Ce-144 activity is below the limits of detection. No measurable fission or activation products were detected from the December 13, 1978 atmospheric nuclear test by the Peoples Republic of China.
| |
| In addition no detectable airborne radionuclides were detected at any station in the North Anna environs indicating no detectable airborne releases -
| |
| l of fission or activation products from the North Anna Power Station.
| |
| AIR RADI0 IODINE (STATIONS 1-7, 21-24)
| |
| ,
| |
| No I-131 was detected during this qua'rter on the Charcoal filters at the air radiciodine stations in the North Anna Power Station environs. Thus no releases of airborne radiciodine were generated above the limits of ;
| |
| detection from the North Anna Power Station.
| |
| PRECIPITATION (STATICN 01)
| |
| Rainfall samples collected in January and March 1979 contained low levels of beta activity (0.38 and 0.42 nei/sq.m) in the same order of magnitude as monitored in the 4th quarter of 1978.
| |
| SOIL Soil samples are analy:ed once every three years and are not scheduled during this quarter. l
| |
| * i
| |
| !
| |
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| 20-A
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| FIGURE 3 Is , i , . . ,
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| * NCRTH ANNA PCWER STATICN
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| |
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| o AIR PARTICULATE FILTERS
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| m .m u QUARTERLY AVERAGE CF CE-144
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| 21 1979 1250 1981 1977 1973
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| TABLE 4 TTELEDYNE RSOTOPES RADIOLOGICAL ENVIRONNENTAL NONITORING PROGRAN SUNNARY VIRGINIA ELECTRIC 8 POWER CONPANY CONTROL LOCATION - STATION 24 NORTil ANN A POWER STATION PAlllW AY- AIRBORNE SAHPLE - AIR PARTICULATE FILTERS UNITS pC6/CU.N.
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| ALL INDICATOR SANPLES LOCATION WITil llIGilEST MEAN CONTROL LOCATION- NON- REPORTING PERIOD ANALYSIS NO LINIT OF ROUTINE DETECTION HEAN HEAN NEAN RANGE STATION FRACTION RANGE RANCE PRACTION STATION DESCRIPTION PRACTION Gruss S 132 0.0076 0.037 0.051 0.051 0 01/02/79-04/03/79 0.026-0.05I 24 10/12 0.008-0.076 0.005-0.076
| |
| !!9/132 ORANGE: 22.0m1.325 Jeg.NN(Control)l0/12
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| -
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| Sr-90 - 2nd quarter only - - -
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| . - .
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| Genoa II - - -
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| -
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| g Isotupic Ro-7 - 0.012 0.0495 0.0599 0.0568 0 0.0342-0.0599 23 1/1 - -
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| 11/18 Aspen ll!!!s 0.9 miles, 158 degrees 1/1
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| .
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| Cs-137 - 0.0012 LLD LLD LLD
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| - -
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| 0/11 Co-844 - 0.012 LLD LLD LLD
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| * 0/81
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| _ _ _ - _ .-. , , _ . - .. - __ _ _ _ _
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| _.
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| !
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| TARLE 4 T TFJiD(NERSOTOPES RADIOLOGICAL ENVIRONNENTAL NOMITORING PROGRAN SUNNARY VIRGINIA ELSCTRIC 4 POWER COMPANY ORDI ANNA ?OJER STATION CONTROL I.0 CATION - STATION 24 PATilNAY- AIR RADIOIODINE SAMPLE - Cll ARCO AL PI LTERS UNITS - p C I /Cu . N.
| |
| ANALYSIS NO LINIT OF ALL INDICATOR SAMPLES LOCATION WITil IllCilEST NEAN CONTROL LOCATION NON- REPORTING PERIOD DLTECTION NEAN NEAN NEAN ROUTINE RANGE STATION FRACTION RANCE RANGE FRACTION STATION DESCRIPTION FRACTION I-I3L 132 0.024 L.T. 0.020 LLD LLD 0 0I/02/79-04/03/79
| |
| - None 0/12 - - -
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| 8/I32 - 0/12
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| 22
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| __ _.._ ___ .
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| ._. _
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| l TABLE 4 TTELEDVNE RSOTOPES anOnot0G: CAL ENY nONNeNTAL NON TORING PROGRAN SUNNARY vgBGINIA ELECTRIC 4 POWER COMPANY CONTROL LOCATION - STATION 24 PATHW AY- AIRRORNE S A MP I.l: - PRECIPITATION UNITS - pC6 / LITER 4 NCf/SQ.N.
| |
| ANALYSIS ND LIMIT OF ALL INDICATOR SAMPLES LOCATION MITil tilGitEST NEAN CONTROL LOCATION ~ NON. REPORTING PERIDO DETECTION NEAN NEAN NEAN ROUTINE RANGE STATION FRACTION BANGE RANCE PRACTION STATION DESCRIP1m0N FRACTION Grass Rets 3 0.08 3.8 SimEle collection station. None 01/01/79-03/31/79 pct / liter 3.4-4.1 Station 1 ON SITE. 0.2Niles.
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| 2/3 42 degrees N inches rainfall 4.2 - -
| |
| 3.6-4.8
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| '
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| 2/3 Gross nota nCl/sq.m. 0.40 0.38-0.42
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| - -
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| Q 2/3
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| TARLE 4 WTELEDYNE RSOTOPES RADIOLOGICAL ENVIRONNENTAL NONITORING PROGRAN SUNNARYVIRGINIA ELECTRIC 4 POWER COPANY
| |
| " " "
| |
| CONTROL LOCATION - STATION 24 PATitWAY- AI RBORNE SAMPLh -SOIL UNITS - pC1/ gm DRY ANALYSIS NO LINIT OF ALL INDICATOR SAMPLES LOCATION WITII IIIGHEST MEAN CONTROL LOCATION- NON- REPORTING PERIOD DETECTION NEAN NEAN NEAN ROUTINE RANGE STATION PRACTION RANCE RANGE PRACTION STATION DESCRIPTION PRACTION SOIL SAMPLES ARE COLLECTED AND ANALYZED ONCE EVERY THREE YEARS POR Sr-89, St-90 AND GANNA SPECTRA-NO ANALYSIS ARE SCllEDULED DURING JANUARY l-NARCal 31, 1979
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| @@W
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| M TELEDYNE.
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| ISOTOPES
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| | |
| ==SUMMARY==
| |
| OF QUARTERLY RESULTS AND DISCUSSION
| |
| ;
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| DIRECT EXPOSURE PATHWAY
| |
| !
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| ' (JANUARY 1,1979 - MARCH 31,1979) ,
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| ENVIRONMENTAL GA.W DOSE (STATIONS 1-7, 21-24)
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| The environmental gamma dose levels were monitored at the same stations as the airborne exposure samples. The mean dose level during the first quarter of 1979 is 0.15 mr/ day. Plotted on Figure 4 are the quarterly average environmental dose levels from 1977 to the 1st quarter 1979. The !
| |
| mean level of 0.15 mr/ day is the icwest dose since 1977. Summari:ed in REMPS Table 5 are the mean, range, and detections / total for the environ-mental gamma dose.
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| TTELEDYNE -
| |
| ~ ISOTOPES SU4!ARY OF QUAPTERLY RESULTS AND DISCUSSION
| |
| ' WATERBORNE EXPLSURE PATHWAY JANUARY 1, 1979 MARCH 31, 1979
| |
| .
| |
| !
| |
| SURFACE WATER (STATIONS 08,09,11)
| |
| The I-131 and gamma activity in surface water remained at less than ,
| |
| the limits of detection (LLD) during the 1st quarter of 1979. Tritium activity at Station 03(discharge cooling) increased to 940 pCi/ liter, the highest H-3 level since the start up of Unit #1.
| |
| Tritium activity at Station 09(Reservoir) dropped to 240 pCi/ liter from 600 PCi/ liter in the 4th quarter of 1978.
| |
| Plotted on Figure 5 is the 940 pCi/ liter activity of H-? at station 08, discharge cooling.
| |
| Tritium activity at Station 11 (RIVER) remained at approximately 830 pCi/ liter.
| |
| Tablulated in REMPS Table 6 are summaries of the monitored radionuclides.
| |
| !
| |
| ^
| |
| GROUND WATER (STATICN LA)
| |
| Ground Water samples from the Environmental Well, contain no gamma emitting nuclides and the tritium activity remains low at 100 pCi/ liter.
| |
| -
| |
| AQUATIC SEDDfENT AND SHORELINE SOIL (5,TATIONS OS and 09)
| |
| Aquatic sediment samples from stations 08 and 09 and a shoreline sample from station 09 were monitored for gamma emitting nuclides. The usual radio-nuclides, K-40, Cs-137, Ra-226 and Th-228 found in sediments and soil were detected. No radionuclides that could be attributed to operations of the North Anna Nuclear Power Station were detected above the limits of detection of the monitoring systems.
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| !
| |
| TTELEENNE ISOTOPES RADIOLOGICAL ENVIRONNENTAL NONITORING PROGRAN SUNNARY VIRGINIA ELECTAIC 4 PONER COMPANY NORTil ANN A PONER STATION P ATilW AV - N ATE R RORNE S AMPLL - GROUND NATER '
| |
| UNITS - pC S / LI Tlit ANALYSIS NO LINIT OF ALL INDICATOR SAMPLES LOCATION NITil ilIGilEST NEAN CONTROL LOCATION NON- REPORTING PEtt0D ptTECTION HEAN NEAN hEAN ' ROUTINE RANGE STATION FRACTION RANGE RANGE FRACTION STATION DESCRIPTION PRACTION Gamma i Table 3 LLD. Singl'e location Single Location 08/01/79-03/31/79 I*** I' I "
| |
| 0/8 Station el al- 3 ,
| |
| t 800 800 Single location Slugte location 01/03/79-03/31/79 1/8 Station on w
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| -- ._. . ._____. _ _ _ _ _ _ _ ___ __ _ _ , _ _ _
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| -- --
| |
| .
| |
| .
| |
| TTELED(NE ISOTOPES RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAN SUNNARY VIRGINIA RLECTRIC 4 POWER CONPANT CONTROL LOCATION - STATION 09 NORTil ANNA POWER STATION P ATiiW A Y - W ATliR BO RN E S AMPLL '- StiblHhNT. SOIL IINITS - pCl/ge. DRY ANALYSIS No LINIT OF ALL INDICATOR SAMPLES LOCATION WITil llIGilEST NEAN CONTROL LOCATION. NON- REPORTING PERIOD DETECTION NEAN NEAN NEAN ROUTINE RANGE STATION FRACTION RANCE RANGE FRACTION STATION DESCRIPTION FRACTION
| |
| -
| |
| Gamma 3 - - - -
| |
| Isotopic K-40 - 0.5 13.9 35.6 4.6 0 March 1979 1.6-35.6 08 1/1 - -
| |
| 3/3 Discharge Cooling Station I/I Cs-137 - 0.02 0.42 4.2 4.2 0 March 1979 09 t/l - -
| |
| u 1/3 Reservoir 1/8 Ra-226 - 0.1 1.9 1.9 1.9 0 1/3 Reservoir 1/5 Th-228 - 0.02 0.77 1.3 1.3 0 (r_ ;)
| |
| 0.06-1.26 -
| |
| 3/3 09 1/1 1/1 O
| |
| V. 2).
| |
| 74 JEE2 IF--'
| |
| - .. . - .
| |
| | |
| )
| |
| i TARLE 09 -
| |
| WTELEDYNE ISOTOPES RADIOLOGICAL ENVIRONNENTAL MONITORING PROGRAM SUNNARY VIRGINIA RL2CTRIC 4 POWER COMPANY CONTROL LOCATION - STATION 09 NORTil ANNA PONER STATION PATHWAY-WATERRORNE SAMPLE -SURFACE WATER UNITS -pC6/ LITER .
| |
| NO LIMIT OF ALL INDICATOR SANPLES LOCATION WITH IIIGHEST NEAN CONTROL LOCATION. MON- REPORTING PERIOD ANALYSIS DETECTION MEAN NEAN MEAN ROUTINE RANGE STATION FRACTIOh RANGE RANGE FRACTION STATION DESCRIPTION FRACTION 1-138 6 0.5 L.T. 0.4 LLD L.T. 0.4 0 01/01/79-03/31/79 0/6 - 0/6 -
| |
| 0/3 -
| |
| Station OR and 09 H-3 3 100 672 940 240 01/01/79-03/31/79 240-940 08 1/1 1/1
| |
| ,3/3 Discharge cooling Mater Gamma 7 Table 3 LLD LLD LLD 0 01/01/19-03/31/79 luotopic -
| |
| 0/3 - -
| |
| 6/7 Stations Oh, 09 and 11 0/3 0
| |
| Y (c o)
| |
| (cc o)
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| |
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| |
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| |
| ,
| |
| .
| |
| >&
| |
| --
| |
| | |
| .
| |
| TTELEDYNE N RADIOLOGICAL ENWIRONNENTAL NONITORING PROGRAN SUNNARY VIRGINIA RLRCTRIC 4 PONER CONPANY CONTROL LOCATION - STATION 09 NORTil ANNA POWER STATION PAlllW AY- WATE RaORNE SAMPLE - 50ll - VICINITY STATION 09 ,
| |
| UNITS - pC1/gmDRY ANAL.YSIS NO LIMIT OF ALL INDICATOR SAMPLES LOCATION NITil IllGitEST NB AN CONTROL LOCATION MON- REPORTING PERIOD l>ETECTION NEAN MEAN NEAN ROUTINE RANGE STATION PRACTION RANGE RANGE FRACTION STATION DESCRIPTION PRACTION ,
| |
| ,
| |
| Camma I - Single Station on the I"***P I " Shoreline of Station 09 March 1979 K-40 - 0.5 5.53
| |
| .
| |
| 1/1 Cn-137 - 0.02 0.069 Single Station - Shorellne of 1/1 Station 09 March 1979 Ra-226 - 0.1 LLD Single Station - Shoreline of March 1979 Station 09 Th-22a 0.02 0.44 Single Station - Shoreline of March 1979
| |
| { ~})
| |
| -
| |
| 1/1 -
| |
| Station 09
| |
| )
| |
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| |
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| |
| | |
| - . _ _ . . .__.
| |
| TTELEDYNE -
| |
| ISOTOPES SUM 4ARY OF QUARTERLY RESULTS AND DISCUSSION INGESTION EXPOSURE PATHWAY (JANUARY 1,1979-MARCH 31,1979)
| |
| .
| |
| MILK (STATIONS 12,13, and 14)
| |
| Milk samples were analy$ed for low levels of I-131, for Sr-89, Sr-90 and for gamma emitters. Summari ed in Table 7 are the levels of activities of these radionuclides measured during this quarterly period. Plotted on Figure 6 is the quarterly average of Sr-90 in milk.
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| |
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| _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ ___ _
| |
| _ _.
| |
| TABLE 7 TTELEDVNE SSOTOPES RADIOLOGICAL ENVIRONNENTAL NOMITORING PROGRAN SUNNARY
| |
| * CatfROL- AVERAGE OF PREVIOUS T11RiiE QUARTERS VIRGINIA ELECTRIC 4 POWER CO.
| |
| NORTil ANNA POWER STATION P ATl!W AY- INGESTION S ANPLL - NILE llNITS - pCl/ liter ANALYSIS NO LIMIT OF ALL INDICATOR SAMPLES LOCATION WITil llIGilEST NEAN CONTROL LOCATION NON- REPORTihG PERIOD DETECTION HEAN MEAN HEAN ROUTINE RANGE STATION FRACTION RANGE RANGE FRACTION STATION DESCRIPTION FRACTION I-131 9 0.5 LtD LLD LLD 0 01/01/79-03/31/79-
| |
| . . .
| |
| 0/9 0/27 Sr-89 3 8 Ll2 LID LID 0 01/01/79-03/31/79
| |
| . . .
| |
| 0/3 0/9 St-90 3 0.8 2.5 3.2 3.3 0 01/01/79-03/31/79 1.4-3.2 13 1/1 . 3.0 3.6 3/3 FREDERICKS IIALL 9/9 Gamma 9 - -
| |
| E-40 200 3200 1300 1865 0 01/01/79-03/31/79 1100-1300 12 3/3 1080-1430 !!32-1203 9/9 Il0LIADAY DAIRY 8.3 Miles, 310 deg 27/27
| |
| * Os- 1 it - 9 Lla lid 10 0 01/01/79-03/31/79
| |
| ,
| |
| -e -
| |
| 9/27
| |
| ;
| |
| 0/9 9
| |
| - . - - . . , , , . - - - - . .,v. .- - - - , -. ,. ..m - - - - , - n
| |
| | |
| .
| |
| CONCLUSICNS TTELEDYNE (JANUARY 1,1979-MARCH 31,1979)
| |
| *
| |
| -
| |
| ISOTOPES The first quarter summaries of the analysis performed for the Radiological Enviratmental Monitoring Program (REMP) in the environs of the North Anna
| |
| -
| |
| Power Station (NAPS) are presented in this report. These scamaries compared to data monitored in previous years indicates that no detectable increases have occurred except for an increase in tritium activity at the surface water discharge cooling (station 08). (Ref.13)
| |
| Considering each of the exposure pathways these are the conclusions from the measured radioactivities.
| |
| AIRBORNE EXPOSURE PATHWAY
| |
| . In the airborne exposure pathway, the levels of gross beta in air particulates decreased to the lowest level in two years as shown in Figure 3. .
| |
| . No Ce-144 or other fission products were detected in air particulate filters indicating no measurable releases of these radionuclides from possible t sources: NAPS or from worldwide fallout from the December 13, 1978 atmos-pheric nuclear test by the Peoples Republic of China.
| |
| . No airborne 1-131 was measured on charcoal filters above the limits of detection of less than 0.024 pC1/Cu.m.
| |
| . The deposition of airborne beta emitters in precipitation was lower than ;
| |
| in previous quarters supporting the conclusion that radioactivity levels ;
| |
| . are minimal and not from operations of NAPS. '
| |
| DI'.<ECT EXPOSURE PATHWAY-
| |
| . In the direct exposure pathway the mean environmental gamma dose ,
| |
| (see Figure 4) was 0.15 mr/ day, the icwest mean exposure in several !
| |
| years. The low gamma dose is consistant with the low airborne radio-activity.
| |
| -
| |
| WATERBORNE EXPOSURE PATHWAY
| |
| . Waterbotne tritium from the NAPS operations has been measured at above 700 pil/ liter in the cooling water discharge (Station 03) since the ,
| |
| initial operation of Unit 1. During this 1st quarter of 1979 the H-3 [
| |
| activity is 940 pCi/ liter. These are the only detections of radionuclides ,
| |
| from NAPS and pose no threat to the population since the discharge water !
| |
| is not a direct source of drinking water. If the 940 pCi/ liter of tiated water was ingested the total body dose would be less than tri- l 0.1 mrem / year, neglible compared to the 17 mrem / year K-40 internal con- !
| |
| stituent of the body.
| |
| . No radionuclides attributed to operations of NAPS were detected in ground water or in sediment samples.
| |
| INCESTION EXPOSURE PATHWAY
| |
| . Milk samples, a possible source of ingested radienuclides, were monitored for low levels (L.T. 0.S pCi/ liter) of I-131, for gamma emitters and for Sr-39, Sr-93. No I-131 was detected, and K-40 and Sr-90 was monitored at the normal concentrations in milk. Thus milk samoles in the vicinity of NAPS are not a source of ingested radionuclides from NAPS operations.
| |
| 38-A
| |
| .
| |
| w+
| |
| | |
| _
| |
| .
| |
| -
| |
| .
| |
| TTELEDYNE -
| |
| -
| |
| ISOTOPES TABLE 8 ,
| |
| !
| |
| RADIATION DOSE TO THE INDIVIDUAL FRGl NATURAL AND ARTIFICIAL SOURCES (FROM REF.11)
| |
| Natural and Artificial Annual per Capita Source In Excesure Source Whole Body Dose Ref. 11 i
| |
| Ambient external gamma 55 mrem / year Page 36, Table 2-13 (Virginia)
| |
| ,
| |
| Medical - bone marrow dose 103 mrad / year Page 213, Table 8-3 ;
| |
| to the adult population 1970 ,
| |
| ,
| |
| K internal constitutent 17 mrem / year Page 29, Table 2-9 of body for beta, and gamma '
| |
| whole body !
| |
| Global fallout - total annual 4.4 mrem / year Page 131, Table 4-10 per capita body dose, est. 1980 :
| |
| ,.
| |
| .1
| |
| >
| |
| !
| |
| r e
| |
| ?
| |
| e 39
| |
| | |
| _-
| |
| .
| |
| .
| |
| ;
| |
| . . _ . _. ...
| |
| 7
| |
| -
| |
| , TTELEDYNE <
| |
| '
| |
| ISOTOPES l REFERENCES .
| |
| : 1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8
| |
| " Environmental Technical Specifications for Nuclear Power Plants,"
| |
| December 1575.
| |
| : 2. Quarterly repcrts on the Environmental Radiological Monitoring Pro-gram (ERMP) at the North Anna Power Station prepared by Teledyne ,
| |
| Isotopes (IWL-0208-345 and 359 July-December 1974) .
| |
| : 3. Quarterly reports ot the ERMP at the North Anna Power Station prepared by Teledyne Isotopes (IWL-0268-364, 367, 371, 375, and 376 January-December 1975). l t
| |
| : 4. Quarterly reports on the ERMP at the North Anna Power Station prepared by Teledyne Isotop2s (IWL-0268-387, 394, and 395 January-December 1976). ,
| |
| S. Quarterly reports on the ERMP at the North Anna Power Station prepared !
| |
| by Teledyne Isotopes (IWL-5343-406, 407, 413, 423, and 429 January-December, 1977). .
| |
| : 6. Teledyne Isotopes " Environmental Monitoring Summary - Preoperational l Program - July 1, 1974 - September 30, 1977 IWL-5343-426. Prepared for Virginia Electric and Power Comoany (NAPS).
| |
| : 7. Appendix B to Operating License, Environmental Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and l
| |
| ;
| |
| Power Company, Docket Nos. 50-338 and 50-336. 1
| |
| : 8. Virginia Electric and Power Company, Radiological Environmental Moni- i toring Manual, June 1977. ,
| |
| I
| |
| : 9. Teledyne Isotopes, " Environmental Radiation Analysis Quality Control Manual," IWL-0032-361,197S, Copy No.14 issued to Virginia Electric and Power Company.
| |
| 1 10. Energy Research' and Development Administration, HASL Procedures Manual, (HASL-300, D-08) .
| |
| : 11. United States Environmental Protection Agency. " Radiological Quality '
| |
| of the Environment in the United States,1977" EPA 520/1-77-009, Sep-tember 1977.
| |
| : 12. United States Nuclear Regulatory Commission. Regulatory Guide 1.109, l " Calculation of Annual Doses to Man from Routine Releases of Reactor i
| |
| Effluents for the Purpose of Evaluating Compliance with 10CFR50, Ap-pendix I," October 1977.
| |
| : 13. Quarterly reports of the REMP at the North Anna Power Station prepared by Teledyne Isotopes, IWL-6343-432; Jan 1,1973-Dec. 31,1973. ,
| |
| s 40
| |
| | |
| -
| |
| :
| |
| .
| |
| =
| |
| APPENDIX A - DATA TABLES i e
| |
| I FIRST QUARTER 1979 i
| |
| l
| |
| !
| |
| l
| |
| .
| |
| 6
| |
| | |
| -
| |
| I
| |
| -
| |
| l APPENDIX A TTELEDYNE ISOTOPES TAtl2 0F CONTENTS (JANtfARY I - MAROI 31. 1979)
| |
| Esponere Analytical ratiway Sample Analysis Data Al s teurne Air Particulate Cross bets (even) A-2 A-22 Comma Isotopic (oJJ) A-3 A-23
| |
| .
| |
| Air RaJioloJ!ne I-833 (evon) A-2tA-22 Frecipitation Cross tota A-24
| |
| -
| |
| a Direct TIR Camma Jose A-25 Wa t e n terne Discharge Water (8) I-838 Camma Isotopic, A-26 Tritium Reservoir Water (9) I-131 Camme Isotopic. A-27
| |
| , Trl t tum o
| |
| "
| |
| North Anna River (!!) Camma Isotopic. A-28 Tritium Well Water (01) Comma Isotopic. A-29 Trit!um .
| |
| Sediment /Sitt Comma isotopic A-30:A-32 So!I Shoreline Comes Isotopic A-33 Ingestlun MllL I-131 Camme '4 totopic A-34
| |
| .
| |
| 9
| |
| -- - , n , -- - ,- , ,--,--~--,..--v.,- ., , - , - -rv -a - , , . - - - , - , - -,-,r , - < --, - -. , - ,
| |
| | |
| _. .. _ _ _ _ -
| |
| _ _
| |
| r
| |
| .i I
| |
| -
| |
| TTELEINNE ISOTOPES NORT)f ANNA POWER STATIoM AIR PARTICutATE 4 ORACOAL PILTERS STATIoM Ntmeta el
| |
| .
| |
| 1 MID CotsfT
| |
| '
| |
| COLitCTIoM DATE MIO GUNT AP FILTER CHARGML FILTER.
| |
| sTAar sTOP TIME GROSS BETA TIME I-131 DATE DATE V0818E 48d17S Daft (pC1/Os.M) DATE (pCi/Cha.M) 0 /02/7s Ot/0s/79 1.37e 02 Cu. M. 03/is 5.3 +-0.7 E-s2 03/16 L.T. s. E-03 03/23 3.0 +-0.6 s-02 08/25 L.T. 6. E-03 :
| |
| c /os 01/86 1.3sE 02 Co. M.
| |
| O / t e. 01/23 1.40s 02 Cu. M. 01/31 3.5 +-0.8 E-02 01/31 L.T. 6. E-03 04/23 03/30 3.3se 02 Co. M. 02/G7 1.4 *-0.6 E-02 02/06 L.T. 9. E-03 I
| |
| c1/30 02/06 a.4te 02 Co. M. 02/15 1.4 +-0.5 E-02 02/14 L.T. 9. E-03 7, 02/06 02/13 1. tit 02 Cu. M. 02/23 3.4 +-0.8 E-02 02/22 L.T. 8. E-03 02/ 3 02/27 2.6sE 02 Cu. M. 03/16 1.0 + 0.3 E-02 03/07 L.T. 5. E-03 02/27 03/06 tost TnANSIT 03/12 L.T. 6. E-03 i
| |
| :
| |
| 03/06 03/13 a.37r Cu. M. 04/05 3.7 +-0.5 E-02 0 3 / 2 f. L.T. I. E-02 l 03/13 ~ o3/20 1.31 Co. M. 04/02 1.2 +-0.5 't-02 03/2e L.T. 1. E 02 03/20 03/27 1. 34 2 tit Cu. M. 04/05 3.8 +-0.7 E-02 04/04 L.T. l. E-02 03/27 04/03 SAMPLE NOT COLLECTED NOME SAMPLE NOT COLLECTED -
| |
| _ . . _ . __ _ _,_ _ _ _ __ _ _
| |
| _
| |
| | |
| R, ,
| |
| ,
| |
| MyTELEDYNE ISOTOPES NORTil ANNA F0WER STATION QUARTERLY COMPOSITE OF AIR FARTICULATES (pC1/Cu.M.)
| |
| STATION NUNRER 01
| |
| * OATE COLLECTED FIRST QUARTER SECOND QUARTER TilIRD QUARTER FOURTH QUARTER GAMMA SPECTRUM ANALYSISt RE-7 3.42+-1.85E-02 8.26+-1.168-02 L.T. 2. E-02 3.77+-1.20E-02 L.T. 5. B-02 5.22+-2.09E-02 L.T. 4 E-02 4.00+-1.24E-02 K-40
| |
| : 1. E-03 L.T. 1. E-03 L.T. 3. 8 03 L.T. 1. E-03 MN-54 L.T.
| |
| C0-58 L.T. 2. E-03 L.T. 8. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 5. E-03 L.T. 3. E-03 L.T. 4 E.03 L.T. 5. E-03 FE-59 Co-60 L.T. 2. E-03 L.T. 1. E-03 L.T. 2 E-03 L.T. 1. E-03 l ZN.65 L.T. 3. E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 4. E-03
| |
| "
| |
| ZR-95 L.T. 2. E-03 L.T. 1.. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-103 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-506 L.T. 2. E-02 L.T. 1. E-02 L.T. 3 E-02 L.T. 1. E-03 1-138 L.T. 5. E-02 L.T. 1. E-02 L.T. 3. E-02 L.T. 1. E-02 CS-134 L.T. 2. E-03 L.T. 3. E-03 L.T. 1. E.03 L.T. 1. E-03 CS-337 L.T. 2. E-05 1.82+-0.95E-03 L.T. 1 E-03 L.T. 1. E-03 RA-140 L.T. 2. E-02 L.T. 6 E-03 L.T. 1. E.02 L.T. 9. E-03 CE-141 L.T. 3. E-03 L.T. 2. E-03 L.T. 2 E-03 L.T. 3. E-03 CE-144 L.T. 8. E-03 L.T. 6 E-03 L.T. 6 E-03 L.T. 7. E-03 RA-226 L.T. 2. E-02 L.T. 1. E-02 L.T. 3 E-02 L.T. 1. E-02 TII- 2 2 8 L.T. 2. E-03 L.T. 1. E-03 L.T. 1 E-03 L.T. 1. E-03 RADIOCllEMICAL ANALYSISt
| |
| $5-89 L.T. 3. E-03 SR-90 6.2 +-1.7 E-04
| |
| , _ _
| |
| . . _ , _
| |
| . ._
| |
| | |
| _ _ - _ _ _ - - _ _ _ _ - -
| |
| _ .
| |
| ;
| |
| TTELEDYNE ISOTOPES NORTH AledA POWER STATION AIR PARTICUI. ATE 4 OLARC0AL PILTERS STATION HlMBER 02
| |
| .
| |
| COL 11CTION DATE NID COUNT AP PILTER MID COUNT ORARCDAL PILTlit STANT 510P TIME GR0ti BETA TIME I-131 DATE DATE V01290! UNITS DATE (pci/Cu.MJ DATE (pci/Cu.N) 01/02/79 01/09/79 1.37E 02 CU. N. 01/19 3.9 e-0.7 E-02 08/16 L.T. 8. E-03 01/09 08/16 1.18E 02 CU. M. 03/23 3.9 +-0.7 2-02 08/25 L.T. 8. E-03 08/16 08/23 1.19E 02 CU. M. 01/31 2.2 +-0.8 E-02 08/38 L.T. 7. E-03 01/23 01/30 1.32E 02 CU. M. 02/07 1.3 +-0.6 E-02 02/06 L.T. 5. E-05 I
| |
| 01/30 02/06 1.25E 02 CU. M. 02/15 3.5 +-0.7 E-02 02/14 L.T. 9. E-03 g 02/06 02/83 1.36E 02 CU. M. 02/23 4.7 +-0.8 E-02 02/22 L.T. 8. E-03
| |
| * 02/83 02/27 2.72E 02 CU. M. 03/36 2.4 +-0.4 E-02 03/07 L.T. 5. E-03 02/27 03/06 SAMPLE NOT COLLECTED NONE L3SS OF POWER 03/06 03/13 1.3s2 02 Cu. M. 04/05 3.9 +-0.7 E-02 03/26 L.T. 1. E-02 03/13 03/20 1.34e 02 Cu. M. 04/02 3.6 +-0.7 E-02 03/28 L.T. 8. E-02 03/20 03/27 1.36E 02 CU. M. 04/05 2.6 +-0.6 E-02 04/04 L.T. 1. E-02 03/27 04/03 1.36E n2 CU. M. 04/85 9.6 +-5.0 E-03 04/12 L.T. 2. E-02 l
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| WTELEDVNE ESOTOPES NOR118 h04A P0hfER STATION AIR PARTICULATE 4 OIARCOAL FILTERS STATION NtMBER 03 MID COUNT AP FILTl1 MID C0taff QlARCOAL FILTER Cu!.lLCTION DATE START S10P ' TIME CROSS BETA TIME 1-13I DATE DATE V0lla4E t5dITS DATE (pCl/Cu.M) DATS (pCl/Os.M) 01/02/79 01/09/79 1.35E 02 CU. M. 01/19 4.4 +-0.7 E-02 01/16 L.T. 1. E-02 01/09 01/16 1.372 02 CU. M. 01/23 3.4 +-0.6 E-02 01/25 L.T. 1. E-02 dt/la 01/23 1.lsE 02 Cu. M. Os/38 4.3 +-0.s E-02 01/31 L.T. s. E-03 08/23 01/30 1.34E 02 CU. M. 02/07 4.0 +-0.7 E-02 02/06 L.T. 1. E-02 01/30 02/06 1.36E 02 CU. M. 02/15 5.1 +-0.7 E-02 02/14 L.T. 6. E-03
| |
| { 02/06 02/83 1.35E 02 CU. M. 02/23 6.0 +-0.4 E-02 02/22 L.T. 7. E-03 02/33 02/27 2.71E 02 CU. M. 03/16 3.7 +-0.4 E-02 03/07 L.T. 6. E-03 02/27 03/06 LOST IN TRANSIT 03/12 L.T. 7. E-05 03/06 03/13 1.39E 02 CU. M. 04/05 5.4 +-0.7 E-02 03/26 L.T. 1. E-02 03/13 03/20 1.35E 02 CU. M. 04/02 4.6 +-0.7 E-02 03/28 L.T. 2. E.02 i 03/20 03/27 1.3su 02 CU. M. 04/05 3.5 +-0.6'E-02 04/04 L.T. 2. E-02 03/27 04/03 1.36E 02 CU. N'. 04/15 5.9 +-0.8 E-02 04/12 L.T. 1. E-02
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| TTELEtWNE ISOTOPES -
| |
| NOR111 ANNA POWER STATION AIR PARTICULATE 4 OIARCOAL FILTERS STATION NUMBER 04 H!D C0teF A' PIL1ER MID COUNT OIARCOAL PILTER
| |
| . COLLECTION DATt!
| |
| STOP TIHil GI.u15 BETA TlHE l-131 START DATE VOLUME UNITS DATE (pC1/Cu.N) DATE (pCl/Cu.M)
| |
| DATE 08/02/79 08/09/79 1.35E 02 CU. M. 01/19 4.3 +-0.7 E-02 01/16 L.T. 7. E-03 ,
| |
| 4.0 +-0.7 E-02 !
| |
| 01/09 01/16 1.19E 02 CU. M. 01/23 01/25 L.T. 8. E-03 08/86 01/23 1.3tE 02 CU. M. 01/31 3.5 +-0.8 E-02 01/31 L.T. 6. E-03 08/23 01/30 1.34E 02 CU. M. 02/07 3.6 +-0.6 E-02 02/07 L.T. 9. E-03 08/30 02/06 1.24E 02 CU. M. 02/15 4.0 +-0.7 E-02 02/14 L.T. 1. E-02 02/Le 02/13 1.36E 02 CU. M. 02/23 3.9 +-0.7 E-02 02/22 L.T. S. E-03
| |
| >.
| |
| E 02/l? 41/27 2.70E 02 CU. M. 03/16 2.2 +-0.4 E-02 03/07 L.T. 6. E-03 02/27 A 1' + 9 LOST IN TRANSlf 03/12 L.T. 5. E-03 03/64 03/14 1.37E 02 CU. M. '04/05 3.8 +-0.7 E-02 03/26 L.T. 1. E-02 03/13 *,3 )'2 0 1.35E 02 CU. M. 04/02 4.7 + 0.7 E-02 03/24 L . T'. 1. E-02
| |
| %'/20 s 03/27 1.372 02 CU. M. 04/05 2.7 +-0.6 E-02 04/04 L.T. 1. E-02 03/27 04/03 1.38E 02 CU. W. 04/15 4.7 +-0.7 E-02 04/12 L.T. 2. E-02 I
| |
| .
| |
| %
| |
| . . .. - . . _ _
| |
| | |
| i i
| |
| i T TELEINNElSOTOPES NORTil ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (PCl/Cu.M.)
| |
| STATION NUMBER 04 SECOND QUARTER TillRD QUARTER FOURTil QUARTER DATE COLLECTED: PIRST QUARTER GAHNA SPECTRUM ANALYSIS 5.47+-1.322-02 7.98+-1.20E-02 6.16+-i.36E-02 7.0S+-0.998-02 BE-7 E-02 L.T. 4. E-02 L.T. 2. E-02 K-40 L.T. 2. E-02 L.T. 3.
| |
| : 1. E-03 L.T. I. E-03 L.T. 9. E-04 HN-54 L.T. 1. E-03 L.T.
| |
| : 1. E'- 0 3 L.T. 1. E-03 L.T. 1. E-03 C0-58 L.T. 2. E-03 L.T.
| |
| E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 3. E-03 rE-59 L.T. 4.
| |
| : 1. .E-03 L.T. 1. E-03 L.T. 9. E-04 Co-60 L.T. 1. E-03 L.T.
| |
| E-03 L.T. 3 E-03 L.T. 2. E-03 L.T. 2. E-03 ZN-65 L.T. 4.
| |
| Y 1. E-03 L.T. 2. E-03 L.T. 9. E-04
| |
| * 2R-95 L.T. 2. E-03 L.T.
| |
| : 2. E-03 L.T. 2 ~. E-03 L.T. 2. E-03 L.T. I. E-03 RU-103 L.T.
| |
| L.T. 1. E-02 L.T. 9. E-03 L.T. 1. E-02 L.T. 8. E-03 RU-106
| |
| : 3. E-02 L.T. 1. E-02 L.T. 2. h-02 L.T. 1. E-02 1-131 L.T.
| |
| s
| |
| : 1. E-03 L.T. 1. E-03 L.T. 3. E-03 L.T. 9. E-04 CS-134 L.T.
| |
| 1.93*-0.88E-03 L.T. 1. E-03 L.T. 9. E-04 CS-137 L.T. 1. E-03
| |
| : 1. E-02 L.T. 7. E-03 L.T. 8. E-03 L.T. 5. E-03 BA-140 L.T.
| |
| L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 CE-14I
| |
| : 7. E-03 L.T. 5. E-03 L.T. 6. E-03 L.T. 4. E-03 CE-144 L.T.
| |
| i
| |
| : 8. 8-02 L.T. I. E-02 L.T. 1. E-02 L.T. 1. E-02 j RA-226 L.T.
| |
| L.T. 1. E-03 L.T. 1 E-03 L.T. 2. E-03 L.T. 1. E-03 TII- 2 2 8 RADIOCHEMICAL ANALYSIS:
| |
| SM-89 L.T. 3. E-03 SR.90 5.2 +-1.8 E-04
| |
| _ _ _ _ _ __. ___ _ _ _ _ _ _ __ _ . _ . . . _. _ .. . ._
| |
| | |
| __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
| |
| t WTELEINNE ISOTOPES MOR111 ANNA POWER STATION AIR PARTICULATE 4 OtARCOAL PILTERS STATION NtMBER .05 l
| |
| l Cott.LCTION DATE MID COUNT AP PILTER MID CDUNT OIARCOAL FILTER l START STOP TIME GROSS BETA TIME I-131 l DATE DATE Vot3ME IMITS DATE (pCl/Cu.M) DATE (pct /Cu.M) 01/02/79 01/09/79 1.34E 02 CU. M. 01/19 3.6 +-0.7 E-02 OS/36 L.T. 7. E-03 03/09 0 /16 1.35E 02 CU. M. 01/23 2.s +-0.6,E-02 01/26 L.T. s. E-03 01/16 08/23 1.39E 02 CU. M. 01/38 3.3 +-0.9 E-02 05/31 L.T. 6. E-03 08/23 ' 01/30 1.36E 02 CU. M. 02/07 2.0 +-0.6 E-02 02/06 L.T. 7. E-03 Ot/30 02/06 1.26E 02 CU. M. 02/15 4.4 +-0.7 E-02 02/14 L.T. 6. E-03
| |
| $; 02/06 02/13 1.15E 02 CU. M. 02/23 3.8 +-0.8 E-02 02/f2 L.T. 8. k-03 02/83 02/27 2.6s2 02 CU. M. 03/16 2.3 +-0.4 E-02 03/07 L.T. 4. E-03 02/22 03/06 LOST IN TRANSIT 03/I!2 L.T. 7. E-03 03/06 03/13 .345E 02 CU. M. 04/05 3.9 +-0.7 E-02 03/26 L.T. 1. E-02 03/ 3 '03/20 n.35E 02 CU. M. 04/02 4.6 +-0.7 E-t2 03/2s L.T. 3. e.02
| |
| ~
| |
| 03/20 03/27 1.3sE 02 CU. M. 04/,05 3.0 +-0.6 E-02 04/04 L.T. 2. E-02 03/27 04/03 1.39E 02 CU. M. 04/05 5.1 +-0.7 E-02 04/12 L.T. 1. E-02
| |
| .
| |
| . - . -. - , .- - -- - , - - .- . _9 - e - ,- -
| |
| | |
| e
| |
| .
| |
| .
| |
| TTELEfWNE ISOTOPES NORTH ANNA FONER STATION QUARTERLY COMPOSITE OP AIR PARTICULATES (PC1/Cu.M.)
| |
| . STATION NUMBER 05 SECOND QUARTER TillRD QUARTER FOURTH QUARTER OATE Col.LECTED: PIRST QUARTER CAHMA SPECTRUM ANALYSIS:
| |
| BE-7 4.68+-0.96E-02 1.16+-0.14E-01 7.36+-1.69E 02 7.38*-1.15E-02 E-02 L . T .' 4 E-02 L.T. 3. E-02 K-40 L.T. 2. E-02 L*. T . 3.
| |
| L.T. 2. E-03 L.T. 1. E-03 HN-54 L.T. 9. E-04 L.T. 1. E-03
| |
| : 3. E-03 L.T. 2. E-03 L.T. 1. E-03 00-58 L.T. 1. E.03 L.T.
| |
| PE-59 L.T. 3. E-03 L.T. 3. E-03 L.T. 4. E-03 L.T. 3. E-03 Co-60 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. E-03 L.T. 4. E-03 L.T. 2. E-03 2N-65 L.T. 2. E-03 2.
| |
| U ZR-95 L.T. I. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 1. E-03 RU-103 L.T. 1. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 2. E-05 R ta.106 L.T. 7. E-03 L.T. 1. E-02 L.T. 1. E-02 L.T. 8. E-03 L.T. 2. E-02 L.T. 1. E-02 L.T. 3. R*02 L.T. 3. E-02 I-131 CS-134 L.'. 8. E-04 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 CS-137 L.T. 1. E-03 1.62+-0.94E-03 L.T. 2. E-03 L.T. 1. E-03 BA-140 L.T. 1. E-02 L,T. 7. E-03 L.T. 9. E-03 L.T. 5. E-03 CE-141 T, 1. E-03 L.T. 2. E-03 L.T. 4. E-03 L.T. 2. E-03 CH-144 L.T. 3. E-03 9.4t+-4.52E-03 L.T. 1,. E-02 L.T. 5. E-03 i RA-226 L.T. 8. E-03 L.T. 1. E-02 L.T. 2. E-02 L.T. 1. E-02 T11- 2 2 8 L.T. 8. E-04 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 RAul0CllEMICAL AN ALYSIS:
| |
| I SR-89 L.T. 2. E-03 SR-90 8.1 +-1.7 E-04
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| NORT11 ANNA POWER STATION AIR PARTIQllATE 4 OlARCOAL FILTERS STATION IMSetER 06 Col.I.I.CTION DATE MID COUNT AP FILTER MID COUNT ORARCOAL FILTER START STOP TIME GROSS BETA TIME I-138 DATE DATE VOLUME tNllTS DATE (pCl/Cu.H) DATE (pCl/cu.M) 08/02/79 01/09/79 1.378 02 Cu. M. 08/19 3.9 +-0.7 E-02 01/16 L.T. 6. E-03 cu. u. 01/23 e3.4 +-0.7 E-02 01/26 L.T. S. E-03 0s/09 03/16 1.20E 02 1.03E 02 cu M.
| |
| * 01/31 4.1 +-1.0 E-02 01/31 L.T. 2. E-02 0/ 6 0 /23 0 /23 03/30 1.34e 02 cu. M. 02/07 1.3 +-0.6 E-02 02/07 L.T. 7. E-03 04/30 02/06 1.26e 02 cu. M. 02/15 3.4 +-0.7 E-02 02/14 L.T. 1. E-02 y
| |
| E cu. M. 02/23 5.6 + 0.s E-02 02/22 L.T. 7. E-03 02/06 02/ 3 1.3se 02 cu. M. 03/16 3.5 +-0.4 E-02 03/07 L.T. 8. E-03 02/ 3 02/27 2.6s2 02 IN TsANSIT 03/12 L.T. 6. E-03 02/27 03/06 LOST 1.40e 02 Cu. M. 04/05 3.5 + 0.6.E-02 03/26 L.T. 1. E-02 03/06 03/ 3 03/13 .03/20 s.36E 02 cu. M. 04/02 5.6 +-0.s E-02 03/29 L.T. 9. E-03 1.37E 02 04/05 3.4 *-0.6 E-02 04/04 L.T. 2. E-02
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| -03/20 03/,7 2 cu. M.
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| 1 T TELEET(NEISOTOPES NORTil ANNA POWER STATION AIR PARTICULATE 8 ORARCOAL PILTERS
| |
| * STATION NIMBER 07 M10 COUNT AP PILTER Mlp COIMF CHARCOAL PILTER Cott.ECTION DATE STAlt T STOP TIME CROSS BETA TIME l-131 DATE DATE VOLlHE tmITS DATE (pCl/Os.M) DATE (pC1/Cu.M) 01/02/79 08/09/79 1.36E 02 CU. M. 01/19 4.3 +-0.7 E-02 01/16 L.T. 1. E-02 '
| |
| 0l/09 01/16 1.39E 02 CU. M. 01/23 4.4 +-0.7 E-02 01/26 L.T. 1. E-02 0l/86 01/23 1.18E 02 CU. M. 01/31 4.2 +-0.9 E-02 01/31 L.T. 9. E-03 01/23 0l/30 1.35E 02 CU. M. 02/07 2.2 +-0.6 E-02 02/07 L.T. 7. E-03
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| g 01/30 02/06 1.26E 02 CU. M. 02/15 4.0 +-0.7 E-02 02/14 L.T. 1. E-02 02/06 02/13 1.39E 02 CU. M. 02/23 4.2 +-0.7 E-02 02/22 L.T. 6. E-03 02/13 02/27 2.6sE 02 CU. M. 03/16 1.7 +-0.4 E-02 03/07 L.T. 7. E-03 02/27 03/06 SAMPLE NOT COLLECTED NONE EQUIPMENT MALPUNCTION 03/06 03/13 1.392 02 CU. M. 04/05 3.8 +-0.7 E-02 03/26 L.T. 9. E-03 03/13 03/20 1.37E 02 CU. M. 04/02 4.8 +-0.7 E-02 03/29 L.T. 1. E-02 03/20 03/27 3.34E 02 CU. M. 04/05 3.6 +-0.6 E-02 04/04 L.T. 1. E-02 03/27 04/03 1.34E 02 CU. M. 04/85 5.8 +-0.8 E-02 04/12 L.T. 1. E-02
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| i TTELEDYNE ISOTOPES NORTil ANNA PONER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pC1/Cu.M.)
| |
| STATION NUMBER 07
| |
| '
| |
| .
| |
| DATE COLLkCTED: FIRST QUARTER SECOND QUARTER TillRD QUARTBR GANNA SPECTRUM ANAL.YSIS:
| |
| BE-7 4.56+-l.16E-02 7.18*-3.73E-02 4.98*-0.96E.02
| |
| !
| |
| E-40 L.T. 2. E-02 L.T. 4. E-02 L.T. 3 E-02 MM-54 L.T. 1. E-03 L.T. 2. E-03 L.T. 7 E-04 Co-58 L.T. 1. E-03 L.T. 2. E-03 L.T. 9 E-04 FE-59 L.T. 5. E-03 L.T. 4. E-03 L.T. 2 E-03 C0-60 L.T. 2. E-03 L.T. 1. E-03 L.T. 9 E-04 L.T. 4. E-03 L.T. 2 E-03 y ZN-65 L.T. 4. E-03 2R-95 L.T. 2. E-03 L.T. 2. E-03 L.T. 3. E-03 RU-103 L.T. 2. E-03 L.T. 3. E-03 . L.T. 3 E.03 R0-806 L.T. 9 E-03 L.T. 2. E-02 L.T. 6. E-03
| |
| -
| |
| I-138 L.T. 2. E-02 L.T. 4. E-02 L.T. 9 E-03 CS-134 L.T. I. E-03 L.T. 2. E-03 L.T. 8 E-04 CS-137 L.T. 3. E-03 1.97*-0.98E-03 L.T. 9 E.04 8A-140 L.T. 2. E-02 L.T. 9. E-03 L.T. 6 E-03 CE-141 L.T. 2. E-03 L_T. 5. E-03 L.T. 3. E 03 CE-144 L.T. 6 E-03 L.T. 1. E-02 L.T. 3 E-03 RA-226 -L.T. 8. E-02 L.T. 3. E-02 L.T. 7 E-03 Til- 2 2 8 L.T. 1. E-03 L.T. 3. E-03 L.T. 7 E-04 RApl0CitEMICAL ANALYSIS:
| |
| SR-89 L.T. 4. E-03 SR-90 6.8 +-1.7 E-04
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| T TELEDVNEISOTOPES Nou111 ANNA POWER STATION AIR PARTICut. ATE 4 CitARCOAL FILTERS STATION NLMBER 21
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| .
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| MID CotMT AP FILTEE NID COUNT ORARCOAL PILTER COLLLCTION DATE START STOP TIME GROSS BETA TIM! I-131 DATE DATE VOLl84! IMITS DATE (pC1/Cu.N) DATE (pC1/Cu.N) 01/02/79 01/09/79 1.35E 02 CU. M. 08/89 4.4 +-0.7 E-02 01/16 L.T. 9. E-03 01/09 01/16 1.37E 02 CU. M. 01/23 3.9 +-0.7 E-02 01/26 L.T. 7. E-03 01/16 01/23 1.03E 02 Cu. M. 01/31 4.3 +-1.0 E-02 01/31 L.T. 8. E-03 01/23 01/30 1.33E 02 Cu. M. 02/07 I.6 +-0.6 E-02 02/07 L.T. 7. E-03 01/30 02/06 1.37E 02 CU. M. 02/15 3.7 +-0.7 E-02 02/14 L.T. 8. E-03
| |
| : ?
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| ; 02/06 02/13 1.sle 02 Co. M. 02/23 4.3 +-0.s E-02 02/22 L.T. 1. E-02 02/Is 02/27 2.69E 02 Co. M. 03/16 1.3 +-0.3 E-02 03/07 L.T. 5. E-03 02/27 03/06 LOST IN TRANSIT 03/12 L.T. 5. E-03 03/06 03/13 1.402 02 CU. M. 04/05 2.5+-0.6 E-02 03/26 L.T. 2. E-02 0;/I3 03/20 1.35E 02 Cu. M. 04/02 4.5 + 0.7 E-02 03/30 L.T. s. E-03 03/.9 03/27 1.3sE 02 Cu. M. 04/05 3.3 +-0.6 E-02 04/04 L.T. 1. E-02 03/27 04/03 1.34E 02 CU. W. 04/85 ,
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| 3.6 +-0.7 E-02 04/12 L.T. 1. E-02 4
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| TTELEDYNE ISOTOPES NORTil ANNA F0wER STATION AIR FARTICULATE 4 ClfARCOAL FILTERS STATION NIMBl:R 22
| |
| .
| |
| Col.LLCTION DATE MID COUNT AP FILTER HID C0lMT CllANCDAL FILTER STANT STOP Tim CROSS SETA TIME l-131 DATE DATE VOLimE UNITS DATE (pC1/Cu.M) DATE (pCl/Cu.M) 01/02/79 03/09/79 1.35E 02 CU. M. 01/19 4.7 +-0.7 E-02 01/16 L.T. 6. E-03 01/09 01/16 1.36E 02 CU. M. 08/23 3.6 +-0.6 E-02 01/26 L.T. 9. E-03 01/16 01/23 1.208 02 CU. M. 01/31 4.9 +-0.9 E-02 03/21 L.T. 8. E-03 08/23 01/30 1.352 02 CU. M. 02/07 2.0 +-0.6 E-02 02/07 L.T. 6. E-03
| |
| > 01/30 02/06 1.23E 02 CU. M. 02/15 3.5 +-0.7 E-02 02/14 L.T. 8. E-03 l.
| |
| "
| |
| 02/06 02/83 1.10E 02 CU. M. 02/23 3.8 +-0.8 E-02 02/22 L.T. 1. E-02 02/13 02/27 2.65E 02 CU. M. 03/16 2.5 +-0.4 E-02 03/07 L.T. 5. E-03 02/27 03/06 LOST IN TRANSIT 03/12 L.T. 7. E-03 .
| |
| 03/06 03/l3 1.38E 02 CU. M. 04/05 1.9 +-0.5 E-02 03/26 L.T. 2. E-02 03/13 03/20 1.31E 02 CU. M. 04/02 5.4 +-0.8 E-02 03/30 L.T.'I. E-02
| |
| ~
| |
| 03/20 03/27 1.32E 02 CU. M. 04/05 3.0 +-0.6 E-02 04/04 L.T. I. E-02 03/27 04/03 1.34E 02 CU. M. 04/85 3.2 +-0.7 E-02 04/12 L.T. 2. E-02
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| .
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| a TTELE[WNE ISOTOPES WORTil ANNA power STATION QUARTERLY COMPOSITES OF AIR PARTICULATES (pC1/Cu.H.)
| |
| STATION NUMBER 22 SECOND QUARTER Tl1150 QUARTER DATE COLLECTED: FIRST QUARTER GAMMA SPECTRUM ANA LYSIS:
| |
| 6.89+-1.04E-02 3.78+-1.08E-02 SE-7 4.25+-1.16E-02 L.T. 2. 2-02 L.T. 4. E.02 E-40 L.T. 4. E-02 L.T. 9. E-04 L.T. 1. E-03 HN-54 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03 C0-58 L.T. 1. E-03 .
| |
| L.T. 3. E-03 L.T. 4. E-03 FE-59 L.T. 4. E-03 L.T. 9. E-04 L.T. 1. E-03 Co-60 L.T. 1. E-03 L.T. 2. E-03 L.T. 3. E-03
| |
| ?" ZN-65 L.T. 3. E-03
| |
| ;; L.T. 1. E-03 L.T. 2. E-03 2R-95 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 RU-103 L.T. 2. E-03 L.T. 8. E-03 L.T. 9. E-03 RU-806 L.T. 3. E-02 L.T. 2. E-02 L.T. 1. E-02 I-838 L.T. 3. E-02 L.T. 9. E-04 L.T. 1. E-03 CS-I34 L.T. 1. E-03 1.72+-0.77E-03 L.T. 1. E-03 CS-117 L.T. I. E-03 L.T. 7. E-03 L.T. 7. E-03 RA-140 L.T. 3. E-02 L.T. 2. E-03 L.T. 2. E-03 CE-841 L.T. 2. E-03 L.T. 6. E-03 L.T. 5. E-03 CE-844 L.T. 6. E-03 L.T. I. E-02 L.T. 1. E-02 RA-226 L.T. 1. E-02 L.T. 3. E-03 L.T. I. E-03 111-228 L.T. 1. E-03 R ADIOClit:HICAL ANALYSIS:
| |
| SM-89 . . .
| |
| * E-03 Sk-90 5.8 +-1.6 E-04
| |
| -. __ _ _ . - -
| |
| _ _ _ . . . . . _ _
| |
| | |
| _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ - - _ _ _ _ _ _ _ .
| |
| )
| |
| ,
| |
| TTELEDVNE ISOTOPES Norm ANNA POWER STATION AIR PARTICUI. ATE 4 OIARCOAL PILTERS STATION NLHBER 23 1
| |
| COLLECTION DATE HID (XRafr AP FILTER HID C0taff CHARCDAL FILTER START STOP TIME GROSS BETA TlW. I-131 DATE DATE V0lla4E lacITS DAll! (pCl/On.N) DATE (pCl/Cu.N) 01/02/79 01/09/79 1.34B 02 CU. M. 01/19 5.3 +-0.7 E-02 01/16 L.T. 7. E-03 01/09 01/16 1.37E 02 Cu. M. 01/23 4.4 +-0.7 E-02 01/26 L.T. a. E-03 01/16 01/23 1.36E 02 Cu. M. 01/31 4.1 +-0.s E-02 01/31 L.T. 7. E-03 01/23 01/30 1.33e 02 CU. N. 02/07 2.5 +-0.6 E-02 02/07 L.T. 1. E-02 01/30 02/06 1.37E 02 Cu. M. 02/15 5.3 +-0.s E-02 02/16 L.T. 7. E-03 7, 02/06 02/13 1.35E 02 CU. M. 02/23 5.s +-0.s E-02 02/22 L.T. 7. E-03 e
| |
| 02/13 02/27 2.698 02 CU. M. 03/16 1.5 +-0.3 E-02 03/08 L.T. 6. E-03 02/27 03/06 LOST IN TRANSIT 03/12 L.T. 5. E-03 CU. M. 04/05 4.4 +-0.7 E-02 03/26 L.T. 1. E-02 03/06 03/11 1.39E 02 03/13 03/20 1.34E 02 Cu. M. 04/02 .4.7 +-0.7 E-02 03/29 L.T. s. E-03 03/27 CU..N. 04/05 2.7 +-0.6 E-02 04/04 L.T. 1. E-02 e 03/20 1.37E 02 03/27 04/03 1.38E 02 CU. M. 04/15 4.8 +-0.7 E-02 04/12 L.T. 2. E-02
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| til ma . $=. l=. k. 9=. b. . k. l=. k. . k. v. l=. k. l=. *
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| * k. k. ,
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| & Di. eft e ma m2 ma ma 1 .4 e2 .2 ma .2 na se .2 .I m2 m2 ma .,3 .3 ea .3 O as 2 aa
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| l= as as sa na sa na ma se na aa sa as at sa 33 aa sa na m e 4 e9
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| g ee N se se M ce M ee ce =. ee == ce ce M e == ==
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| |
| t NORTil ANNA POWER STATION l AIR PARTICULATE 4 CalARCOAL PILTERS STATION NUNSER 24 NID COUNT AP PILTER MID COUNT CHARCOAL PILTER Col.LEsYlON DATE START STOP TIME GROSS BETA TIME I-131 ,
| |
| DATE DATE VOLUME UNITS DATE (PC1/Cu.M) DA1 E (pC1/Cu.N) 01/02/79
| |
| '
| |
| 01/09/79 9.60E 01 CU. M. 01/19 7.5 +-1.1 E-02 01/18 L.T. 1. E-02 01/09 01/16 1.34E 02 CU. M. 01/23 7.6 +-0.9 E-02 08/26 L.T. 9. E-03 01/16 08/23 SAMPLE NOT COLLECTED 01/23 01/30 2.69E 02 CU. M. 02/07 8.4 +-2.9 E-03 02/07 L.T. 3. E-03 01/30 02/06 1.34E 02 CU. M. 02/15 6.6 +-0.8 E-02 02/16 L.T. 7. E-03 02/06 02/83 1.34E 02 CU. M. 02/23 6.7 +-0.9 E-02 02/22 L.T. I. E-02 02/83 02/27 2.65E 02 CU. M. 03/16 4.7 +-0.5 E-02 03/08 L.T. 6. E-03 02/27 03/06 LOST IN TRANSIT 03/84 L.T. 4. E-03 03/06 03/13 1.34E 02 CU. M. 04/05 5.2 +-0.7 E-02 03/26 L.T. 1. E-02 03/13 03/20 1.35E 02 CU. M. 04/02 4.8 +-0.7 E 02 03/29 L.T. l. E-02 03/20 03/27 1.31E 02 CU. M. 04/05 2.4 +-0.6 E-02 04/04 L.T. l. E-02 03/27 04/03 1.55E 02 CU. M. 04/15 5.1 +-0.7 E-02 04/12 L.T. 8. E-02
| |
| _ _- - - _ . . -
| |
| | |
| _ - . . - . - _____ _ _ _
| |
| t
| |
| .
| |
| WTELEDYNE ISOTOPES NORTH ANNA POWER STATION .
| |
| !
| |
| QUARTERLY CONPOSITE OF AIR PARTICULATES l
| |
| !
| |
| ?
| |
| (pC1/Cu.M.)
| |
| .
| |
| STATION NUNSER 24
| |
| .
| |
| DATE COLLECTED: FIRST QUARTER $ECOND QUARTER THIRD QUARTER GANNA SPECTRUM ANALYSIS:
| |
| BE-7 5.68*-3.75E-02 6.14+-0.97E-02 4.98+-3.392 02 i
| |
| E-40 L.T. 2. E-02 L.T. 2. E-02 L.T. 3. E-02 NN-54 L.T. 2. E-03 L.T. 8. E-04 L.T. 1, E-03 Co.5s L.T. 2. E-03 L.T. 1. E-03 L.T. 3. E-03 FE-59 L.T. 7. E-03 L.T. 3. E-03 L.T. 4 E-03 ;
| |
| i C0-60 L.T. 2. E-03 L.T. 1. E-03 L.T. 1 E-03 *
| |
| ,
| |
| ZN-65 L.T. 4. E-03 L.T. 2. E-03 L.T. 3 E-03 2R-95 L.T. 2. E-03 L.T. I. E-03 L.7, 2. E-03 RH-803 L.T. 3. E-03 L.T. 1. E-03 L.T. 2. E-03 Ru-306 L.T. 4. E-02 L.T. 7. E-03 L.T.. 1.. E-02 I-831 L.T. 3. E-02 L.T. 1. E-02 L.T. 3. E-02 CS-134 L.T. 1. E-03 L.T. 9. E-04 L.T. 3. E-03 CS-137 L.T. 1. E-03 L.T. 3. E-03 L.T. 3. E-03 RA-840 L.T. 1. E-02 L.T. 8. E-03 L.T. 9. E-03 CE-141 L.T. 4. E-03 L.T. 2. E-03 L.T. 3. E-03 CE-144 L.T. 9. E-03 L.T. 4. E-03 L.T. 6. E-03 RA-226 L.T. 2. E-02 L.T. 9. E-03 L.T. 2. E-02 TH-226 L.T. 2. E-03 L.T. 8. E-04 L.T. 2. E-03 R ADIO"sitiNICAL ANALYSIS SR-89 L.T. 5. E-03 Su-90 67 +-3.1 E-04
| |
| _ . _ _ . . . _ . _ _ _ _ _ _ _ . , _ . _ .,, .. . _, ,._.._ _ ._ . - _ _ _ . . , _ . - . . , _
| |
| | |
| _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ . _ .
| |
| .
| |
| I
| |
| * NORTH ANNA POWER STATION WATER-PRECIPITATION
| |
| .
| |
| '
| |
| STATION NUNSER 01 DATE COLLECTED: JANUARY FEBRUARY NARCH RADIOCHEMICAL ANALYSIS:
| |
| ' GR-t 3.4 +-0.8 8 00 pC1/ liter 4.1 +-0.8 5 00 GR
| |
| * 4.2 +-0.1 E-01 nC1/sq.m. 3.8 +-0.8 E-01 nC1/sq.m tact.as of rain 4.83 inches of ralafall 3.61 inches of ralafall
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| - . _ _ - _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ .
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| .
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| }
| |
| .
| |
| .
| |
| WORTil ANNA POWER STATION
| |
| 'PrTELEDYNE MH7 DOPES
| |
| ,
| |
| DIRECT EXPOSURE TLD NET EXPO 5URE TillRD QU ARTER FOURTil QUARTER ANNUAL FIRST QUARTER SECOND QUARTER 12/26/78-03/27/79 03/27/79-06/26/79 06/26/79-09/25/79 09/25/79-12/26/79 mR/ Jay 06/27/78-06/26/79 mR mR/ Jay mR/ Jay mA mR/Jpy mR STATION mk mR/ Jay mR 15.810.7 0.174 ___ 19.021.1 0.209 23.220.9 0.219 59.121.5 0.862 On ___
| |
| 11.020.4 0.123 13.820.4 0.152 14.110.6 0.155 34.920.6 0.162 44.422.7 0.122 02 12.010.4 0.132 13.610.4 0.149 15.020.3 0.165 J4.520.4 0.158 42.814.2 0.!!7 03 i t
| |
| ' 12.010.6 0.132 17.815.4 0.196 12.310.3 0.835 15.120.4 0.164 73.023.1 0.200 04 --- ---
| |
| 14.720.6 0.162 19.310.6 0.210 21.428.8 0.233 05A 0.162 0.2f9 79.513.8 0.238 05 13.420.4 0.147 15.510.7 0.170 14.711.5 23.811.1 06 15.410.4 0.169 20.412.5 0.224 23.320.4 0.256 17.Sto.4 0.193 100.128.1 0.274 12.320.4 0.135 15.217).5 0.167 16.9 0.6 0.186 17.810.1 0.193 63.113.4 0.173 07 15.920.6 0.175 11.820.7 0.130 16.210.6 0.178 24.423.7 0.265 73.423.1 0.201 28
| |
| >
| |
| 22 16.911.4 0.186 21.411.2 0.235 21.410.5 0.235 23.210.2 0.252 85.813.8 0.235 g
| |
| * 23 12.410.7 0.136 18.910.5 0.208 20.711.3 0.227 12.810.3 0.139 70.414.2 0.193
| |
| *24 10.711.0 0.118 12.720.2 0.140 12.010.6 0.132 17.820.3 0.193 52.412.5 0.144 0.35 0.18 0.19 0.20 0.19 HEAN .
| |
| (ar/ Jay)
| |
| RANCE 0.12-0.19
| |
| * 43-0.22 0.33-0.26 0.14-0.27 0.12-0.27
| |
| =
| |
| (ar/ day) 12/12 11/11 DETECTION / II/II II/II 12/12 TOTAL
| |
| * Control Location - STATION 24: ORANGE 22.0 MILES, 325 De8rees N
| |
| &
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| 4
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| * 4 e & O O O O O O O O O O O O O O O O O O O E B3
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| se se N O O == C == 0 C == == 0 O == == == N >
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| W C =. *C O ==
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| se . M. ao m as N N ==.
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| .,s i&& == 889 2 P. O A tA tA 43 4 3 O.
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| . as p M. == m W
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| p
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| Q at == Q m ad X Q b W N N g gg me Q Q 3 y g p. a.s p =
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| A=26
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| W S3 33 m m3 33 al saa 88 as as na a3 33 N 33 33 na a3
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| < m W3
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| >= O B3 O ,
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| to as .e se N O O we C ee O O es se O O se se me N me e.
| |
| 33 M l'= O O O O O O O O O O O O O O O O O O O 2 33 U e a3 4 e C as et an a 2 33 33 33 33 33 al na 33 33 33 m3 33 33 m3 33 al na 33 BJ U E 3. 9 2 N
| |
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| TTELENNE ISOTOPES NORTH ANNA F0WER STATION SEDIMENT /SI LT (pCl/gs DRY) ,
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| STATION NUMBER 09 DATE COLLECTED MARCil GAMMA SPECTRUM ANALYSIS:
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| , ,
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| BE-7 . L.T. 6. E-01 E-40 4.61*-0.69E 00 MN-54 L.T. 6. E-02 i
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| C0-58 L.T. 6. E-02 FE-59 L.T. 2. E-01 00-60 L.T. 5. E-02 5
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| CE-141 L.T. 9. E-02 C E - 8 .. . L.T. 3. E-01 9 RA-226 1.85+-0.238 00 Tel- 2 2 s 3.26+-0.13E 00
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| _ _ _
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| 1 NORTil ANNA POWER STATION TTELEINNE lSOTOPES sEntweNT/ SILT (pCl/gm DRY)
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| STATION NUMBER 11 DATE COLI.ECTED: MARCil GAMMA SPECTRUM ANALYSIS:
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| BE-7 L.T. 4. E-02
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| ,
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| K-40 , 1.60+-0.16E 00
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| ;
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| HN-54 L.T. 7. E-03 CO-58 L.T. 6. E-03 FE-59 L.T. 2. E-02 C0-60 L.T. 8. E-03
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| RU-803 L.T. 7. E-03 RU-IO6 1. . T . 5. E-02 I-131 L.T. 4. E-02 CS-I34 L.T. 7. E-03 CS-137, L.T. 5. E-03 ,
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| BA-140 L.T. 2. E-02 CH-14I L.T. 1. E-02 CH-144 L.T. 3. E-02 NA-226 L.T. 5. E-02 Til- 2 2 8 6.32e-0.65E-02
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| NORTH ANNA POWER STATION SOIL (pC1/gm DRY)
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| STATION NUMBER 09 DATE COLLECTED: MARCil GAMMA SPECTRUN ANALYSIS:
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| BE-7 L.T. 7. E-01 K-40 5.53+-1.005 00
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| ' HN-54 L.T. 6. E-02 s
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| C0-58 L.T. 6. E-02 FE-59 L.T. 1. E-01 CO-60 L.T. 6. E-02 2N-65 L.T. 1. E-01 y ZR-95 L.T. 1. E-01
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| 1 i
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| _ _ _ _ _ _ _ _ -
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| .
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| TTELEDVNE lSOTOPES NORTil ANNA POWER STATION HILE (pC t'/ li t e r)
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| PIRST QUARTER COMPOSITE
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| ,
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| STATION Sr-89 Sr-90 12 L.T. 7. E 00 2.9 +-0.4 E 00 43 L.T. 4. E 00 - 3.2 *-0.4 2 00 14 L.T. 6. E 00 1.4 *-0.3 E 00
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| ?
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| " .
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| .
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| , SECOND QUARTER
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| .
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| O
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| __-
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| ...
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| '
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| TTEl.EDYNE IwL-7043-444
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| .. ISOTOPES
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| .
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| [
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| >
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| VIRGINIA ELECTRIC AND POWER CGIPANY i
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| P.O. BOX 402
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| !
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| .
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| MINERAL, VIRGINIA 23117 NORTH ANNA POWER STATICN
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| * !
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| ENVIRONMENTAL RADIOLCGICAL MCNITORING PROGRAM 1979 -
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| ,
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| !
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| DESCRIPTION OF THE OPERATIONAL PRCGRAM AND QUARTERLY REPORTS AND ANALYSIS
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| !
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| i
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| !
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| !
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| 1
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| ,
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| Prepared by j
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| 1 i TELEDYNE ISCTTOPES i 50 VAN BUREN AVENUE WESTWCCD, NEW JERSEY 07675 ;
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| !
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| ;
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| ;
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| _ _ _ _ _ _ _ _ - - _ _ _ _
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| ........, .. .. _ _ . . .
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| W TELEDYNE ISOTOPES
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| -
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| TABLE OF CONTENTS Page ii LIST OF TABLES 11 LIST OF FIGURES ,
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| 1 I!frRODUCTION 2
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| THE RADIOLOGICAL E.WIRONMENTAL PROGRAM ABSTRACTS OF ANALYTICAL PROCEDURES 11 A3STRACTS OF RADI0 ASSAY PROCEDURES 14 18 QUALITY C0ffrROL OF ANALYSIS SUM 4ARY OF QUARTERLY RESULTS AND DISCUSSION EXCEPTIONS AND SPECIAL EVENTS 19 AIRBORNE EXPOSURE PATifdAY 20 DIRECT EXPOSURE PATHWAY 26 WATERBORNE EXPOSURE PATHWAY 29
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| '
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| INGESTION EXPOSURE PAThVAY 35 CONCLUSIONS 38 REFERENCES 40 1
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| * APPENDIX S-DATA TABLES-SECOND QUARTER 1979 B-1
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| .
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| 9
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| >
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| T TELEDYNE ISOTOPES
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| -
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| l LIST OF TABLES Page !
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| TABLE 1 Operational Radiological Environmental Monitoring Program 5 TABLE 2 Sampling Station Identification and Location 8 TABLE 3 Lower Limits of Detection (LLD) IS TABLE 4 REMP Summary - Airborne Exposure 22 TAB E S REMP' SLMIARY - Direct Exposure 30 !
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| ;
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| TABLE 6 REMP Summary - Waterborne Exposure 33 l TABLE 7 REMP SLM1ARY - Ingestion Exposure 37 l TABLE 8 Radiation Dose to the Individual frcm Natural and Aritifical 39 Sources j LIST OF FIGURES t e
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| .
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| FIGURE 1 Map of Sampling Stations in Vicinity of NAPS 9 FIGURE 2 Map of the Environmental Sampling Stations 10 FIGURE 3 Airborne Exposure - Gross Beta and Ce-144 (1977-1979) 21
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| :
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| FIGURE 4 Direct Exposure - Environmental TLD (1977-197 9) 27 FIGURE S Waterborne Exposure - Tritium (1977-1979) 30 FIGURE 6 Ingestion Exposure - Sr-90 (1977-1979) 36
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| 11
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| . . - . .
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| SPTELEDYNE
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| ^ ISOTOPES INTRODUCTION Outlined in this document is the description of the operational l environmental radiological monitoring program conducted by Virginia Electric and Power Company for the North Anna Power Station, and a summary of the data generated to satisfy the monitoring require =ents. This program is based on the technical specifications requiring the collection and anlaysis i of various sample media to provide information on the type and quantityThe of radioactivity in certain indicator organisms or critical pathways.
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| operational program became mandatory on April 5,1978 upon granting of the
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| .
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| !
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| operating license for the North Anna Power Station Unit 1.
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| Vigrinia Electric and Power Company is responsible for the col-1ection of the samples required for the program and Teledyne Isotopes is responsible for the analysis of each sample and submission of the reports l of analysis. Quarterly summaries of the data reported for each sample type i will be appended to this document for the period of January 1,1979 through December 31, 1979.
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| These quarterly data summaries will include a summary of the ;
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| radioactivities reported for each sample type and pathway and a tabulation '
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| of the mean, range, and detections / total for each sample type and radionuclide.
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| From the data su=maries, a radiological environmental monitoring program table as specified in Regulatory Guide 4.8 (Ref.1) will be prepared and used as the basis for evaluating the radiation exposures resulting from the North l Anna Power Station operations.
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| Baseline levels of radioactivity in the environs of the North Anna Power Station have been established during the preoperational phase conducted from July 1, 1974 through December 31,1977 (Ref. 2-6) . On April 5, 1978 the operating license for the North Anna Power Station - Unit 1 was ,
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| granted requiring the transition from the preoperational to the operational phase of the radiological environmental monitoring program.
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| The operational phase of the program is described in Appendix B to the Operating I.icense (Ref. 7) and the required analysis and specifica-
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| ,
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| t tions (Table 1) were phased into the program during the January 1- March 31, 1973 quarter.
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| The overall objectives (Ref. 7) of the operational radiological I environmental monitoring program are to identify changes of radioactivity in the vicinity of the North Anna Power Station and to provide information
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| ,
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| '
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| on the types and quantity of radiation in certain critical pathways and indicator organisms as a basis for evaluating radiation exposure from sta-tion operation.
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| i 1
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| __ _. _ _-- _ - _ _ _ - -
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| . . . . .. .
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| T TELEDYNE -
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| , H90 TOPES DESCRIPTION OF THE OPERATIONAL PROGRAM
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| '
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| THE RADIOLOGICAL ENVIRONMENTAL PROGRAM The description of the operational radiological environmental ana-lysis program is presented in this section. Personnel of VEPCO collect the samples specified in Table 1 and ship them to Teledyne Isotopes for the analytical phase of the program. Interim data reports are submitted by Teledyne Isotopes as the analyses are completed, normally within 33 days of the date of receipt of samples (Ref. 9). Summary reports are issued quarterly by Teled'y ne Isotopes,:usually within 45 days after the end of ,
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| the quarter. The quarterly reports will be appended to this report and !
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| will contain (1) computer compilations of the analytical data from the interim data reports, (2) summaries of the environmental radiological ana-lysis for each media listing the mean and range of detected radionuclides and the ratio of detected radionuclides to total measurements, (3) data interpre*ations for each media and analysis based on the summary table prepared in accordance with Regulatory Guide 4.8 (Ref.1) .
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| The radiological environmental program outlined in Table 1 con-tains the techn. cal specification requirements for the North Anna Power Station (Ref. 7 ).
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| Sampling station identifications and relative positions to the effluent release point are listed in Table 2 (Ref. 8 ) and shown on Figure 1 and Figure 2 (maps indicating the environmental sampling stations).
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| The operational environmental radiological program requires measurements on the following media.
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| Airborne Particulates Particulate filters are collected weekly from air sampling stations 1, 3, 5, 7, 21, 22, 23, 24 and analy:ed for gross beta activity. Quarterly composites of these particulate air samples are analy:ed for Sr-89, Sr-90 (second quarter'only) , and gammaremit-ting nuclides by high resolutien Ge(Li) gamma spectrometry. Air sampling stations are located on Figures 1 and 2 and listed in Table 1.
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| Lapse time recorders are used*to calculate actual air volumes.
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| Radiogas (Radioiodine)
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| Charcoal cartridges are collected from sampling stations 3, 21, 23, 24 weekly. The cartridges are analy:ed for radioiodine [
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| by distillation and beta counting. Charcoal cartridge sampling locations are shown on Figures 1 and 2.
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| l 2 e l
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| I
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| ,
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| '
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| . . . _ .
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| -
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| ~
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| TTELEDYNE .
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| ISOTOPES Direct Radiatien Environmental direct radiation levels are monitored by therm- 3 oluminescent dosimeters (TLD) using a multi-area, phosphor teflon i CaSO 4
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| :Dy dosimeter. Dosimeters are placed at each location and ex-changes are made quarterly. TLDs are located at stations 1, 3, 4, S, 6, 7, 21, 22, 23, and 24 (see Table 1 and Figures I and 2).
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| * Milk ;
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| Milk samples are collected' monthly from locations'22, 13, 14 and analyzed for I-131 by chemical separation and gamma isotopic emit- j ters by high resolution Ge(Lil ga=ma spectrometry. Quarterly milk samples ;
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| are analy:ed for Sr-89, Sr-90. Milk sampling locations are listed in Table 1 and shown in Figures 1 and 2. !
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| #
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| Well Water 1
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| !
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| Water samplo. are collected quarterly from the Environmental ;
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| Laboratory well and . !aly:ed for tritium and for gamma emitting nu- ;
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| clides by high resolution Ge(Li) gamma spectrometry. The second I quarter samples are also analyzed for Sr-89, Sr-90. l Surface Water r
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| . A sample of surface water (North Anna River) is collected quar- l terly from Station 11 for tritium and gamma isotopic nuclides. Surface i
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| '
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| , water samples are also collected monthly from Station 08 (Discharge)
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| ' and Station 09 (Reservoir) and analyted for tritium, iodine-131, and gamma isotopes. The second quarter surface water samples or composites are also analyted for Sr-89, Sr-90. ;
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| '"~ '
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| Fish Fish are collected annually near the beginning of the season froia two locations and analyzed for gamma emitting nuclides by high i resciution Ge(Li) gamma spectrometry. Fish sampling sites tre at locat.'ots 3 and 9 on Figure 1. j Terrestrial Vegetation Samples of green leafy vegetation (cultivated or weeds) are collected annua 11'y during the harvest from two locatiens, Stations l 21 and 23. These samples are analyted for gamma emitting nuclides by high resolution Ge(Li) gamma spectremetry.
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| Soil Soil samples are collected frem locations near the airborne stations overy three years and analy:ed for gamma emitting nuclides by high resolutien Cc(Li) gamma spectremetry. The stations are 1, 3, 4, 5, 6, 7, 21, 22, 23, and 24 Stations 1, 21, 22, 23 and 24 are also analy:ed for Sr-89, Sr-90. j f
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| 3 .
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| TTELEDYNE
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| .
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| ISOTOPES -
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| .
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| Sediment / Silt ,
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| Silt samples from Stations 8, 9, and 11 along with a shore-line sample from the vicinity of Station 9 are collected semiannually !
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| and analyzed for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. Sediment / silt samples are analyzed annually for
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| - '
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| Sr-89, Sr-90.
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| !
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| I
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| _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ . - - _ _ _ _ _ _ _ _ _ _ _ . .__. __ _
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| TABLE 1
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| '
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| NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
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| .
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| EXPOSURE PAlllWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY A:;D/0R SAMPLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS AIEBORfiE Particulates Site or site boundary: 1,21, Continuous sampler Weekly gross beta on
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| * 22, 23 (2/3 running time each filter, quarterly Connunities: 3,5,7 cycle), changes gamma isotopic on each I Control: 24 weekly location composite, '-
| |
| Sr-89-90 on second o, Radiolodine 3.21,23,24 quarter composite.
| |
| - I-131 on radiolodine weekly.
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| ,
| |
| 5011 1,3,4,5,6,7,21,22,23,24 Once per 3 years Gansna isotopic on each,
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| *
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| ,
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| Sr 89-90 on~1,21.22, 23, 24 (on collection)
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| DIRECT 1,3,4,5,6,7,21,22.23,24 -
| |
| Quarterly Ganna dose quarterly WATERBORNE Reservoir: 9 Monthly Ganna {sotopic radio-Discharge: 8 iodine 11-3 quarterly composite, Sr 89-90 second quarter composite
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| .
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| North Anna River:d ll Quarterly Ganna isotopic,' H-3 on Ground (well): 1A collection. Sr 89-90 second quarter sample
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| .
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| - - , - , - - - , _- - . - ,, , . _ , - - - - . - - .-
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| - _.
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| '.
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| 8 TABLE 1 ,
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| -
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| NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
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| .
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| ~
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| EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY A!10/0R SAMPLE MAP HUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS
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| .
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| AQUATIC Reservoir: 9 Semiannually Gamma isotopic on Sedia:ent Discharge: 8 collection. Sr 89-90 North Anna River: 11 annually Shoreline Vicinity of: 9 lilGESil0N .
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| a milk Hearest Dalries: 12, 13, 14 Monthly" Radtolodine ,e, g,,,,
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| , 'sotopic monthly Sr
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| .
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| 89-90 quarterly
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| * Hon-dairy activity Calculated dose Radiolodine ''. Gamma b b dependent isotopic DSr 89-90 Fish Reservoir: 9 Annually, near Gamma isotopic (Bass,orsunfish Discharge: 8 beginning of season or crappfe and catfish)
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| .
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| Green Leafy 21, 23 Annually during Gamma isotopic on vegetation. . c collection cultivated or harvest ,
| |
| weeds, flaturally ,
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| occurring
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| .
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| __ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _. _ _ _ e _ , -. --. , , _ . . , -- -
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| .. -_ -
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| t
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| .
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| . d A_BLE,1 ,
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| . NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM
| |
| ' ,
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| i EXPOSURE PATiWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AH0/0R SAMFLE HAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS
| |
| : a. Once each month 1 and 2 mrem thyroid isodose lines will be calculated using the previous month's release data based on the cow-milk-chlid pathway. Should a dairy be located within the 1 mrem isodose line the sampling and analysis frequency ~ for radioiodine will be modified to semimonthly for the month following the month for which the calculation was made. A similar sampling program will be for the 2 mrem isodose line except on a weekly frequency.
| |
| : b. Monthly updates of the current year's annual accumulated calculated thyroid 15 mrem isodose lines based on the
| |
| " goat-milk-child and the cow-milk-child pathway will be dono. Should the isodose line extend beyond the site boundary, a survey to locate goats or cows within the isodose 'ine will be carried out within 30 days. Should goats or cows be observed, efforts to obtain samples from the c ners of the animals will be put forth. If sestples are obtainable, a sampling program similar to "a" above ill be initiated. If samples are unobtainable,
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| '
| |
| the annual report will document such and include the calculated ooses.
| |
| : c. Monthly updates of an annual 15 mrem isodose line (using release data and maximum organ dose in each of the 16 sectors) based on the grass-ca Mle-beef-man pathway will be done. Should the isodose line extend beyond the site boundary, sampling and analyses will be modified to monthly for the current year.
| |
| : d. Samples will be taken from the Environmental Laboratory well.
| |
| e.- Radiolodine analyses will be done by chemical separation.
| |
| .
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| 4 4 8
| |
| _ _ _ . - . _ - _ _ _ - - _ _ _ _ _ -___m_ _- ____ __ .. _.- _ _ _. . ~ . . - - -v-. ,. . , , - - - - - . . ., ,,.__- - %.e, ~ . . . . . - .% . . _ , . _ . . - -_ - ._., . _ - __ .,_
| |
| | |
| _ _ - _ _ _ - - _ - - - - _ _ __ _ __
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| .-_ ._
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| , ,'
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| TABLE 2
| |
| .
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| SAMPLING STATION IDENTIFICATION AND RELATIVE POSITION TO EPPLUENT RELEASE POINT
| |
| .
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| '
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| 2 DEGREES AND DISTANCE RENARKS STATION COMPASS DIRECTION ,.
| |
| NUMBER LOCATION MILES -
| |
| 0.2 42 NE 01 On Site S.3 225 SSW
| |
| '
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| 02 Fredericks lla11 7.1 243 WSW Mineral i 03 5.1 287 WNW 04 Wares Crossroads 4.2 20 NNE 05 Good llopa Church 3.2 11 SSE 05A Sturgeon's Creek a
| |
| '
| |
| - 4.7 115 ESE 06 Levy, f-7.3 167 SSE 07 Bumpass 3.1 148 SSE 04 Discharge Lagoons 320 NW CONTROL
| |
| ~ Lake Anna, upstreen 2.2 0"
| |
| 5.8 128 SSE 11 North Anna River, downstream 8.3 310 MW 12 llolladay Dairy S.6 205 SSW ,
| |
| 13 Fredericks 11 11 3.2 202 SSW 14 Trice Dairy 1.0 301 WNW 21 Route 635 3.0 242 WSW ,
| |
| 22 Route 7-0 0.9 154 SSE 23 Aspen il111s 325 NW CONTROL e 22.0 24 Orange
| |
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| FIGURE 2 i
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| RADIOLOGICAL
| |
| \ /D gg '
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| ENVIRONMENTAL hORANGC ,
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| SAMPLING STATIONS t' s ...
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| + **
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| / SAMPLE LOCATIONS-O
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| .
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| ._.. - . .- _. _
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| _ _ .____-
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| --. . ..
| |
| i TTELEDYNE ISOTOPES
| |
| ~.
| |
| t I
| |
| .
| |
| ABSTRACTS OF THE ANALYTICAL PROCEDURES !
| |
| The following are abstracts of the radionuclide separation, puri-fication, and measurement techr.iques used by Teledyne Isotopes. These tech-j niques have been developed to' meet the detection sensitivities (Table 3) and associated accuracies required by the nuclear industry in compliance with l technical specifications. !
| |
| Air Particulates ;
| |
| Gross Beta Transfer filter to a 2-inch diameter planchet and asssy in a Beck-man Sharp Wide Beta II automatic alpha / beta counter. i Gamma Isotopic Analysis _
| |
| Composite station filters are combined quarterly and radioassayed .'
| |
| on a high resolution, high efficiency Ge(Li) detector.
| |
| Radiogas ,
| |
| Iodine-131
| |
| ^
| |
| Two pro'cedures are used for the analysis of charcoal cartridges .
| |
| [
| |
| ;
| |
| for iodine-131.
| |
| METHOD 1. If the charcoal used is NOT impregnated with elemental
| |
| * i iodine, icdide carrier is added and leached with NaOH. The stable iodide and I-131 is then stripped and extracted as iodine and precipitated as PdI,,
| |
| * mounted on a nylon planchet, and assayed by low level beta counting.
| |
| METHOD 2. If the charcoal used in the filters is impregnated with l iodine, the chemical yield of the distillation procedure cannot be determined and the samples are analy:ed by high resolution ganna spectrometry (Ge(Li)) by integration of the I-131 photopeak.
| |
| Direct Radiation (TLD) .
| |
| CaSO :Dy thermoluminescent dosimeter packets consisting of the 4 :
| |
| i four-area RadiGuard badge are placed at monitoring locations. At the end of the monitoring period, the dosimeters are returned to Teledyne Isotopes for readcut. Results are reported in mR for the collection period or mR/ collection l
| |
| time period. ,
| |
| Milk.
| |
| i Iodine-131
| |
| !
| |
| Stable iodide carrier is added to an aliquet of milk and the io-dido and I-131 is removed by anien exchange resin. The iodine is stripped
| |
| .
| |
| 11
| |
| | |
| _ _
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| ._ .__.
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| SPTELEDYNE ISOTOPES ;
| |
| t with NaOH solution, treated with hydroxylamine hydrochloride and nan 02 ' ""d extracted into CHC1. #
| |
| as free iodine (I ). It is then back extracted into L I
| |
| NaHSO 3 solution and precipitated as Pdf2 . The precipitate is mounted on a nylon planchet for low level beta counting.
| |
| Strontium-89/Stroncium-90 I To 1 liter of milk add strontium carrier and TCA solution. Stir ;
| |
| solution and allow precipitation to settle overnight. Filter, wash, and dis- !
| |
| card precipitate. To the filtrate and oxalic acid, followed by NH 4CH until <
| |
| '
| |
| the solution is alkaline in order to precipitate calcium and strontium oxalates.
| |
| This precipitate is filtered and ashed, and the ash is dissolved in nitric L
| |
| '
| |
| acid. Fe(CH)3 scavenges are performed and stable yttrium carrier added, followed by a S to 7 day period for Y-90 ingrowth. The yttrium is precipi-tated as the hydroxide, redissolved and precipitated as the oxalate, and ,
| |
| then mounted on a nylon planchet and counted in a low level beta counter. [
| |
| The strontium is precipitated from the sample as SrCO , mcunted on a nylon l planchet and counted in a low level beta counter for dr-89 and/or the Y-90 l
| |
| '
| |
| ingrowth.
| |
| Gamma Isotopic Analysis l
| |
| Transfer 1 liter of milk to a 1-liter wrap-around Marinelli count- :
| |
| ing beaker and radioassay on a high resolution Ge(I.1) detector.
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| ,
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| Well Water ,
| |
| !
| |
| Tritium An aliquot of sample is converted to hydrogen gas by reduction in i a hot :ine furnace, mixed with methane counting gas and radioassayed utilizing an internal low level gas proportional counter. Very low levels of activity can be detected due to the sophistication of the counting equipment, the electronics, and the shielding. !
| |
| Gamma Isotopic Analysis l One liter of sample is transferred to a 1-liter Marinelli wrap- j around counting beaker and counted on a Ge(1.1) detector. ,
| |
| ,
| |
| Surface Water .
| |
| I Tritium );
| |
| An aliquot of sample is. converted to hydrogen by gas reduction in ,
| |
| a hot tinc furnace, mixed with methane counting gas and is radioassayed util- i i:ing an internal low level gas proportional counter. Very low levels of ac-
| |
| ,
| |
| l tivity can be detected due to the sophistication of the counting equipment, j
| |
| the electronics, and the shielding. l l
| |
| l l
| |
| i
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| * 1 I
| |
| 12 .
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| .
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| T , - - - , _ _ _
| |
| | |
| . . _ _ _ . _ , . _ __ __.
| |
| TTELEDYNE
| |
| .
| |
| ISOTOPES Gamma Isotooic Analysis One liter of sample is transferred to a 1-liter Marinelli wrap-around counting beaker and counted on a Ge(Li) detector.
| |
| Fish Gamma Isotopic Analysis
| |
| .
| |
| Remove the edible portions by filleting the fish and homogeni:ing '
| |
| in a high speed blender or dice into small pieces. Transfer the blended or diced portions to a 300 mi bottle, record the weight, and radioassay on a ,
| |
| high resolution Ge(Li) detector.
| |
| Vegetation / Terrestrial (Green Leafy)
| |
| Gamma Isotopic Analysis i
| |
| Completely fill a 300 m1 bottle with a green leafy vegetation.
| |
| Record sample weight and radioassay on a Ge(Li) detector. Calculate the ob-served gamma emitting nuclides in pCi/gm wet. ,
| |
| Soil and Sediment / Silt
| |
| '
| |
| Gamma Isotopic Analysis ,
| |
| Fill a 300 mi bottle with soil, record the sample weight, and radioassay en a high resolution Ge(Li) detector.
| |
| Strontium-89/Stronium-90 Weigh an aliquot of dry soil or sediment and transfer to a 1-liter beaker. Add strontium carrier and concentrated HNO3 ; then heat the sample
| |
| '
| |
| for 2 hours to leach strontium from the soil. Filter the resulting solution, wash the precipitation with hot water, and discard the residue. Evaporate the filtrate to a few milliliters and add NH 4CH until alkaline. Add' sat- ,
| |
| urated Na2 CO. solution to precipitate SrCO3 , and centrifuge and discard supernate. dissolve precipitate in HNO3 and evaporate to almost dryness.
| |
| Proceed with Sr-39, Sr-90 purification procedures using fuming nitric acid, an Fe(CH)3 scavenge, etc.
| |
| '
| |
| i 1
| |
| 13
| |
| ,
| |
| | |
| _ _ _
| |
| . - - . . . . ... - =
| |
| .
| |
| ; SPTELEDYNE >
| |
| ISOTt) PES
| |
| '
| |
| t
| |
| :
| |
| :
| |
| ,
| |
| -
| |
| ABSTRACTS OF THE RADI0 ASSAY PROCEDURES .
| |
| The lower limits of detection for radionuclides by the radioassay (
| |
| procedures are listed in Table 3. f l
| |
| Gross Beta
| |
| !
| |
| Evaporated or solid phase aliquots are transferred to a 2-inch diameter stainless steel planchet and counted in a icw level gas flow thin j window Geiger counter.
| |
| Ge(Li) Gamma Spectremetry_ ,
| |
| '
| |
| Based upon the specific media to be analy:ed, samples are counted in 1-liter wrap-around Marinelli type containers, 300 mi bottles or 2-inch !
| |
| filter paper source geometries on 55 cc Ge(Li) detectors coupled to multi- '
| |
| channel spectrometers. All resultant spectra are maintained on magnetic tape for computer analysis and for future reference. ,
| |
| '
| |
| Strontium-89/ Strontium-90 .
| |
| After decomposition and radiochemical separation and purfication, !
| |
| mounts of Sr-89 and Y-90 are counted in a low level gas flow thin window .
| |
| Geiger counter. Nuclide purity is established by counting over at least one l half-life for Y-90 and by multiple counts for Sr-89. !
| |
| !
| |
| Tritium i
| |
| An aliquot of distilled sample is added to scintillation cocktail !
| |
| and counted in a liquid scintillation spectremeter, or converted to the gaseous phase and counted in an internal gas proportional counter depending ,,
| |
| . on sensitivity requirement'.
| |
| Iodine-131 ,
| |
| Mounts are counted in a low level gas flow thin window Geiger coun-ter. Nuclide purity is established by counting over at least one half-life.
| |
| Positive detections of I-131 are also verified by counting on a beta-gamma coincidence spectrometer.
| |
| -
| |
| ,
| |
| Rare Gases l
| |
| Purified fractions are assayed in internal gas proportional counters. ,
| |
| t
| |
| !
| |
| l
| |
| !
| |
| '
| |
| !
| |
| ,
| |
| 14 r
| |
| , . . , , - - - ,
| |
| | |
| . _ -__.- _ _--.
| |
| .. . _ . _ _ .
| |
| W TELEDYNE
| |
| - ISOTOPES TABLE 3
| |
| ,
| |
| LOWER LIMITS OF DETECTICN
| |
| * *
| |
| * LLD 6 Sampled Volume !
| |
| Sample Analysis Reporting Units Required i
| |
| : 1. Airborne Particulate 3 3
| |
| '
| |
| Gross Alpha 2.5 x 10-3 PCi/m 3 125 m l Gross. Beta 7.6 x 10'3 pCi/m 3
| |
| Ge(Li) Gamma Isotopic See Table 3.2 1625 m ,
| |
| ,
| |
| : 2. Airborne Iodine 3 Charcoal Cargridge I-131 ** 2.4 x 10-2 pC1/m 125 m -
| |
| : 3. Direct Radiation TLD Environmental Badge 2 mR 2 2 mR
| |
| : 4. Milk Sr-90 0.8 pCi/1 4 liters I-131 by Chemical Separation 0.5 pC1/1 Ge(L1) Gamma Isotopic (Cs-137) See Table 3.2 Cs-137 Chemical Separation 3 pCi/1 '
| |
| i
| |
| : 5. Well' Water I Gross Alpha 0.5 pCi/1 2 liters Gross Beta 0.S pCi/1 Tritium (gas count) 100 pCi/1 Ge(Li) Gamma Isotopic See Table 3.2 i
| |
| : 6. Surface Water Gross Beta 0.5 pCi/1 2 liters Tritium (gas count) 100 pCi/1 Ge(Li) Gamma Isotopic See Table 3.2
| |
| : 7. Fish: Flesh Gross Beta plue K-40 0.1 pCi/gm wet (2) 1 Kg Ge(Li) Gamma Isotopic See Table 3.2 Sr-89 *0.8 pCi/gm Sr-90 *0.5 pCi/gm [
| |
| '
| |
| : 8. Vegetation (corn' leaf, food, f terrestrial, aquatic)
| |
| Ge(Li) Gamma Isotopic See Table 3.2 (2) 1 Kg Sr-89 0.8 pCi/gm .
| |
| Sr-90 0.5 pCi/gm l i
| |
| : 9. Soil Ge(Li) Gamma Isotopic See Table 3.2 -
| |
| 1 Kg t
| |
| >
| |
| ,
| |
| : 10. Sil Ge(L1) Gamma Isotopic See Table 3.2 (2) 1 Kg Sr-89 0.8 pCi/gm Sr-90 0.5 pCi/gm 15
| |
| ,
| |
| | |
| __
| |
| >
| |
| .. _.
| |
| TTELEDYNE
| |
| '
| |
| ISOTOPES TABLE 3.2 LOWER LDtITS OF DETECTION BY HIGH RESOLUTION Ge(Li) G#ofA SPECTROSCOPY E.WIRGIOiENTAL SMIPLES t
| |
| Water (1 liter) Soil 6 Vegetation Filters Nuclide pC1/1 (400 gm) pCi/gm pC1/ total filter, 2E-01
| |
| -
| |
| 2E+01 Be-7 8E+01 t i
| |
| 2E702 SE-01 SE+01 K-40 SE+01 2E-01 8E+01 Cr-51 2E-02 2 Mn-54 8 2E-02 2 Co-58 8 4E-02 3 Fe-59 1E+01
| |
| -(' 2 Co-60 8 2E-02 4E-02 3 Zr-95 1E+01 ,
| |
| i 2E-02 2 Ru-103 8 2E-01 SE+01 Ru-106 8E+01 3E-02 2 I-131 10 2E-02 2
| |
| . Cs-134 9 2E-02 2 Cs-137 9 SE-02 6 Ba-140 3E+01 2E+01 4E-02 2E+01 La-410 4E-02 3 Ce-141 2E+01 2E-01 2E+01 Ce-144 8E+01 1E-01 1E+01 Ra-226 6E+01 ,
| |
| '
| |
| 2E-02 1E+01 Th-22f IE+01 16
| |
| | |
| . . . . . . .... . .
| |
| - - - - . .
| |
| TTELEDYNE ISOTOPES TABLE 3 t
| |
| LOWER LIMITS OF DETECTION
| |
| * Detection in limits as stated are per gram of ashed material. The actual detection limits in pCi/gm (wet) will vary by a factor of 10-100, depending on the wet versus ash weight factor.
| |
| ** Analysis by chemical separation and beta counting of Pd1 2 . The non-impregnated with elemental icdine charcoal cartridges must be used when chemical separation is required.
| |
| *** The LLD values listed in this table are at the mid-collection time. Samples must be counted within one half-life after collection for these LLD values to be applicable.
| |
| 3.29 4.66 egfa LLD = ]Ts" gg-
| |
| _
| |
| gg-(Ref. 10) 2.22 (V)(c)(DF) 2.22 (V)(c)(DF)(Y)
| |
| ,
| |
| where S= background = cpm at = counting time = min.
| |
| de 2.22 = conversion factor =
| |
| '
| |
| V= volume or weight of sample c= counter efficiency DF = decay factor of the radionuclide frem mid-collection to mid-count time Y= chemical yield
| |
| : LLD = lower limit of detection at the mid- .
| |
| collection time
| |
| .
| |
| !
| |
| P 17
| |
| | |
| .- . .. -- . - . . - - . . . . . . . .. ..
| |
| TTELEDYNE ISOTOPES QUALITY CCNTROL OF ANALYSIS Important elements of the Quality Control Program at Teledyne Iso-topes are (1) Sample and Analysis Control and (2) Laboratory Procedure Con-trol. .
| |
| Details of these elements of the Quality Control Program are provided in separate documents and issued to our customers on a proprietary basis.
| |
| : 1. Sample and Analysis Control All samples arriving at our laboratories are assigned a T.I. code number and are processed by the procedures described in our " Quality Control Manual" (Ref. 9 ) . Copy No. 14, latest revision date of 01/15/78, of the manual has been issued to the Virginia Electric and Power Company. :
| |
| The Quality Control Manual contains ,
| |
| l (a) Specifications for the handling and processing of samples and the documentation required for calculating and reporting the l
| |
| -
| |
| results of the analysis.
| |
| (b) The organi:ation chart of the Envirvamental Analysis Grot p at Teledyne Isotopes and the resumes of supervisory personnel.
| |
| (c) References to the routine stability checks of backgrcunds rad standards required for the calibration of the counting instru-ments used for radioassaying of samples.
| |
| (d) References to the operational checks on blanks, spikes, splits, and cross checks of samples.
| |
| (e) A section en accuracy checks containing summaries of inter-comparison data with EPA cross check programs
| |
| '
| |
| : 2. Laboratory Procedure Control Approved laboratory procedures are followed at Teledyne Isotopes for the analysis of each samples media for specific radionuclides. Copies of the following procedures were issued to the Virginia Electric and Power Company: Determination of Radiostrontium, Determination of Radiciodine, Detection of Gross Alpha and/or Gross Beta, Dete5mination of Gamma Spectra, Determination of Tritium.
| |
| !
| |
| .
| |
| 18
| |
| .
| |
| | |
| e SubNARY OF QUARTERLY RESULTS AND DISCUSSION SECOND QUARTER 1979
| |
| .
| |
| G be 4 e
| |
| | |
| . . .
| |
| (
| |
| . .
| |
| .
| |
| SPTELEDYNE
| |
| _
| |
| ISOTOPES EXCEPTIONS AND SPECIAL EVENTS (APRIL 1,1979-JUNE 30,1979)
| |
| .
| |
| EXCEPTIONS No samples were lost in shipment during the second quarter of 1979. All samples were received and analy:ed within the schedule established for the ana-lytical program. A partial set of seven iodine impregnate charcoal filters was used during the week of 05/09/79. Because of the stable iodine in these filters it was necessary to radioassay them by gamma spectrometry, a method i f
| |
| resulting in a limit of detection of L.T. 0.20 pCi/Cu.M. instead of L.T. 0.024 -
| |
| pCi/Cu.M.
| |
| SPECIAL EVENTS During the second quarter of 1979 no unusual events occurred that could influence the radiological environment in the vicinity of the North Anna Power Station. [,
| |
| i I
| |
| , . i
| |
| !
| |
| I
| |
| .
| |
| 5 e
| |
| t
| |
| >
| |
| e e
| |
| i 19-3
| |
| --
| |
| | |
| . - - - - - - - . . . - . . .
| |
| ;
| |
| T TELEDYNE
| |
| -
| |
| M5011)PFJ5 SUlWARY OF QUARTERLY RESULTS AND DISCUSSION
| |
| ..- AIRBCRNE EXPOSURE PATHWAY (APRIL 1,1979-JUNE 30,1979)
| |
| .
| |
| AIR PARTICULATE FILTERS _ (STATIONS 1-7,21-24) i The average gross beta activity during the second quarter of 1979 remained :
| |
| low (0.038 pC1/Cu.M) at the same level as in the first quarter of 1979. (see '
| |
| Table 4).
| |
| Cerium-144 activity was detected in one of twelve quarterly air t x'+iculate
| |
| ,
| |
| Cesiir,'* 7 was l composite filters at a level close to the limits of detection. ;
| |
| detected in nine of the twelve quarterly A.P. composite filters at an average level of 0.018 pC1/Cu.M., an activity slightly greater than the limits of de-taction. Both Ce-144 and Cs-137 are probably fallout from worldwide deposition of pre 1978 atmospheric nuclear devices.
| |
| Plotted on Figure 3 are the average monthly gross beta and the single de-tection of Ce-144 (see Table 4 also).
| |
| Strontium-89 and strontium-90 were monitored during this quarter and Sr-90 at 0.00064 pCi/Cu.M. was detected in eleven of the twelve stations at a level L slightly higher than the limits of detection. (See Table 4).
| |
| * l Bery111um-7 was monitored in twelve of twelve AP stations at an average l activity of 0.081 pC1/Cu.M. This nuclide is probably cosmic ray induced in '
| |
| the upper atmosphere. F Potassium-40 was detected in three of twelve stations at 0.045 pCi/Cu.M.
| |
| and probably results from the deposition of dust from the soil.
| |
| AIR RADIOICDINE (STATIO*45 1.-7, 21-24)
| |
| No iocine-131 was detected above the limits of detection of 0.024 pCi/Cu.M.
| |
| in the charecal filters radioassayed for the NAPS program. Seven stable iodine filters were inadvertantly used during the week of 05/09/79-05/15/79 and had to be radioassayed by gamma spectrometry. This method of monitoring I-131 results in a higher MDL of 0.2 pCi/Cu.M. instead of L.T. 0.024 pC1/Cu.M.
| |
| ,
| |
| PRECIPITATION (STATICN 01)
| |
| .
| |
| Rainfall samples collected during April, May, and June contained an average These levels ;
| |
| deposition of 0.7'nC1/Sq.m. with a range of 0.5 to 0.9 nCi/Sq.m.
| |
| of deposition compare to 0.38-0.42 nCi/sq.m. monitored during the first quarter of 1979.
| |
| SOIL Soil samples are monitored once every three years and are not scheduled for analysis during this quarter.
| |
| 20-3 t
| |
| | |
| -- - .__. - _ _ . _ _ _ . - _- - . . -_ . _ - _ _ . _ _ _ ___
| |
| l 1
| |
| - - - . . .
| |
| ,
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| .
| |
| * D**D D' i
| |
| - Wc c .
| |
| ;;s
| |
| .
| |
| i
| |
| :
| |
| ,
| |
| :
| |
| FIGURE 3 i is >'
| |
| e< '
| |
| +
| |
| - ' ' ' NORTH ANNA PCWER STATION
| |
| !
| |
| - 6 + i '
| |
| : r. m.~. . . . . . , . .'..y,
| |
| - .......
| |
| , .
| |
| Isnge,.m- .v, i . .r= A i. m t s me,r r_!_ , .. _ . . - . . . AIRSORNE EXPOSURE PATHWAY
| |
| ,
| |
| l i EI23h_U .v =-er.c.: IHiiEliF:5 -!*WEFE AIR PAATICUIATE FILTEA5 .
| |
| t
| |
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| : 4. ... . . , . w ..th
| |
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| : m. ea
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| 4.. [
| |
| j 1
| |
| inne.m . m- e . ** -W MONTMLY AVERAGE OF GROSS BETA
| |
| .
| |
| ' yM QUARTERLY AVERAGE OF CE.144
| |
| ,
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| ;
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| ,
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| .
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| - - =_ _ N __.M_9
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| -.-- u-_ M "_ _ _y : =:
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| I, TABLE 4 1 k
| |
| R ADIOLOGIC AL ENVIRONMENTA( MONITORING PRilCR AM $UMMARY ;
| |
| PATHWAY .alRbORNE COMPIL ATION - QU AR TERLY $UMMARY NORTH ANNA POWER $TATION !
| |
| SAMPLE - ft.ARCOAL FILTERS CONTROL - ORANGE-22.0 Mt.125 OLG.NW VIRGINIA ELECTRIC & power CD, l UNITS - PLI/CU. M s
| |
| .
| |
| ANALYSIS NO LIMIT OF ALL INDICATOR $AMPLES LOCATION WITH HIGHEST MEAN CONTROL LOCAil04 NON- REPORTING PERl00 DETECTION MEAN X E-00 MEAN X E-00 MEAN X E-00 RDUTINE MEAN X E-00 RANGE STATION FRACTICN RANGE RANGE '
| |
| FRACTION ST ATION DESCttlPfl0N FRACTION
| |
| . . . . - _ - - - - ............ ... - _ - _ . . . . . _ - . - - _--- ....- - - . .-- ........... .... _ _....
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| -
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| .
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| l-131 147 0.024 LT 0.020 LT 0.020 0 04/03/79-0F/03/T9 LT 0.020 -LT 0.020 LT 0.0060 -LT 0.020 000/147 000/013 I i
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| :
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| 1-131 _7 0.20 LT 0.2u*
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| LT 0.20 - I.T 0.20 NOT ASSAYED RY LOW LEVEL METil0D 05/09/79-05/15/79 000/007 a U
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| :.
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| .
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| * Stable todine impregnated charcoal Anadvertently used at NAPS. lied to be radiotasayed by gamma spectrometry with higher MDL.
| |
| .
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| G
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| |
| . . ._ . - , , - y- ,--.v-_ , - ,, , - - m.. ,r . - . .c-. - - , - ..n., ,, , - . - . .r,. . _ - - .-- ~
| |
| | |
| . _ _ _ _ _ _ _ _ _ _ - - _ - _ _ _ _ _
| |
| l TABLE 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAN SUMNARY NORTH ANNA POWER STAllDN t POTHWAY- AIRSONNE COMPILATION - 00ARTERLY
| |
| | |
| ==SUMMARY==
| |
| | |
| CONTROL - FREVIOUS 3 quARTeas VIRGINIA ELECTRIC C POWER CO SAMPRE - WATER - PRECIPITATION UNIls - PCI/ LITER CONTROL LOC ATION NON- REPORTING PERIOD ON AL Y SI S HD LIMIT OF ALL INDICATOR SAMPLES LOC Ail 0N WITH HIGHFST ME AN MEAN'M E-00 RouilNE ^l MEAN M E-00 MEAN N E-00 !
| |
| DETECTION RANGE RANCE NEAN M E-00 RANGE STATION FRACTION
| |
| * STAil0N DESCRIPil0N FRACTION FRACTION .................. _. - -----....._ . .... .._-_.
| |
| -
| |
| __ --..
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| ......................... .... _
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| -
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| .
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| .
| |
| l 7.0 0 04/01/19-06/30/19 GR-8 3 7.0 - 9.9 f 99 01 003/003 3.5 I 3.5 -
| |
| 003/003 DN SITE-0.2 Mt.42 OEG.NE
| |
| .
| |
| l.
| |
| .
| |
| AVtRAGE NONTHLY RAINFALL = 4.12 inches 0.66 nC1/sq.a. '
| |
| .
| |
| GR.s 3
| |
| ,,
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| 0.52 - 0.88 7
| |
| w d
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| o e
| |
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| i
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| ~t TABLE 4 TTELEDYNE ISOTOPES RADIOLOGICAL ENVIRONNENTAL MONITORING FROGRAM SUNNARY VIRGINIA ELECTRIC 4 POWER C0FANY O A ' "
| |
| l CONTROL LOCATION - STATION 24
| |
| *
| |
| ! FATHW AY. AIRBORNE
| |
| '
| |
| SAMPLE -30lL
| |
| ! UNITS -pCi/gm DRY
| |
| !
| |
| LOCATION MITil llIGilEST NEAN CONTROL LOCATION NON- REPORTING PERIOD ANALYSISas NO LINIT OF ALL INDICATOR SAMPLES j ROUTINE
| |
| ,
| |
| NEAN NEAN NEAN
| |
| ( DETECTION
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| * RANGE STATION FRACTION RANGE RANGE j l
| |
| '
| |
| PRACTION STATION DESCRIPTION FRACTION
| |
| ,
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| l
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| ,
| |
| .
| |
| .
| |
| SOIL SAMPLES ARE COLLECTED AND ANALYZED ONCE EVERY THREE YEARS FOR Sr-89. Sr-90 AND GANNA SPECTRA-I NO ANALYSIS ARE SCilEDULED DURING APRIL 1- JUNE 30, 1979 U.I 03
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| . - _ . . ... __ _ ._. .
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| T TELEDYNE
| |
| -
| |
| ISOTOPES SUhNARY OF QUARTERLY RESULTS AND DISCUSSION
| |
| ,
| |
| DIRECT EXPOSURE PATHWAY (APRIL 1,1979 - JUNE 30,1979)
| |
| ENVIRONMENTAL GA.4fA DOSE (STATIONS 1-7, 21-24)
| |
| The average environmental gamma dose measured during the second quarter of 1979 was 0.18 mr/ day. Plotted on Figure 4 are the quarterly averages of ;
| |
| the daily dose. The dose of 0.18 mr/ day during the second quarter is slightly l higher than the 0.15 mr/ day monitored during the first quarter.
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| t' TABLE 5 TTELEDYNE ISOTOPES RiolotoGICAL ENVIRONMENTAL MONITORING PROGRAN
| |
| | |
| ==SUMMARY==
| |
| | |
| CONTROL LOCATION - STATION 24 NORTH ANNA POWER STATION PATilW AY- DIRECT EXPOSURE SAMPLE - TLD ENWIRON MENTAL BADGES UNITS - ar/ Jay CONTROL LOCATION NON- BEFORTING PERIOD
| |
| * ANALYSIS NO LIMIT OF ALL INDICATOR SAMPLES LOCATION NITH llIGIIEST MEAN MEAN MEAN ROUTINE DETECTION HEAN RANGE STATION FRACTION RANGE RANGE FRACTION STATION DESCRIPTION FRACTION
| |
| * GAMMA . O.18 IOSE 11 *2mri2mr 0.13-0.22 22 1/1 0.24 0.14 0 03/27/79-06/26/79 11/11 ROlTTE 780 1.0 MILES, 242 Deg.S 1/2 .
| |
| !
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| E$
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| _ _ _ . _ , _ . . . _ . _
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| T TELEDYNE
| |
| -
| |
| ISOTOPES .
| |
| SUFNARY OF QUARTERLY RESULTS AND DISCUSSION WATERBORNE EXPOSURE PATHWAY APRIL 1, 1979-JUNE 30, 1979
| |
| >
| |
| SURFACE WATER (STATIONS 08,09,11)
| |
| The iodine-131 and gamma activities in surface water remained below the ,
| |
| limits of detection during the second quarter of 1979. Tritium activity of l
| |
| 830 pCi/ liter was monitored at station 08, discharge cooling, and continues in the range monitored since July of 1978. See Figure S for the H-3 activities 3 at Station 08.
| |
| Tritium activity at Station 09 (Resevoir) was S70 pCi/ liter compared to '
| |
| 240 pCi/ liter monitored during the 1st quarter of 1979.
| |
| i The tritium activity at Station 11 (River) is 790 pC1/ liter slightly lower l than the 330 pCi/ liter measured during the first quarter. t
| |
| !
| |
| Compiled in Table 6 are summaries of the radionuclides monitored in surface !
| |
| water.
| |
| -
| |
| GROUND WATER (STATION 1A)
| |
| Ground water samples collected from the environmental well contained neither strontium-89, strontium-90, gamma emitters, nor tritium. All measurements were below the limits of detection. j AQUATIC SEDDtENT AND SHORELINE SOIL ;
| |
| Aquatic sediment and shoreline soil are monitored semiannually and analy:ed i for gamma emitters and annually for Sr-89, Sr-90. No analysis were performed i during the second quarter. l
| |
| :
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| RIVER WATER (STATION 11)
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| (See Surface Water above - station 11)
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| .
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| R ADIOLOGICAL ENVIRONMENI AL MONITORING PROGR AM
| |
| | |
| ==SUMMARY==
| |
| | |
| NORIH ANNA POWER stall 0N COMPILATION - QUARTERLY 5'UMMARY VIRGINIA ELECTRIC C POWER CO P AIHW AY- W ATERBORNE CONTROL - PREVIOUS 3 00ARTERS 5 AMPLE - WATER - GROUND UNIT 5 - PCI/ LITER .
| |
| NON- REPORTING PE4800 CONTROL LOC ATION NO LIMli 0F ALL INDICAIOR SAMPLES LOCATION WITH HIGHEST MEAN MEAN X E-00 RouilHE 6 ANAL Y $15 MEAN X E-00 a DEIECTION MEAN X E-00 RANGE RANGE MEAN X E-00 RANGE STATION FRACTION FRACTION FRACTION STATIC 4 DESCRIPTEDN _...-- ----............ .... _=__ -.-
| |
| -...---------- -__.
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| _
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| -....-................... ........--, ...... . _---.
| |
| 0 06/26/79-06/26/79 5R-89 I LT 2.0 LT 2.0 -LT 2.0 000/001 0 06/26/79-06/26/79 52-90 t LT 0.50 LT 0.50 -LT 0.50 g 000/001 6 0 06/26/79-06/26/79 9.00 LT 8.00 C5-8)F 1
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| -LT LT 8.00 8.00 000/001 .
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| 0 06/26/19-06/26/79 i H-3 1 100. LT 120.
| |
| LT 120. -LT 120.
| |
| 000/001 t
| |
| I l
| |
| i
| |
| '
| |
| l
| |
| . I I
| |
| .
| |
| -
| |
| l l
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| _ - _ _ _ - _ _ _ _ _ _ _ - _ _ -_
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| .
| |
| TABLE 6 TTELEDYNE lSOTOPES RADIOLOGICAL ENVIRONMENTAL NOMITORING PROGRAM SUNNARY VIRGINIA ELECTRIC 4 POWER CONPANY CONTROL LOCATION - STATION 09 NORTil ANNA POWER STATION P A TilW AY- W AT E R 80 RN E S AMPLE - SEDIHENT. SOIL UNITS - pCI/ga. DRY LOCATION WITH llIGilEST NEAN CONTROL LOCATION NON. REPORTING PERIOD .
| |
| ANALYSIS NO LINIT OF ALL INDICATOR SANPLES NEAN MEAN NEAN ROUTINE '
| |
| DETECTION RANGE STATION FRACTION RANGE RANGE PRACTION STATION DESCRIPTION FRACTION ,
| |
| .
| |
| O f
| |
| TilERE WERE NO SEDIMENT OR SOIL SAMPLES COLLECTED DURING T11IS QUARTER M
| |
| '
| |
| &
| |
| .
| |
| l 4
| |
| ,, ,, . ,- - . , - , - - -
| |
| | |
| _ _ _ _ _ - - _ - _ _ . _ - .
| |
| TABLE 6
| |
| ,
| |
| R ADIOLOGIC AL ENVIRONMENI AL MONITORING PROGR AN 50MN ARY COMPIL AT ION - 00 AR TERLY
| |
| | |
| ==SUMMARY==
| |
| NORTH ANNA POWER STATION 8 PAfHWAY- V&iERBORNE VIRGINEA ELECTRIC & POWER CO SOMPL E - WATER - RIVER CONTROL - L ARE ANN A.UPS-2.2 MI .320 DEG.NW ti!Ill s - PCl/LIIER CONTROL LOCATION HON- REPORTING PERIGO AN AL V515 NO LIMif 0F A'L L INDICATOR SAMPLES LOCATION WIT 11 HIGHEST MEAN ROUilNE
| |
| *MEAN M E-00 MEAN X E-00 DEFECTION MEAN N E-00 RANGE ST All0N FRACTimi RANGE MEAN x E-00 RANGE FRACTION FRACTION STATION DE5ERIPTION ............ ..... . .... ____ __ _.....
| |
| _
| |
| ____ . .......= _ _ -_
| |
| - _ _ - - _ - _ ............... ............ ........ _-
| |
| 0 06/20/79-06/20/79 50-89 1 LT 4.0 LT 4.0 -LT 4.0 000/001 0 06/20/79-06/20/79 5R-90 l LT 0.90 .
| |
| LT 0.90 -LT 0.90 000/001 0 06/20/79-06/20/19 C5-137 1 LT e.00 LT 8.00 -LT 4.00 000/001 190. 0 06/20/19-06/20/19 H-3 1 790.
| |
| 790. -
| |
| 190. 11 001/001 790. - 190.
| |
| 001/001 NORIH ANNA Re0EWNS-5.8 MI.128 OEG.55 g
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| }
| |
| TABLE 6 TTELEfWNE ISOTOPES RADIOLOGICAL ENVIROHNENTAL NONITORING PROGRAN SUNNARY
| |
| , VIRGINIA ELECTRIC 4 POWER COMPANY CONTROL LOCATION - STATION 09 NORTil ANNA POWER STATION PATilWAY- WATERBORNE SAMPLE - SOIL - VICINITY STATION 09 #
| |
| UNITS - pCl/gmDRY ANALYSIS NO LINIT OF ALL INDICATOR SANPLES LOCATION WITil llIGilEST NEAN CONTROL LOCATION NON. REPORTING PERIOD DETECTION NEAN NEAN NEAN ROUTINE
| |
| - RANGE STATION FRACTION RANGE RANCE FRACTION STATION DESCRIPTION FRACTION , _ _ , , , , ,
| |
| s e
| |
| e 9
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| t
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| (#4 4-TilERE WERE NO SOIL SAMPLES COLLECTED DURING TIIIS QUARTER
| |
| .
| |
| .
| |
| ..___________-__u_-__ _ - - _ _ _ _ _ _ , _ _ _ __,,a m m_ -m-- - - . - ---e -w, r,. , , ,y - - - . _ .
| |
| | |
| . . . . . . . . . . . .
| |
| TTELEDYNE
| |
| ,
| |
| SIMtARY OF QUARTERLY RESULTS AND DISCUSSION INGESTION SAMPLES (APRIL 1, 1979 - JUNE 30, 1979) l MILK (STATIONS 12, 13, and 14)
| |
| Milk samples were analyzed for low levels (L.T. 0.5 pCi/ liter) of iodine-131, ,
| |
| for gamma emitters and for Sr-89, Sr-90. Summari:ed in Table 7 are the radio- i nuclides detected in milk and plotted on Figure 6 is the quarterly average of !
| |
| '
| |
| Sr-90 in milk. The average Sr-90 in milk during this quarter is 3.9 pCi/ liter in agreement with the average Sr-90 monitored since 1977. ;
| |
| /ISH (STATIONS S and 9)
| |
| Fish samples collected at the Discharge Lagoon and in Lake Anna upstream were analy:ed for gamma emitters. Potassium-40 was measured in both fish sam- :
| |
| pies and cesium-137 was measured at station S (Discharge Lagoon). '
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| - -
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| .
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| - _ _ . _ _ . . _ _ _ _ _ . _ .._
| |
| TTELEDYNE CONCWSIONS ISOTOPES
| |
| !
| |
| The results of analysis performed for the Radiological Environmental l Monitoring Program at NAPS and presented in this second quarter 1979 report indicate that no detectable radionuclides were monitored that were probably plant related, except tritium (H-3) in surface and river water. l The maximum waterborne H-3 was 830 pCi/ liter et the discharge canal, j station (08). We conclude that this H-3 activity is plant related because the '
| |
| higher levels have been observed beginning with the start-up of Unit 1 at NAPS. 1 Concurrent with the 830 pCi/ liter tritium at the discharge canal (station 08), -
| |
| the activity at station 09 (Reservoir) was 570 pCi/ liter and at station 11 (river) was 790 pCi/ liter. ,
| |
| '
| |
| If the 830 pCi/ liter of H-3 from station 08 was ingested the total body dose would be less than 0.1 mrem / year, a neg11ble dose compared to the natural ;
| |
| radionuclides in the human body. Thus the only measurable and probable release from NAPS poses no threat to the population.
| |
| ,
| |
| )
| |
| 3 s
| |
| ,
| |
| '
| |
| t l
| |
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| I
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| , l' 38-B
| |
| ,.
| |
| | |
| .
| |
| TTELEDYNE ISOTOPES
| |
| ,
| |
| TABLE 8 RADIATION DOSE TO TIIE INDIVIDUAL FRCM NATURAL AND ARTIFICIAL SOURCES (FROM REF.11)
| |
| ,
| |
| Natural and Artificial Annual per Capita Source In Exposure Source Whole Body Dose Ref. 11 ,
| |
| ,
| |
| Ambient external gamma 55 mrem / year Page 36, Table 2-13 ,
| |
| i (Virginia)
| |
| Medical - bone = arrow dose 103 mrad / year' Page 213, Table 8-3 to.the adult population 1970 K internal constitutent 17 mrem / year Page 29, Table 2-9 of body for beta, and gamma >
| |
| whole body .
| |
| -
| |
| Global fallout - total annual 4.4 mrem / year Page 131, Table 4-10 per capita body dose, est. 1980
| |
| :
| |
| .
| |
| !
| |
| '
| |
| .
| |
| *
| |
| .
| |
| l I
| |
| .
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| l
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| - ;
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| .,
| |
| i
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| .
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| 39 -3
| |
| _-_ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
| |
| | |
| . - . _ _ _ . - . _ . . _
| |
| ,
| |
| -. 'WTELEDYNE }O ISOTOPES h
| |
| .
| |
| REFERENCES
| |
| '
| |
| : 1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8
| |
| " Environmental Technical Specifications for Nuclear Power Plants,"
| |
| December 1975. .
| |
| : 2. Quarterly reports on the Environmental Radiological Monitoring Pro-gram (ERMP) at the North Anna Power Station prepared by Teledyne l Isotopes (IWL-0268-345 and 359 July-December 1974). !
| |
| : 3. Quarterly reports on the ERMP at the North Anna Power Station prepared by Teledyne Isotopes -(INL-0268-364, 367, 371, 375, and 376 January- ,
| |
| December 1975).
| |
| : 4. . Quarterly reports on the ERMP at the North Anna Power Station prepared ,
| |
| by Teledyne isotopes (IWL-0268-387, 394, and 395 January-December
| |
| -
| |
| 1976).
| |
| ,
| |
| Quarterly reports on the EPJIP at the North Anna Power Station prepared t
| |
| l 5.
| |
| by Teledyne Isotopes (INL-5343-406, 407, 413, 423, and 429 January-
| |
| ..
| |
| December, 1977). k
| |
| : 6. Teledyne Isotopes " Environmental Monitoring Summary - Preoperational Program - July 1,1974 - September 30, 1977 INL-5343-426. Prepared for Virginia Electric and Power Company (NAPS).
| |
| : 7. Appendix B to Operating License, Environmental Technical Specifications for North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. S0-338 and S0-336.
| |
| : 8. Virginia Electric and Power Company, Radiological Environmental Moni-toring Manual, June 1977. '
| |
| : 9. Teledyne Isotopes, " Environmental Radiation Analysis Quality Control ,
| |
| Manual,'.' INL-0032-361,197S, Copy No.14 issued to Virginia Electric !
| |
| and Power Company.
| |
| ,
| |
| : 10. Energy Research' and Development Administration, HASL Procedures Manual '
| |
| (HASL-300, 0 03) . * ,
| |
| " Radiological Quality ;
| |
| : 11. United States Environmental Protection Agency.
| |
| of the Environment in the United States,1977" EPA S20/1-77-009, Sep-tcmber 1977.
| |
| : 12. United States Nucicar Rc;;ulatory Commission. Regulatory Guide 1.109,
| |
| ; '
| |
| " Calculation of Annual Doses to Man from Routine Releases of Reactor l
| |
| ' Effluents for the Purpose of Evaluating Compliance with 10CFRSO, Ap-pendix I," October 1977.
| |
| : 13. Quarterly reports of the REMP at the North Anna Power Station prepared by Tcledync Isotopes, IWL-6343-432;.Jan 1, ID73-Dec. 31,1973. ,
| |
| 40 -3
| |
| .
| |
| - - . - - , - .. -
| |
| | |
| E
| |
| :
| |
| @
| |
| G
| |
| * APPENDIX 3 - DATA TABLES SECOND QUARTER 1979 r
| |
| .
| |
| f
| |
| .
| |
| .
| |
| i
| |
| '
| |
| f 1
| |
| 1
| |
| .
| |
| | |
| 1 i
| |
| 'FrTELEDYNE MM7 TOPES APPENDII B TABLE OP CONTENTS APRIL 1 - JUNE 30, 1979 [
| |
| t
| |
| .
| |
| EXPuSURE ANALYTICAL PATHWAY SAMPLB ANALYSIS DATA Alsburmo Air Particulataa Gross Beta (even) 8-238-24 Gamma Isotopic (odd) t Air Radiolodine 1-131 (even) B-2sB-24 Precipitation Gross tota B-33 Direct TLD Gamma Dose B-26 l
| |
| !
| |
| Ingestion Milk I-131 3-29 B-35 Gamma Isotopic S-29:3-31 Sr-89,Sr-90 3-29:3 33 Pish Gamma Isotopic t-27:t-28 I
| |
| w Waterborne Welt Water (10) Sr-89,Sr-90 3-32
| |
| *
| |
| .
| |
| Games Isotopic s-32 Il- 3 3-32 North Amma River (II) Games Isotopic 5-34 11 - 3 t-34 Sr-89,Sr-90 3 34 Discharge Water (08) I-I31 B-35 Gamma Isotopic R-35 11 - 3 B-37 Sr-89,Sr-90 3-37
| |
| , Reservoir Water (09) 1-131 8-36 Gamma Isotopic 3-36 11 - 3 B-37 Sr-89,Sr-90 3-37
| |
| .
| |
| __ ___ _ - . . - , . . , ., , , , , -, - . , - - - - . - - - . . , , , -, - , , -
| |
| | |
| .
| |
| .
| |
| .
| |
| TTELEDYNE SSOTOPES NORTil ANNA POWER STATION e
| |
| AIR PARTICULATE 4 CllABCOAL PILTERS STATION NUMBEa 01
| |
| .
| |
| ,
| |
| Cof.LECTION DATE MID COUNT AP PILTER MID COUNT CilARCOAL PILTER START STOP TIME GAOSS BETA TIME I-131 :
| |
| DATE DATE VOLUME UNITS DATE (pCl/Cu.M) DATE (pCl/Cu.MT g 4
| |
| 04/03/79 04/10/79 1.31E 02 CU.M. 04/22 2.5 +-0.6 E-02 04/Is L.T. 1. E-02 f 04/10 04/17 1.2tu 02 CU.M. 04/30 3.7 +-0.s E-02 o4/25 L.T. 7. E-03 04/17 04/24 1.36E 02 CU.M. 05/09 6.4 +-0.8 E-02 05/03 - L.T. 1. E-02 04/24 05/03 1.36E 02 CU.N. 05/15 3.s +-0.6 E-02 05/10 L.T. 3. E-02 05/04 05/05 1.55e 02 CU.M. 05/19 4.2 +-0.7 E-02 05/29 L.T. 2. E-02 05/05 05/15 1.IIE 02 C U .' M . 05/27 2.5 +-0.7 E-02 05/23 L.T. I. P-02 05/22 CU.N. 05/38 4.0 +-0.7 E 02 06/02 L.T. 1. E-02
| |
| = 05/15 1.348 02
| |
| * 05/22 05/29 1.39E 02 CU.M. 06/13 3.0 +-0.6 E.02 06/09 L.T. 9. E-03 05/29 06/05 1.328 02 CU.M. 06/19 2.6 +-0.6 E-02 06/16 L.T. 1. E-02 06/05 06/12 1.37E 02 CU.M. 06/21 4.2 e.0.7 E-02 06/23 L.T. 9. E-03 06/82 06/19 3.35E 02 CU.M. 06/30 3.7 +-0.7 E-02 06/29 L.T. 3. E-02 06/19 06/26 1.35E 02 CU.N. 07/11 3.5 +-0.6 E-02 07/04 L.T. 6. E-03 06/26 07/03 1.36E 02 CU.M. 07/12 2.8 +-0.6 E-02 07/11 L.T. 1. E-02
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| _ _ _ _ _ _ _ _ - _ - _ - - - .
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| :
| |
| "MFIELE0YNE ISOT0f1ES NORTH ANNA FoNER STATIoM AIR FARTICuLATR 4 CHARCOAL FILTER 3 STATION NUNSER 02 COLLECTION DATE MID count AP FILTER MID CouMT CHARCOAL FILTER START SToP TIME GROSS SETA TIME I-13I DATE DATE Volume uMITS DATE (pct /Cu.M) DATE (pCL/Cu.M) 04/os/7s 04/so/7s 3.1:e 02 Cu.M. 04/22 L.T. s. B-83 04/18 L.T. 2. E-02 e4/10 04/t7 1.tSa 02 Co.M. 04/30 4.7 +-o.s E-o2 04/25 . L.T. 7. E-03 04/i7 04/24 1.34E 02 Cu.M. 05/o9 4.8 +-0.8 E-02 05/03 L.T. 2. E-02 u4/24 os/ot 1.36E 02 Cu.M. 05/15 . 3.6 +-o.6 s-02 05/10 L.T. 2. E-02 os/as os/os 1.58E o2 Cu.M. os/Is 3.8 +-o.4 E-02 05/2s L.T. 2. E-02 05/08 os/ns 1. ass 02 Cu.M. 05/27 2.s +-o.7 a-02 05/23 L.T. 2. E-01 os/es 05/22 1.32E 02 Cn.M. 05/31 3.9 +-o.7 E-02 06/02 L.T. 1. E-02
| |
| *
| |
| . os/22 05/29 1.30e 02 Cu.M. 06/13 3.2 +-o.6 E-o2 06/os L.T. 8. E-03 l 05/29 06/05 1.2s2 o2 Cu.M. 06/19 3.2 +-0.7 E-02 06/16 L.T. 1. E-o2 06/05 06/12 1.28e 02 Co.M. 06/21 3.8 +-o.7 E-02 e6/29 L.T. 1. E-02 06/12 06/19 1.28E 02 Cu.M. 46/30 3.1 +-o.7 B-02 07/o4 L.T. 1. E-02 t 06/ 9 06/26 s.2se 02 Cu.M. 07/11 3.1 +-o.6 8-02 07/o4 L.T. 9. E-03 r 06/>6 07/03 s.35E 02 Cu.M. 07/12 2.5 +-o.6 e-02 07/11 L.T. 3. E-02
| |
| .
| |
| wm- - - , - - ,n,r w r r w- .- =y i- w-- -- -m w-w -v- m----- -- -v- , - tY* ==Vww= -----t -- y7-- <r -- -- - -aw'--w -
| |
| * _ _ _ _ _ _ - _ _ _ - _ _ - _ _ _
| |
| ~
| |
| t I NORTil ANNA PLwtR STATION QUARTERLY COMPOSITE OF AIR PARTICULATES'
| |
| .
| |
| (PCl/Cu.W.) l'
| |
| !
| |
| STATION NUMBER 02 l DATE COLLECTED: PIRST QUARTER SECOND QUARTBit GAMMA SPECTRUM ANALYSIS:
| |
| BE-7 L.T. 2. E-02 7.08+-1.278-02 L-40 L.T. 2. E-02 4.09+-2.17E-02 HM-54 L.T. 1. E-03 L.s. 1. E-03 C0-58 L.T. 2. E-03 L.T. I. E-03 FE-59 L.T. 5. E-03 .L.T. 4. E-03 l Co-60 L.T. 2. E-03 L.T. 1. E-03 2N-65 L.T. 3. E-03 L.T. 3. E 03 ZR-95 L.T. 2. E-03 L.T. 1. E-03*
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| us 8 RU-103 L.T. 2. E-03 L.T. 2. E-03 ue RU-106 L.T. 1. E-02 L.T. 1. E-02 1-138 L.T. 1. B-02 L.T. 1. E-02 CS-134 L.T. 2. E-03 L.T. 1. E-03 CS-137 L.T. 2. E-03 1.86+-0.98E-03 BA-140 L.T. 8. E-03 L.T. 8. E-03 CE-141 L.T. 3. E-03 L.T. 2. E-03 CE-144 L.T. 6. E-03 L.T. 6. E-03 RA-226 L.T. 1. E-02 L.T. 1. E-02 Tit- 2 2 8 L.T. 1. E-03 L.T. 2. E-03 RADIOCllEMICAL ANALYSIS:
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| SR-89 L.T. 3. B-03 SR-90 4.0 *-2.1 B-04
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| i TTELElWNE ISOTOPES NORTil ANJA POWER STATION AIR PARTICULATE 4 CilARCOAL PILTERS STATION NLNBER 03 COLLECTION DATE MtD COUNT AP PtLTER MID COUNT CliARCOAL P tLTER S TART SToP TIME GROSS BETA TlHE- I-838 DATh VOLUME UNITS DATE (pct /Cu.M) DATE (pCl/Cu.N)
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| DATE 04/03/79 04/10/79 1.32E 02 CU.M. 04/22 4,4 . 0.7 E-02 04/18 L.T. 1. E-02 04/10 04/17 1.33E 02 CU.N. 04/30 3.2 +-0.7 E-02 04/25 L.T. a. E-03
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| * 04/87 04/24 a.sse 02 CU w. 05/09 5.4 +-0.s E-02 05/03 L.T. 3. e-02 ;
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| 04/24 05/08 a.33E 02 CU.N. 05/15 4.6 +-0.7 E-02 05/10 L.T. 1. E-02 ,
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| 05/08 05/0s 1.57e 02 CU.N. 05/19 5.4 +-0.7 E-02 05/29 L.T. 2. E-02 05/0s 05/15 1.17E 02 Cu.W. 05/27 4.0 +-0.s E-02 05/23 L.T. 3. E-02 05/s5 05/22 n.36E 02 Co.w. 05/31 4.7 +-0.7 e-o2 06/02 L.T. 2. E-02 05/22 05/29 a.3s2 02 CU.N. 06/13 4.6 +-0.7 E-02 06/09 L.T. 8. E-02 05/29 06/05 1.26E 02 CU.N. 06/19 3.8 +-0.7 E-02 06/15 L.T. t. E-02 06/05 06/12 1.36E 02 CU.N. 06/21 5.4 +-0.8 E-02 06/23 L.T. 7. E-03 06/12 06/19 a.36E 02 CU.M. 06/30 5.4 +-0.8 E-02 06/29 L.T. 8. E-03 06/19 06/26 3.35E 02 CU.N. 07/11 5.2 +-0.7 E-02 07/05 L.T. 8. E-03 06/26 07/03 1.36E 02 CU.N. 07/12 5.4 +-0.7 E-02 07/tt L.T. 1. e-02
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| s s I TTELEDVNE lSOTOPES WORTH ANNA POWER STATION AIR PARTICULATE 6 CilARC0AL FILTERS STATION NUMBEg 04
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| COLLECTION DATE MID COUNT AP FILTER MID COUNT CHABCOAL FILTER START STOP TIME GROSS BETA TIME I-831 DATE DATE VOLUME UNITS DATE (pC1/Cu.M) DATE (pCl/Co.M) 04/03/79 04/10/79 1.32E 02 CU.M. 04/22 2.5 *-0.6 8-02 04/18 L.T. 1. E-02 04/10 04/ 7 a.36E 02 Cu.M. 04/30 2.2 .-0.6 s-02 04/25 L.T. 6. E-03
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| 04/17 04/24 1.36e 02 Cu.M. 05/09 4.0 e-0.7 E-02 05/03 L.T. 1. E-02 04/24 05/03 a.36e 02 CU.N. 05/15 2.7 +-0.6 R-02 05/10 L.T. 1. E-02 :
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| . 05/15 05/22 s.36e 02 Cu.M. 05/33 2.8 +-0.6 E-02 06/02 L.T. 9. E-03 05/22 05/29 s.stE 02 CU.N. 06/13 3.7 +-0.7 E-02 06/09 L.T. B. E-03 05/29 06/05 1.3RR 02 CU.M. 06/19 3.2 +-0.6 E.02 06/16 L.T. 9. E-03 ,
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| 06/05 06/32 1.35e 02 Cu.M. 06/21 4.3 +-0.7 E-02 06/23 L.T. s. e-02 06/12 06/s9 8.35E 02 Cu.M. 06/30 4.7 .-0.7 e-02 06/29 L.T. 1. E-02 06/19 06/26 1.36E 02 CU.N. 07/11 3.9 +-0.6 E-02 07/05 L.T. 2. E-02
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| - 06/26 07/03 1.36E 02 CU.N. 07/12 3.6 +-0.6 E-02 07/12 L.T. 2. E-02
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| TTELEfWNE ISOTOPES NORTH ANNA POWER STATION AIR FARTICULATS 4 CHARCOAL FILTERS STATION NUMBER 05 COLLECTION DATE MID COUNT AP FILVER HIS COUNT CHARCOAL FILTER START STOP TIME CROSS BETA TIME l-131
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| * DATE DATE VOLUME UNITS DATE (pCl/Cu.N) DATE (pct /Co.N) 04/03/79 04/10/79 1.53E 02 CU.N. 04/22 2.6 +-0.6 5 02 04/18 L.T. 3. E-02 04/10 04/17 9.07E 01 CU.N. 04/30 2.7 s-0.9 E-02 04/25 L.T. 8. E-03 04/17 04/24 1.3sE 02 CU.N. 05/09 5.6 +-0.8 E-02 05/03 L.T. 2. E-02 04/24 05/01 1.38E 02 CU.N. t3/15 4.3 +-0.7 E-02 05/11 L.T. 1. E-02
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| 05/01 05/08 1.59E 02 CU.N. 05/19 4.3 e-0.6 E-02 05/29 L.T. 2. E-02 05/0s 05/15 1.lsE 02 CU.N.. 05/27 3.0 *-0.7 E-02 05/23 L.T. 2. E-01 05/15 05/22 1.38E 02 CU.N. 05/31 3.4 e-0.7 E-02 06/02 L . T ., 2. E-02 05/22 05/29 1.41E 02 CU.N. 06/13 5.7 *-0.7 E-02 06/09 L.T. 7. E-43 05/29 06/05 1.30E 02 CU.N. 06/19 4.4 +-0.7 E-02 06/16 L.T. 7. E-03 06/05 06/12 1.3sg 02 CU.N. 06/21 5.4 +-0.8 E-02 06/23 L.T. S. E-03 06/32 06/19 1.30E 02 CU.N. 06/30 6.0 +-0.8 E-02 06/29 L.T. 9. E-03 06/19 06/26 1.40E 02 CU.N. 07/11 4.7 +-0.7 E-02 07/05 L.T. 8. E.03 06/26 07/03 1.38E 02 CU.N. 07/12 4.3 +-0.7 E-02 07/12 L.T. 1. E-02 I.
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| TTELEDYNE ISOTOPES NORTH ANNA POWER STATION AIR PARTICULATE 4 CHARCOAL PILTERS STATION NUMBER esA MID COUNT AP FILTER MID COUNT CHARCOAL FILTER COLLtCTION DATE TIME I-331 START STOP TIME CROSS SETA DATE (pCl/Cu.M) DATE (pCS/Cu.M)
| |
| DATE DATE VOLUME UNITS 04/03/79 04/10/79 1.318 02 CU.N. 04/22
| |
| * 3.4 +-0.7 E-02 04/18 L.T. 1. E-02 ,
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| * NORTil ANNA POWER STATION AIR PARTICULATB 4 CilARC0AL FILTERS STATION NUMBER 22 MID COUNT AP FILTER HID COUNT CllARCOAL FILTER Col.t.ECTION DATE TIME I-138 STAkT STOP TIME GROSS BFTA DATE (pCl/C .N) DATE (pCl/Cu.M)
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| DATE DATE Vol.UN E UNITS 04/Os/79 04/10/79 a.12E 02 Cu.M. 04/22 4.0 +-0.3 E-02 04/18 L.T. 2. E-02 04/ 0 04/17 1.23E 02 Cu.M. 04/30 2.9 +-0.7 E-02 04/25 . L.T. 7. E-03 04/I7 04/24 1.36E 02 CU.N. 05/09 6.4 +-0.8 E-02 05/03 L.T. 2. E-02 04/24 05/0 1.35E 02 CU.N. 05/15 . 5.2 +-0.7 E-02 05/11 L.T. 1. E-02 05/03 c5/0s 1.55E 02 CU.N. 05/19 3.5 +-0.6 E-02 05/38 L.T. 2. E-02 05/05 05/15 SANFLE NOT COLLECTED NONE m 05/l5 05/22 1.35E 02 CU.N. 05/31 4.5 +-0.7 E-02 06/02 L.T. 2. E-02 5 05/22 05/29 1.30E 02 CU.N. 06/13 5.0 +-0.7 E-02 06/10 L.T. 2. E-02 05/29 06/05 1.32E 02 CU.N. 06/19 2.4 +-0.6 E-02 06/16 L.T. 4. E-03 06/05 06/12 1.29E 02 Cu.M. 06/21 4.7 +-0.s e-02 06/23 L.T. 7. E-03 ,
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| 06/12 06/19 1.36E 02 CU.N. 06/30 5.4 +-0.8 E-02 06/29 L.T. 1. E-02 06/19 06/26 1.36E 02 CU.N. 07/11 3.5 +-0.6 E-02 07/05 L.T. 9. E-03 06/26 07/03 1.35E 02 CU.N. 07/12 2.3 +-0.6 E-02 07/I3 L.T. 9. E-03
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| TTELENNE ISOTOPES NORTH ANNA POWER STATION AIR PARTICULATE 4 CHARCOAL FILTERS STATION NUNSER 23 COLLECTION DATE HID COUNT AP FILTER MID COUNT CHARC0AL FILTER START STOP TIME GROSS SETA TIME , I-838 VOLUME UNITS DATE (pCl/Cu.N) DATE (pCl/Cu.N)
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| DATE DATE 04/03/79 04/10/79 1.47E 02 CU.N. 04/22 3.5 +-0.6 E-02 04/18 L.T. l. E-02 04/10 04/17 1.38E 02 CU.N. 04/30 2.7 +-0.6 R-02 04/25 - L.T. 7. E-03 I 04/17 04/24 8.37E 02 CU.N. 05/09 6.2 +-0.8 E-02 05/05 L.T. 1. E-02 l 4
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| 05/15 05/22 1.388 02 CU.N. 05/31 4.2 +-0.7 E-02 06/02 L.T. 1. E-02 05/22 05/29 1.29E 02 CU.N. 06/13 3.2 +-0.6 E-02 06/10 L.T. 1. E-02 05/29 06/05 1.25E 32 CU.N. 06/19 4.5 +-0.7 E-02 06/16 L.T. 1. E-02 06/05 06/32 1.37E 02 CU.N. 06/21 5.2 +-0.8 E-02 06/23 L.T. 1. E-02 '
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| 'prTELEDYNE ISOTOPES NORTil ANNA PONER STATION AIR PARTICULATE 4 CHARCOAL PILTERS STATION NUMBER ' 24 AP PILTER HID COUNT CHARCOAL FILTER COLLECTION DATE MID COUNT I-131 TIME CROSS DETA TIME START STOP (pCl/Cu.N) DATE (pCl/Cu.M)
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| 04/03/79 04/10/79 1.098 02 CU.N. 04/22, s.1 +-0.9 E-02 04/18 L.T. 1. E-02 04/ 0 04/17 a.3 E 02 Co.w. 04/30 3.3 +-0.7 E-02 04/26 L.T. 2. E-02 04/ 7 04/24 1.32E 02 CU.N. 0s/09 5.8 +-0.8 E-02 Os/Os L.T. 8. E-03 ,
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| , 05/22 05/29 l.32e 02 CU.u. 06/t3 3.3 +-0.6 E-02 06/10 L.T. 9. e-03 0s/29 06/0s 1.32E 02 CU.N. 06/19 3.7 +-0.7 E-02 06/16 L.T. 1. E-02 06/0s 06/12 a.34e 02 Cu.u. 06/2: 4.3 +-0.7 E-02 06/23 L.T. 6. E-03
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| NRT BIP05URE FOURTH QUARTER ANNUAL SECOND QUARTER THIRO QUARTER 06/27/78-06/26/79 FIRST QUARTER 12/26/78-03/27/79 03/27/79-06/26/79 , mR mR/ day mR/ day mR mR/ day STATION mR 59.111.5 0.362 01 35.820.7 0.174 - -
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| e 04 0.162 14.720.6 79.523.s 0.21s 05A 0.147 15.520.7 0.170 05 13.420.4 100.128.1 0.274 ;
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| 15.420.4 0.169 20.422.5 0.224 06 63.123.4 0.173 12.310.4 0.135 15.210.5 0.167 07 73.483.1 0.201 21 15.920.6 0.175 11.020.7 0.130 85.813.8 0.235 i 22 16.911.4 0.186 21.421.2 0.235 70.414.2 0.193 0.136 18.910.5 0.20s Y 23 12.410.7 0.144 52.422.5
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| *24 10.711.0 0.118 12.720.2 0.140 0.19 ,
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| 0.15 .
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| 0.14 HEAN (or/ day) 0.12-0.27 0.13-0.22 RANGF. 0.22-0.19
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| .
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| (or/ Jay) 11/11
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| !!/11 11/11 DETECTION /
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| TOTAL
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| ,
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| * Control Location - STATION 24 ORANGR 22.0 MILES 323 Degrees N
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| STATION NUNSBR OS
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| DATE COLLECTED: APRIL GAMMA SPECTRUN ANALYSIS:
| |
| BE.7 L.T. 4. E-01
| |
| * E-40 1.4t+-0.68E 00 MN-54 L.T. 4. E-02 CO-58 L.T. 4. E-02 FE-59 L.T. 1. E-01 C0-60 L.T. 4. E-02 ZN-65 L.T. 8. E-02 ZR-95 L.T. 4. E-02 L.
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| RU-103 L.T. 5. E-02 R0-106 L.T. 4. E-01 I-838 L.T. 3. E-01 CS-134 L.T. 4. B-02 CS-137 L.T. 4. E-02 BA-140 L.T. 2. E-01 CE-14l L.T. 8. E-02 CE .44 L.T. 2. E-Ol RA-226 L.T. 6. E-01 TH-228 L.T. 6. E-02
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| WTELEDYNE ISOTOPES WORTH ANNA POWER STATION WATER-PRECIPITATION l STATION NUNSER-01 ,
| |
| DATE COLLECTEDs APRIL MAY JUNE BADIOCHEMICAR. ANALYSIC f GR-B 9.9 -3.3 3 00 pCi/litor 3.5 -S.3 a se 7.6 e-1.8 5 Se 5.2 e-0.3 E-81 nC1/sq.m. 5.9 e-0.8 E-et act/sq.a. .
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| __ _ _ _ - - _ - - -
| |
| . - - _ _ - _ - .- - -
| |
| i I
| |
| .
| |
| TTFI FaWNE SSOTOPES NORTH ANNA POWER STATION QUARTERLY COMPOSITE OF SURPACE WATER I
| |
| (pC!/ liter)
| |
| SECOND QUARTER STATION NUNSER 08 STATION NUNSBR 09' R ADIOCHEMICAL AN ALYSIS
| |
| -
| |
| SR-89 L.T. 7. R 00 L.T. 3. E 01 Sp 30 L.T. 5. E-01 L.T. 7. B-01 6
| |
| TkITluN ANALYSIS.
| |
| .
| |
| H-3 8.3 +-0.9 E 02 5.7 *-0.9 E 02
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| |
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| , _-. .
| |
| . - _ . _ . . _. _- . _ . _ __ _ . _ _ . - ..- .-- . - . . .-..._. .__.
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| s
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| THIRD QUARTER F
| |
| '
| |
| 0 i
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| !
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| I i
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| {
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| l f
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| L F
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| Y sw. - , - - . w.-.,,. . - - , > - i.- -- . _ . -- . -ym , y ,
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| | |
| -- ..
| |
| TTELEDYNE IWL-7043-444 ISOTOPES i
| |
| ,
| |
| .
| |
| .
| |
| VIRGINIA ELECTRIC AND POWER COMPANY P.O. BOX 402 MINERAL, VIRGINIA 23117 NORTH ANNA POWER STATION r ENVIRONMENTAL RADIOLOGICAL MONITCRING PROGRAM 1979 DESCRIPTION OF THE OPERATIONAL PROGRAM
| |
| -
| |
| AND QUARTERLY REPORTS AND ANALYSIS
| |
| !
| |
| Prepared by TELEDYNE ISCTOPES ,
| |
| '
| |
| 50 VAN BUREN AVENUE WESTWOOD, NEW JERSEY 07675
| |
| :
| |
| !
| |
| | |
| .. . . . . . .
| |
| T TELEDYNE
| |
| ._
| |
| ISOTOPES .
| |
| TABLE OF CONTENTS Page LIST OF TABLES 11 ,
| |
| LIST OF FIGURES
| |
| -
| |
| 11 INTRODUCTION 1 THE RADIOLOGICAL ENVIRON > ENTAL PROGRAM 2 ABSTRACTS OF ANALYTICAL PROCEDURES 11 i
| |
| .
| |
| ABSTRACTS OF RADI0 ASSAY PROCEDURES 14 !
| |
| QUALITY CONTROL OF ANALYSIS 18
| |
| ,
| |
| SUbiMARY OF QUARTERLY RESULTS AND DISCUSSION EXCEPTIONS AND SPECIAL EVE.VTS 19 AIRBORNE EXPOSURE PATHWAY 20
| |
| [ DIRECT EXPOSURE PATHWAY 26 WATERBORNE EXPOSURE PATHWAY 29 INGESTION EXPOSURE PATEWAY 35 :
| |
| '
| |
| * CONCLUSIONS 41 REFERENCES 43 APPENDIX C- DATA TABLES - THIRD QUARTER 1979 C-1
| |
| .
| |
| %
| |
| ,
| |
| 1
| |
| __ _ -. - _ _ _
| |
| | |
| . _ . _ .
| |
| _
| |
| T TELEDYNE ISOTOPES s
| |
| LIST OF TABLES Fage TABLE 1 Operational Radiological Environmental Monitoring Program 5 TABLE 2 Sampling Station Identification and Location s 8 TABLE 3 Lower Limits of Detection (LLD) IS TABLE 4 Remp Summary - Airborne Exposure 22 TABLE S Remp Su= mary - Direct Exposure 28 TABLE 6 Remp Summary - Waterborne Exposure 31 TABLE 7 Remp Summary - Ingestion Exposure 38 42 TABLE 8 Radiation Dose to the Individual from Natural and Artificial Sources LIST OF FIGURES
| |
| ,
| |
| '
| |
| FIGURE I Map of Sampling Stations in Vicinity of NAFS 9 FIGURE 2 Map of the Environmental Sampling Stations 10 FIGURE 3 Airborne Exposure - Gross Beta and Ce-144 (1977-1979) 21' FIGURE 4 Direct Exposure - Environmental TLD (1977-1979) 27 FIGURE S Waterborne Exposure - Tritium "977-1979) 30 FIGURE 6 Ingestion Exposure - Sr-90 (1977-1979) 36 i
| |
| !
| |
| 11
| |
| .
| |
| | |
| . _ _ _ _ _ _ _ - ___ _ _______ _ _
| |
| _ . . _ . _ _ _ _ _ . .
| |
| , ;
| |
| .
| |
| -
| |
| !
| |
| 'pr11ELEtyVNE ,
| |
| , -
| |
| ISOTOPES ,
| |
| INTRODUCTION
| |
| '
| |
| Outlined in this document is the description of the operational environmental radiological monitoring program conducted by Virginia Electric and Power Company for the North Anna Power Station, and a summary of the data generated to satisfy the monitoring requirements. This program is based on the technical specifications requiring the collection and anlaysis of various sample media to provide information on the type and quantity of radioactivity in certain indicator organisms or critical pathways. The operational program became mandatory on April 5,1978 upon granting of the
| |
| '
| |
| operating license for the North Anna Power Station Unit 1.
| |
| Virginia Electric and Power Company is responsible for the col-
| |
| ,
| |
| lection of the samples required for the program and Teledyne Isotopes is responsible for the analysis of each sample and submission of the reports of analysis. Quarterly summaries of the data reported for each sample type will be appended to this document for the period of January 1,1979 through ;
| |
| '
| |
| December 31, 1979.
| |
| These quarterly data summaries will include a summary of the radioactivities reported for each sample type and pathway and a tabulation of the mean, range, and detections / total for each sample type and radionuclide. i From the data summaries, a radiological environmental monitoring program table ;
| |
| as specified in Regulatory Guide 4.8 (Ref.1) will be prepared and used as
| |
| <~ the basis for evaluating the radiation exposures resulting from the North ,
| |
| Anna Power Station operations.
| |
| * Baseline levels of radioactivity in the environs of the North I Anna Power Station have been established during the preoperational phase conducted from July 1,1974 through December 31, 1977 (Ref. 2-6). On April l' S, 1978 the operating license for the North Anna Power Station - Unit I was i
| |
| .
| |
| granted requiring the transition from the preoperational to the operational phase of the radiological environmental monitoring program. .
| |
| The operational phase of the program is described in Appendix B ,
| |
| to the Operating License (Ref. 7) and the required analysis and specifica- ,
| |
| i
| |
| . tions (Table 1) were phased into the program during the January 1- March 31, 1978 quarter.
| |
| The overall objectives (Ref. 7) of the operational radiologiesi environmental monitoring program are to identify changes of radioactivity in the vicinity of the Norta Anna Power Station and to provide information :
| |
| on the types and quantity of radiation in certain critical pathways and indicator organisms as a basis for evaluating radiation exposure from sta- l tion operation. -
| |
| r
| |
| ;
| |
| i i
| |
| l 1
| |
| >
| |
| .
| |
| -__ _ _._ __- _ , . . . . _ - , . . _ _ _ . . _ _ _ .
| |
| | |
| _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
| |
| . .____ ___. _ _ _
| |
| -
| |
| TTELEDYNE
| |
| -.
| |
| ISOTOPES DESCRIPTION OF THE OPERATIONAL PROGRAM THE RADIOLOGICAL ENVIRONMENTAL PROGRAM i
| |
| The description of the operational radiological ^ environmentII' ana-lysis program is presented in this section. Personnel of VEPCO collect the samples specified in Table 1 and ship them to Teledyne Isotopes for the analytical phase of the program. Interim data reports are submitted by Teledyne Isotopes as the analyses are completed, normally within 33 days of the date of receipt' of samples (Ref. 9) . Swnmary reports are issued quarterly by Teledyne Isotopes,.usually within 45 days after the end of
| |
| . the quarter. The quarterly reports will be ' appended to this report and l will contain (1) computer compilations of the analytical data from the !
| |
| interim data reports, (2) su=maries of the environmental radiological ana- ,
| |
| '
| |
| lysis for each media listing the mean and range of detected radionuclides and the ratio of detected radionuclides to total measurements, (3) data interpretations for each media and analysis based on the summary table
| |
| . prepared in accordance with Regulatory Guide 4.8 (Ref.1) .
| |
| The radiological environmental program outlined in Table 1 con-tains the technical specification requirements for the North Anna Power Station (Ref. 7 ).
| |
| !
| |
| Sampling station identifications and relative positions to the effluent release point are listed in Table 2 (Ref. S ) and shown on Figure 1 C'-
| |
| and Figure 2 (maps indicating the environmental sampling stations).
| |
| The operational environmental radiological program requires ;
| |
| measurements on the following media. '
| |
| Airborne Particulates Particulate filters are collected weekly from air sampling stations 1, 3, 5, 7, 21, 22, 23, 24 and analy:ed for gross beta
| |
| .
| |
| activity. Quarterly composites of these particulate air samples l are analy:ed for Sr-89, Sr-90 (second quarter 8cnly) , and ga=ma emit-i
| |
| -
| |
| ting nuclides by high resolutien Ge(Li) gamma spectrometry. Air
| |
| '
| |
| sampling stations are located on Figures 1 and 2 and listed in Table 1.
| |
| Lapse time recorders are used*to calculate actual air volumes.
| |
| Radiogas (Radiciodine)
| |
| Charcoal cartridges are collected from sampling stations 3,
| |
| ,
| |
| 21, 23, 24 weekly. The cartridges are analy:ed for radioiodine l by distillation and beta counting. Charcoal cartridge sampling locations are shown on Figures 1 and 2.
| |
| 2
| |
| | |
| .._ _ _ _
| |
| .
| |
| 'peTELEDYNE ISOTOPES Direct Radiation Environmental direct radiation levels are monitored by therm-oluminescent dosimeters (TLD) using a multi-area, phosphor teflon -
| |
| CaSO 4
| |
| :Dy dosimeter. Dosimeters are placed at.each location and ex-changes are made quarterly. TLDs are located at stations 1, 3, 4, S, 6, 7, 21, 22, 23, and 24 (see Table 1 and Figures 1 and 2) .
| |
| ~
| |
| Milk Milk samples are collected' monthly from locations'22,13,14 and analyzed for 1-131 by chemical separation and gamma isotopic emit-ters by high resolution Ge(Li) gamma spectrometry. Quarterly milk samples are analy:ed for Sr-89, Sr-90. Milk sampling locations are listed in Table 1 and shown in Figures 1 and 2.
| |
| Well Water Water samples are collected quarterly from the Environmental Laboratory well and analy:ed for tritium and for gamma emitting nu-clides by high resolution Ge(Li) gamma spectrometry. The second quarter samples are also analyzed for Sr-89, Sr-90.
| |
| Surface Water
| |
| (.
| |
| '
| |
| ..A sample of surface water (North Anna River) is collected quar-terly from Station 11 for tritium and gamma isotopic nuclides. Surface
| |
| , water samples are also collected monthly from Station 08 (Discharge)
| |
| ' and Station 09 (Reservoir) and analy:ed for tritium, iodine-131, and gamma isotopes. The second quarter surface water samples or composites are also analyzed for Sr-89, Sr-90.
| |
| .,
| |
| p
| |
| --- ..
| |
| Fish are collected annually near the beginning of the season frem two locations and analy:ed for gamma emitting nuclides by high resolution Ge(Li) gamma spectremetry. Fish sampling sites are at locations 3 and 9 on Figure 1.
| |
| Terrestrial Vegetation
| |
| *
| |
| ,
| |
| Samples of green leafy vegetation (cultivated or weeds) are
| |
| ,
| |
| collected annually during the harvest from two locations, Stations l 21 and 23. These samples are analy:ed for gamma emitting nuclides ,
| |
| ; by high resolution Ge(Li) gamma spectrometry.
| |
| 1
| |
| '
| |
| Soil .
| |
| Soil samples are collected from locations near the airborne stations every three years and analy:ed for gamma emitting nuclides by high res. lution Ge(Li) gamma spectrometry. The stations are 1, 3, 4, 5, 6, 7, 21, 22, 23, and 24 Stati:ns 1, 21, 22, 23 and 24 are also analy:ed for Sr-89, Sr-90.
| |
| ,
| |
| 3
| |
| .
| |
| .
| |
| . . -- - - _ . . -
| |
| | |
| ,
| |
| - -. -. - ---. ..--.. . . .- . . . . . _
| |
| ..
| |
| * TTELEDYNE ISOTOPES Sediment / Silt Silt samples from Stations 8, 9, and 11 along with a shore- ;
| |
| -
| |
| line sample from the vicinity of Station 9 are collected semiannually and analyted for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. Sediment / silt samples are analyzed annually for Sr-89, Sr-90.
| |
| >
| |
| >
| |
| >
| |
| >
| |
| .
| |
| '
| |
| ( ,
| |
| I
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| :
| |
| ,
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| I
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| !
| |
| b Y
| |
| O e
| |
| i i i I
| |
| e i
| |
| * ..
| |
| --w--- =- --- , ,_ __ _
| |
| | |
| _ - _ _ _ _ _ _ _ _ _ _ - -. _
| |
| '
| |
| i TABLE 1 ,
| |
| '
| |
| NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM , ,
| |
| i
| |
| ?
| |
| EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AND/0R SAP.PLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS ,
| |
| .
| |
| AIRBORf;E -
| |
| Particulates Site or site boundary: 1,21, Continuous sampler Weekly gross beta on i 22, 23 (2/3 running time each filter, quarterly. ' I, Communities: 3,5,7 cycle), changes gamma isotopic on each *
| |
| . ' Control: 24 weekly location composite, Sr-89-90 on second -
| |
| , Radiolodine 3,21,23,24 quarter composite. I I-131 on radiotodine
| |
| ,
| |
| weekly.
| |
| .
| |
| Soil '
| |
| 1,3,4,5,6,7,21.22,23,24 Once per 3 years Gamma isotopic on each.
| |
| , Sr.89-90 on 1,21,22, 23, 24 (on collection)
| |
| DIRECT 1,3,4,5,6,7,21,22,23,24 -
| |
| Quarterly Gamna dose quarterly
| |
| !
| |
| WATERBORHE Reservoir: 9 Honthly Gammafsotopicradio-Discharge: 8 iodine 11-3 quarterly composite, Sr 89-90 ,
| |
| second quarter composite
| |
| .
| |
| North Anna River: d11 Quarterly Ganna isotopic,11-3 on Ground (well): lA collection, Sr 89-90 second quarter sample
| |
| .
| |
| - - - - - _ _ - - - - - -- - - _ _ _ - - _ _ . - _ - - .- - , - - - --.n. - -
| |
| . - . . . . . - .-. , , , - - - - . , . _
| |
| | |
| _- _ _ _ _ _ _ _ _ _ _ _ _____ _ _ _ _ ____ __
| |
| _.
| |
| . _ _ _ _ _ .
| |
| _ _ _ .
| |
| %
| |
| i ) >:
| |
| .
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| :
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| '
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| i
| |
| - '
| |
| ~
| |
| TABLE 1 .
| |
| ,
| |
| <
| |
| -
| |
| NORTH ANNA POWER STATION -
| |
| OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM
| |
| -
| |
| I
| |
| : EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AllD/0R SAMPLE HAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS 4 .
| |
| AQUATIC . Reservoir: 9 Semiannually Ganna isotopic on Sedinient Discharge: 8 collection Sr 89-90 '
| |
| North Anna River: 11 annually Shoreline Vicinity of: 9 IslGEST10tl a milk Nearest Dairies: 12, 13, 14 Monthly Radiolodine'''. Ganma
| |
| , isotopic monthly. Sr 89-90 quarterly
| |
| * Non-dairy activtty Calculated dose Radiolodine **. Gansna ,
| |
| b h b dependent isotopic Sr 89-90 Fish Reseivoir: 9 Annually, near Gansna isotopic (Bass,orsunfish Discharge: 8 beginning of season or crapple and catfish)
| |
| Green Leafy 21, 23 Annually during Ganna isotopic on vegetation. .
| |
| harvest c collection
| |
| -
| |
| cultivated or weeds. !!aturally ,
| |
| occurring !
| |
| .
| |
| 6 m _ - _ .----- . - .--..._...-.--,--._m., - - . . - _.r- . , - - ,..,..-_,-.-.-.._-.--,--_.,----,w,- , . _ y ._-,..._m .,.,..,.,y,,-, ,- , , , . . .-.,-.-,_,-#,. ,m._,s.,_.. _ , . ,-
| |
| | |
| -_ - - _.- - .
| |
| -
| |
| 1 l
| |
| . :.;TABLE,1 .
| |
| '
| |
| . NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM EXPOSURE PATiiWAY SAMPLE LOCATION AND/OR SAMPLING AND TYPE AND FREQUENCY i AUD/0R SAMFLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS
| |
| '
| |
| l l -
| |
| .
| |
| : a. Once each month I and 2 mrem thyroid isodose lines will be calculated using the previous month's release data
| |
| ; based on the cow-milk-child pathway. Should a dairy be located within the 1 mrem isodose line the sampilng
| |
| ; and analysis frequency for radiciodine will be modified to semimonthly for the month following the month for
| |
| ,
| |
| which the calculation was made. A similar sampling program will be for the 2 mrem isodose line except on a weekly frequency. .
| |
| .
| |
| '
| |
| : b. Monthly updates of the current year's annual accunulated calculated thyroid 15 mrem isodose lines based on the
| |
| '8 goat-milk-child and the cow-milk-child pathway will be done. Should the isodose line extend beyond the site -
| |
| boundary, a survey to locate goats or cows within the isodose line will be carried out within 30 days. Should gjats or cows be observed, efforts to obtain samples from the owners of the animals will be put forth. If
| |
| , semples are obtainable, a sampling program similar to "a" above will be initiated. If samples are unobtainable,
| |
| ; the annual report will document such and include the calculated doses. ;
| |
| .
| |
| ,
| |
| : c. Monthly updates of an annual 15 mrem isodose line (using release data and maximum organ dose in each of the 16 sectors) based on the grass-cattle-beef-man pathway will be done. Should the isodose line extend beyond the site boundary, sampling and analyses will be modified to monthly for the current year,
| |
| : d. Samples will be taken from the Environmental Laboratory well. !
| |
| : e. Radioiodine analyses will be done by chemical separation. i
| |
| ,
| |
| /
| |
| .
| |
| - - - _ _ _ _ - - - - - - - - . - - - - - - -- , ,- ,,,-e -,--.-,,,.,,,,.,.-w -
| |
| ,,_w, , , - o e,- ,-,-- , , , , - - - - - ,, ,--,,,,-w - - - - , , - - - - , - - - - , -
| |
| | |
| _ - _ _ _ . _ _ _ - _ _ _ _ _
| |
| -
| |
| ,
| |
| ! )
| |
| .
| |
| TABLE 2 SAMPLING STATION IDENTIFICATION AND RELATIVE POSITION TO EFFLUENT RELEASE FOINT
| |
| . ,
| |
| DEGREES AND DISTANCE REWARES STATION MILES CONFASS DIRECTION NUMBER LOCATION '
| |
| 0.2 42 NE 01 On Site S.3 225 SSW 02 Fredericks flat t l 243 WSW j Mineral 7.2 03 S.3 287 WNW 04 Wares Crossroads 20 NNE Good liope Church 4. 2 ,
| |
| 05 '
| |
| 3.2 11 SSE OSA Sturgeon's Creek 4.7 115 ESE 06 Levy.
| |
| ,
| |
| 7.3 167 SSE Bumpass I 07
| |
| * 148 SSE
| |
| ,2 . 2 Os Discharge Lagoons 320 NW CONTROL ,
| |
| e Lake Anna, upstream 2.2 09
| |
| . S.8 128 SSE North Anna River, downstream Il 8.3 310 NW Ilo11aday Dairy 12 S.6 205 SSW ,
| |
| 13 Fredericks lis11 3.2 202 SSW Trice Dairy 14 301 WNW ,
| |
| 1.0 21 Route 685 242 WSW 2.0 22 Route 7-0 ,
| |
| 0.9 158 SSE 23 Aspen Ill!!s 325 NW CONTROL 22.0 24 Orange
| |
| .
| |
| 1
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| -
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| !.
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| .
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| _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ - - _ _ _ - - _ _ - - ___~__m - _ _ _ e -A *-m w- w e. -r -- e
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| . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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| _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
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| '
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| .
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| .
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| .
| |
| e.,
| |
| FIGURE 2
| |
| "
| |
| ~ RADIOLOGICAL
| |
| \ /U sg.
| |
| .
| |
| ENVIRONMENTAL SAMPLING STATIONS h0RANGC ) ,
| |
| v . ...
| |
| '
| |
| + **
| |
| ,/ SAMPLE LOCATIONS-O a
| |
| g k. f ..
| |
| N% * '"
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| . h.y % ,4 A
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| %.4 6''
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| .
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| - ,, b' ... .M i(~ .
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| 7 . .. ~
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| q 9 j
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| ,p..,g'. h, . .. '
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| j \ }
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| u too
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| ', - .',\ ' ,, .
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| ss ' '
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| iO' .j.f.,8
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| 4(4g% '
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| w W
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| (.k...[ ,, - I
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| o o. Stattse sette
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| .
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| _, . . - - - - -- - --
| |
| | |
| spe
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| -
| |
| i TTEl.EDYNE !
| |
| H50 TOPES
| |
| .
| |
| .
| |
| - ;
| |
| ABSTRACTS OF THE ANALYTICAL PROCEDURES i l The following are abstracts of the radionuclide separation, puri-fication, and measurement techniques used by Teledyne Isotopes. These tech- .
| |
| !
| |
| ,
| |
| niques have been developed to meet the detection sensitivities (Table 3) and associated accuracies required by the nuclear industry in compliance with technical specifications.
| |
| Air Particulates j
| |
| ,
| |
| Gross Beta Transfer filter to a 2-inch diameter planchet and assay in a Beck-man Sharp Wide Beta II automatic alpha / beta counter.
| |
| Gamma Isotopic Analysis l
| |
| !
| |
| Composite station filters are combined quarterly and radioassayed on a high resolution, high efficiency Ge(Li) detector. l l
| |
| ' Radiogas Iodine-131 ;
| |
| ! Two procedures are used for the analysis o'f charcoal cartridges i for iodine-131. l METHOD 1. If the charcoal used is NOT impregnated sith elemental !
| |
| !
| |
| iodine, iodide carrier is added and leached with NaOH. The stable iodide ;
| |
| and I-131 is then stripped and extracted as iodine and precipitated as PdI2 '
| |
| mounted on a nylon planchet, and assayed by low level beta counting.
| |
| METHOD 2._ If the charcoal used in the filters is impregnated with !
| |
| ;
| |
| iodine, the chemical yield of thc distillation procedure cannot be determined ;
| |
| and the samples are analy:ed by high resolution gamma spectremetry (Ge(Li)) by integration of the I-131 photopeak. :!
| |
| r Direct Radiation (TLD)
| |
| ;
| |
| CaSO 4
| |
| :Dy thermoluminescent dosimeter packets consisting of-the four-area RadiGuard badge are placed at monitoring locations. At the end o#
| |
| !'
| |
| the monitoring period, the dosimeters are returned to Teledyne Isotopes for rendout. Results are reported in mR for the collection period or mR/ collection i
| |
| time period.
| |
| ,
| |
| Milk.
| |
| Iodine-131 1 Stabic iodide carrier is added to an aliquot of milk and the io- i i
| |
| i dide and I-131 is removed by anion exchonge resin. The iodine is stripped
| |
| , :
| |
| i r 11 l i
| |
| !
| |
| ' '
| |
| l - - ._ .. - . __. - . . .-.
| |
| | |
| _. . . . .
| |
| TTELEDYNE ISOTOPES
| |
| ,
| |
| with NaOH solution, treated with hydroxylamine hydrochloride and NASO2 , and extracted into CHC1 as free iodine (I . It is then back extracted into i
| |
| '
| |
| NaHSO 3 solution and 3 precipitated as Pd,)2The precipitate is mounted on a I
| |
| nylon planchet for low level. beta counting.
| |
| .
| |
| Strontium-89/ Strontium-90 To 1 liter of milk add strontium carrier and TCA solution. Stir ;
| |
| solution and allow precipitation to settle overnight. Filter, wash, and dis- l
| |
| '
| |
| card precipitate. To the filtrate and oxalic acid, followed by NH 4CH until the solution is alkaline in order to precipitate calcium and strontium oxalates.
| |
| This ' precipitate is filtered and ashed, and the ash is dissolved in nitric acid. Fe(OH)3 scavenges are performed and stable yttrium carrier added, followed by a 5 to 7 day period for Y-90 ingrowth. The yttrium is precipi-tated as the hydroxide, redissolved and precipitated as the oxalate, and ;
| |
| then mounted on a nylon planchet and counted in a low level beta counter.
| |
| The strontium is precipitated from the sample as SrC0 3, mounted on a nylon l planchet and counted in a low level beta counter for Sr-89 and/or the Y-90 t l
| |
| ingrowth, Gamma Isotopic Analysis i
| |
| Transfer 1 liter of milk to a 1-liter wrap-around Marinelli count- [
| |
| 7 ing beaker and radioassay on a high resolution Ge(Li) detector.
| |
| ,
| |
| Well Water Tritium An aliquot of sample is converted to hydrogen gas by reduction in a hot tine furnace, mixed with methane ccunting gas and radioassayed utili:ing an internal low level gas proportional counter. Very low levels of activity can be detected due to the sophistication of the counting equipment, the electronics, and the shielding.
| |
| i Gamma Isotopic Analysis ;
| |
| One liter of sample is transferred to a 1-liter Marinelli wrap- 3 around counting beaker and counted on a Ge(Li) detector. j
| |
| .
| |
| Surface Water Tritium
| |
| ;
| |
| An aliquot of sample is converted to hydrogen by gas reduction in a hot :ine furnace, mixed with methane counting gas and is radioassayed util-1:ing an internal low level gas proportional counter. Very low levels of ac- .
| |
| '
| |
| tivity can be detected due to the sophistication of the counting equipment, the electronics, and the shielding.
| |
| 12 .
| |
| i l
| |
| l
| |
| | |
| - . _ .
| |
| .
| |
| 'Tr#TERJEDYNE ISOTOPES
| |
| !
| |
| !
| |
| Gamma Isotopic Analysis f
| |
| (
| |
| One liter of sample is transferred to a 1-liter Marinelli wrap- !
| |
| !
| |
| around counting beaker and counted on a Ge(Li) detector.
| |
| Fish
| |
| !
| |
| Gamma Isotopic Analysis Remove the edible portions by filleting the fish and homogeniting in a high speed blender or dice into small pieces. Transfer the blended or ;
| |
| t diced portions to a 300 mi bottle, record the weight, and radioassay on a high resolution Ge(Li) detector. l
| |
| !
| |
| Vegetation / Terrestrial (Green Leafy)
| |
| !
| |
| Gamma Isotopic Analysis Completely fill a 300 m1 bottle with a green leafy vegetation.
| |
| Record sample weight and radioassay on a Ce(Li) detector. Calculate the ob-l served gamma emitting nuclides in pC1/gm wet.
| |
| r~ Soil and Sediment / Silt Gamma Isotoolc Analysis Fill a 300 mi bottle with soil, record the sample weight, and ,
| |
| r radioassay on a high resolution Ge(Li) detector.
| |
| Strontium-89/Stronium-90 Weigh an aliquot of dry soil or sediment and transfer to a 1-liter beaker. Add strontium carrier and concentrated HNO3 ; then heat the sample for 2 hours to leach strontium from the soil. Filter the resulting solution, wash the precipitation with hot water, and discard the residue. Evaporate ,
| |
| the filtrate to a few milliliters and add NH40H until alkaline. Add sat-urated Na2CO solution to precipitate SrC03 , and centrifuge and discard supernate. dissolve precipitate in HNO3 and evaporate to almost dryness.
| |
| Proceed with Sr-89, Sr-90 purification procedures using fuming nitric acid, an Fe(OH)3 scavenge, etc.
| |
| t 7
| |
| 6 1
| |
| 13 l
| |
| l I _ -
| |
| _ _
| |
| | |
| -
| |
| .
| |
| TTE1.EDYNE ~
| |
| ISOTOPES' ABSTRACTS OF THE RADICASSAY PROCEDURES The lower limits of detection for radionuclides by the radioassay procedures are listed in Table 3.
| |
| Gross Beta Evaporated or solid phase aliquets are transferred to a 2-inch diameter stainless steel planchet and counted in a low level gas flow thin window Geige'r counter.
| |
| Ge(L1) Gamma Spectrometry _ ,
| |
| Based upon the specific media to be analyzed, samples are counted in 1-liter wrap-around Marinelli type containers, 300 mi bottles or 2-inch filter paper source geometries on 55 cc Ge(L1) detectors coupled to multi-channel spectrometers. All resultant spectra are maintained on magnetic tape for computer analysis and for future reference.
| |
| Strontium-89/ Strontium-90 l After decomposition and radiochemical separation and purfication, mounts of Sr-89 and Y-90 are counted in a low level gas flow thin window
| |
| ( '-
| |
| Geiger counter. Nuclide purity is established by counting over at least one half-life for Y-90 and by multiple counts for Sr-89.
| |
| Tritium An aliquot of distilled sample is added to scintillation cocktail and counted in a liquid scintillation spectrometer, or converted to the ;
| |
| gaseous phase and counted in an internal gas proportional counter depending on sensitivity requirements.
| |
| Iodine-131 Mounts are counted in a low level gas flow thin window Geiger coun- l ter. Nuclide purity is established by counting over at least one half-life.
| |
| Positive detections of I-131 are also verified by counting on a beta-gamma ,
| |
| -
| |
| coincidence spectrometer.
| |
| Rare Gases ;
| |
| Purified fractions are assayed in internal gas proportional counters.
| |
| .
| |
| t 14
| |
| .
| |
| - - _ _ _ _ _ _ _ _ _ _ _ _- _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _
| |
| | |
| .
| |
| .
| |
| _
| |
| TTELEDYNE -
| |
| ISOTOPES
| |
| ~
| |
| l i
| |
| TABLE 3 LOWER LIMITS OF DETECTION
| |
| *** LLD & Sampled Volume !
| |
| ~
| |
| Sample Analysis Reporting Units Required 1
| |
| l 1. Airborne Particulate 3
| |
| !
| |
| Gross Alpha 2.5 x 10-3 pCi/m 3
| |
| ~
| |
| 125 m i
| |
| !
| |
| Gross' Beta 7.6 x 10 pCi/m Ge(Li) Gamma Isotopic See Table 3.2 1625 m 3 e
| |
| l l
| |
| : 2. Airborne Iodine -2 3 Charcoal Cargridge I-131 **2.4 x 10 pCi/m 125 m ;
| |
| i
| |
| : 3. Direct Radiation ;
| |
| '
| |
| TLD Environmental Badge 2 mR 2 2 mR
| |
| : 4. Milk Sr-90 0.8 pCi/1 4 liters I-131 by Chemical Separation 0.5 pCi/1 Ge(Li) Gamma Isotopic (Cs-137) See Table 3.2 Cs-137 Chemical Separation 3 pCi/1
| |
| : 5. Well Water - f Gross Alpha 0.S pCi/1 2 liters Gross Beta 0.5 pCi/1 Tritium (gas count) 100 pCi/1 !
| |
| Ge(Li) Gamma Isotopic See Table 3.2
| |
| : 6. Surface Water Gross Beta 0.5 pCi/1 2 liters Tritium (gas count) 100 pC1/1 >
| |
| '
| |
| Ge(Li) Gamma Isotopic See Table 3.2 -
| |
| ;
| |
| : 7. Fish: Flesh ,
| |
| Gross Beta plue K-40 0.1 pCi/gm wet (2) 1 Kg Ge(Li) Gamma Isotopic See Table 3.2 Sr-89 *0.8 pC1/gm Sr-90 *0.5 pCi/gm
| |
| '
| |
| : 8. Vegetation (corn,' leaf, food, terrestrial, aquatic)
| |
| Ge(Li) Gamma Isotopic See Table 3.2 (2) 1 Kg Sr-89 0.8 pCi/gm Sr-90 0.5 pCi/gm ,
| |
| : 9. Soil Ge(L1) Gamma Isotopic See Table 3.2 1 Kg i 10. Silt Ge(Li) Gamma Isotopic See Table 3.2 (2) 1 Kg l 0.8 pCi/gm l Sr-89
| |
| '
| |
| Sr-90 0.5 pCi/gm 15
| |
| | |
| --
| |
| .
| |
| TTE1.EDYNE ISOTOPES -
| |
| ~
| |
| TABLE 3.2 LOWER LIMITS OF DETECTION BY HIGH RESOLtJTION Ge(Li) G#NA SPECTROSCCPY ENVIRONMENTAL S#tPLES Water (1 liter) Soil 6 Vegetatien Filters Nuclide pCi/1 (400 gm) pCi/gm pCi/ total filter Be-7 8E+01 2E-01 2E+01 K-40 2E,+02 SE-01 SE+01 Cr-51 8E+01 2E-01 8E+01 Mn-54 8 2E-02 2 Co-58 8 2E-02 2 Fe-59 LE+01 4E-02 3
| |
| ,
| |
| Co-60 8 2E-02 2 Zr-95 1E+01 4E-02 3 Ru-103 8 2E-02 2 Ru-106 8E+01 2E-01 8E+01 1-131 10 3E-02 2 Cs-134 9 2E-02 2 Cs-137 9 2E-02 2 Ba-140 3E+01 8E-02 6 La-410 2E+01 4E-02 2E+01 Ce-141 2E+01 4E-02 3
| |
| >
| |
| Ce-144 8E+01 2E-01 2E+01 Ra-226 6E+01 1E-01 1E+01 l
| |
| Th-22S 1E+01 2E-02 1E+01 4 l
| |
| l i
| |
| 16
| |
| ~
| |
| I
| |
| | |
| _
| |
| .
| |
| TTELEDYNE ISOTOPES TABLE 3 LOWER LIMITS OF DETECTION
| |
| * Detection in limits as stated are per gram of ashed material. The actual detection limits in pCi/gm (wet) will vary by a factor of 10-100, depending on the wet versus ash weight factor.
| |
| ** Analysis by chemical separation and beta counting of PdI2 . The non-impregnated with elemental iodine charcoal cartridges must be used when chemical separation is required.
| |
| *** The LLD values listed in this table are at the nid-collection time. Samples must be counted within one half-life after collection for these LLD values !
| |
| to be applicable.
| |
| = 3*29 ' 4.66 e;-
| |
| LLD ,
| |
| 2.22 (V)(c)(DF) 2.22 (V)(c)(DF)(Y)
| |
| '. .
| |
| where S= background = cpm At = counting time = min.
| |
| ""
| |
| 2.22 = conversion factor =
| |
| g V= volume or weight of sample c= counter efficiency DF = decay factor of the radionuclide from mid-collection to mid-count time Y= chemical yield LLD = lower limit of detection at the mid-collection time
| |
| .
| |
| 17
| |
| !
| |
| ,
| |
| =
| |
| | |
| _ _ _ - _ _
| |
| _, .-
| |
| TTELEDYNE
| |
| - M90 TOPES QUALITY CONTROL OF ANALYSIS Important elements of the Quality Control Program at Teledyne Iso-
| |
| -topes are (1) Sample and Analysis Control and (2) Laboratory Procedure Con-trol.
| |
| Details of these elements of the Quality Control Program,are provided in separate documents and issued to our customers on a proprietary basis.
| |
| ,
| |
| : 1. Sample and Analysis Control All samples arriving at our laboratories are assigned a T.I. code number and are processed by the procedures described in our " Quality Control Manual" (Ref. 9 ) . Copy No. 14, latest revision date of 01/1S/78, of the manual has been issued to the Virginia Electric and Power Company.
| |
| The Quality Control Manual contains (a) Specifications for the handling and processing of samples and the documentation required for calculating and reporting the results of the analysis.
| |
| !
| |
| l g- (b) The organi:ation chart of the Environmental Analysis Group at Teledyne Isotopes and the resumes of supervisory personnel.
| |
| (c) References to the routine stability checks of backgrounds and standards required for the calibration of the counting instru-ments used for radioassaying of samples.
| |
| (d) References to the operational checks on blanks, spikes, splits, and cross checks of samples.
| |
| (e) A section on accuracy checks containing summaries of inter-comparison data with EPA cross check programs ;
| |
| : 2. Laboratory Procedure Control ;
| |
| Approved laboratory procedures are followed at Teledyne Isotopes i for the analysis of each samples media for specific radionuclides. Copies of the following procedures were issued to the Virginia Electric and Power Company: Determination of Radiostrontium, Determination of Radiciodine, Detection of Gross Alpha and/or Gross Beta, Determination of Gamma Spectra, Determination of Tritium.
| |
| :
| |
| !
| |
| l 18
| |
| . _ .
| |
| | |
| e
| |
| .
| |
| | |
| ==SUMMARY==
| |
| OF QUARTERLY RESULTS AND DISCUSSION THIRD QUARTER 1979
| |
| .
| |
| $
| |
| (" .
| |
| s
| |
| | |
| - --
| |
| [ T TELEM NE ISOTOPES EXCEPTIONS AND SPECIAL EVENTS (JULY 1,1979 - SEPTEMBER 30, 1979)
| |
| EXCEPTIONS .
| |
| ;
| |
| All samples except two air particulate and two charcoal filters were received and analyted as scheduled during the third quarter of 1979. The '
| |
| two air particulate and charcoal filters were not collected because of -
| |
| equipment malfunction.
| |
| '
| |
| SPECIAL EVENTS During the third quarter of 1979 no unusua"1 events occurred that could influence the radiological environment in the vicinity of the North Anna T Power Station.
| |
| l l i
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| l l 19-C
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| dyr'rELE!7VNE :
| |
| ISCirOf>ES SUSNARY OF QUARTERLY RESULTS AND DISCUSSION AIRBORNE EXPSOURE PATifdAY (JULY 1,1979 - SEPTEMBER 30, 1979)
| |
| I AIR PARTICULATE FILTERS (STATIONS 1-7, 21-24)
| |
| The average gross beta activity during the third quarter of 1979 continued. low at 0.017 to 0.042 pC1/Cu.M. l Cerium-144 in air particulate filters was below the limits of detection indicating that the worldwide fallout from the 1977 atmospheric nuclear tests is no longer detectable.
| |
| Plotted on Figure 3 are the gross beta and Ce-144 activities monitored in the air particulate filters. The data indicates that NAPS did not release any of the monitored radionuclides at levels above the limits of detection.
| |
| 1 AIR RADI0 IODINE (STATIONS 1-7, 21-24)
| |
| No iodine-131 was detected above the limits of detection of 0.024 pCi/Cu.M.
| |
| on the charcoal filters. These measurements support the conclusion that no
| |
| ( -
| |
| measurable releases of airborne I-131 wre made from NAPS.
| |
| PRECIPITATION (STATION 01)
| |
| Gross beta activitf in the monthly precipitation samples averaged 3.1 pCi/ liter and the average rainfall was 4.6 inches. Average deposition from precipitation was 0.23 nCi/sq.m. .
| |
| . ;
| |
| ,
| |
| SOIL No soil samples were scheduled for monitoring during this quarter.
| |
| I 1
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| TABLE 4 RADICLOGICAL EAVIRCMPENTAL PChlTORING PROGRAW SUMM A R Y COMPILAllCN - CU/NTERLY
| |
| | |
| ==SUMMARY==
| |
| VIRGINI A ELECTRIC E P0hER COPPAhv PATPWAY- AIRBORNE NOR1H ANNA P0hER STATICN SAMPLE - AIR PARilCULATE FILTERS CCNTROL - ORakCE-22.0 Pl.325 CEC.NW UNII 5 - PCI/CU. N
| |
| .
| |
| CON 1ROL LOCAllCN kCh- REPORilkG PERIOD ANALYSIS NO LIMli 0F ALL IN0lC A1064 5 APPLES .LOCATICN blTP PICHF51 PEAN RCLTINE MEAN X E-C0 MEAN N E-C0 DETECil0N MEAN N E-00 RANGE RANGE STATION FRACilfA RANGE FEAN X E-00 FRACTICA FRACil0N STAil(A CESCRIPil0N ............ ....... . .. . ............
| |
| . . . . . . - - - - --=.......... ....- _ __........... .................................-
| |
| .
| |
| 0.042 0.038 0 07/03/ 79-10/02/79 G2-8 154 0.C076 0.033 0.C25 - 0.052 03 013/013 C.030 - 0.05e C.017 - 0.042 013/013 154/154 FINERAL-7.1 Pl.243 CEC.W5W 0.CC0C0 0 C7/31/ 79-10/02/ 79 5 AMPLE 2 0.0CC00 0.00400 O l'
| |
| * 000/002 C.CCCCO. 0.COC00
| |
| *h0T 0.CC00n-COLT.ECTED (CC/002 ._
| |
| . . .
| |
| 0.0498 0 07/03/79'-10/02/79 U 0.0761 C.C4SS 0.0519 C.0761 - 0.C761 0.C498 -
| |
| BE-i 12 0.0120 0.0761 03 001/001 C01/001 C.0378 - PINERAL-7.1 Pl.243 ctg.W5W 011/012 Li 0.C0100 0 07/03/73-10/02/73 LT 0.C01CO-Li 0.CCICO 0.C0120
| |
| '
| |
| 'L i 0.0020C 05-137 12 0.00200 CC0/ Col Li C.00040-Li C00/012 '
| |
| LT 0.0300 0 07/03/79-10/02/79' 0.C300 -Li 0.0300 0.00120 LT 0.03C0 Li 3-131 12 0.0300 C00/001 LT 0.CC100-L1 CC0 /012
| |
| * EQUIPNENT NALFUNCTION
| |
| .
| |
| .
| |
| e
| |
| : v. r . . - - _ , . , . . , - ___e , c _ _ . _ , , , . - ,-
| |
| | |
| ____--
| |
| .
| |
| N
| |
| .
| |
| TABLE 4 RADIOLOGICAL EAVIRCNPEktAL PfkITORING PRnGRAM SUM M AR Y
| |
| '
| |
| PAIHWAY- AIRBORNE COMPILATION - CU#RTERLY SUPMARY VIRGIN!A ELFCTRIC E P0hER CCPPANY 5 ANFLE - CP ARCOAL FILTERS CCNTROL - ORANGE-22.0 Pl.325 CEC.NW NORTH ANNA P0hER STATICN UNil$ - PCl/CU. N ANatV585 NO LIMIT OF ALL INDICATOR SAMPLES LOCATICN blit IICHE5T PEAN CONTROL LOC A TICE kCN- REPORilkG PERIGO
| |
| '
| |
| DETECTION MEAN X E-00 PEAN X E-OO MEAN 3 E-00 ROLTINE PEAN X E-00 RANGE STATION FRACTI(k RANCE RANGE FRACTION STATI(k CESCRIPTION FRAClifK
| |
| ...................... ..........._ ........ .............................__
| |
| .
| |
| 8-131 154 0.024 LT 0.020 LT 0.020 0 07/03/79-10/02/79 LT 0.020 -LT 0.020 LT 0.C080 -L T C.020 C00/154 OC0/013 ,
| |
| SAMPLE 2 LT 0.00C00 0 07/31/fF9-10/02/ 79
| |
| *NOT LT 0.CC000-LT 0.C0000 COLLECTED CC0/002 i
| |
| 1 e
| |
| *EqtalPHENT NALFUNCTION U
| |
| A
| |
| .
| |
| 1
| |
| ,
| |
| 4
| |
| -- .
| |
| -.-_ - _ _.- _ _ -________._________ -_. _________ .._____
| |
| | |
| _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ .
| |
| .
| |
| TABLE 4 RADICLOGICAL EAVIRCNPENTAL PCNITORING PROGRAF
| |
| | |
| ==SUMMARY==
| |
| -
| |
| PATtWAY- Alan 0RNE COMPILATick - CUAPTERLY
| |
| | |
| ==SUMMARY==
| |
| VIRGINIA ELECTRIC E P0hER CCMPANY 5 AMPLE - WATER - PRECIPITATICN CONTROL - NORTH AN NA P0hER STATICh UNITS - PCI/Ll1ER A N AL V515 NO LIMIT OF ALL INDICATOR 5 APPLES LOCATICN blTP blCPEST PEAN CONTROL LOC ATICh hCN- REPCRTihG PERICO DETECTION MEAN X E-00 PEAN X E-C0 MEAN X E-C0 RCLTINE NEAN X E-00 R ANG E STATICN FRACTICN RANCE RANGE FRACTION STATith CE5CRIPTIch fRACTICA
| |
| _......... ..____.__ _ _. ..._____ - .._...... ....__............................... ........_ _-__ ._. .... ...........-_....
| |
| CR-8 3 3.1 3.1 0 07/01/79-09/30/79 2.7 -
| |
| : 3. 4 01 002/003 2.7 -
| |
| 3.6 CO2/003 I-131 1 LT2000. 0 07/01/79-11/30/79 LT200C. -LT2CCO.
| |
| C00/001 .
| |
| C5-137 1 LT 7.00 0 07/01/79-11/30/79
| |
| *
| |
| * LT 7.C0 -LT 7.00
| |
| *
| |
| (C C / Col H-3 1 ICO. 100. O C7/01/79-ll/30/79 100. -
| |
| ICO. 01 001/C01 100. - 1CO.
| |
| C01/001
| |
| *:
| |
| 4.6
| |
| * Rainfall s3 1.2 #
| |
| (6nches) 002/003 e
| |
| popustter 3 0.24 CR-B 0.28 e.39 01 ,
| |
| *
| |
| (NCi/SQ HI) 002/003 9
| |
| , , _ _ - - . . ,
| |
| | |
| .
| |
| TTELEDYNE I ISOTOPES P
| |
| I TABLE 4 SOIL SAMPLES : NO ANALYSIS ARE SCHEDULED DURING JULY 1-SEPTEMBER 30, 1979 i
| |
| .
| |
| (
| |
| .
| |
| * 4
| |
| .
| |
| .
| |
| 25-C
| |
| | |
| 0
| |
| , l j TTELEDYNE m b i ISOTCPES
| |
| | |
| ==SUMMARY==
| |
| OF QUARTERLY RESULTS AND DISCUSSION ,
| |
| DIRECT EXPOSURE PATHWAY (JULY 1,1979 - SEPTEMBER 30, 1979)
| |
| .
| |
| E W.IRONMENTAL RADIATION GASNA DOSE (STATIONS 1-7, 21-24)
| |
| The average environmental gamma dose during the third quarter of 1979 was 0.19 mr/ day. See Figure 4 for the plot of average quarterly gamma dose. From the plot we conclude that the radiation dose is low snd no dose contribution from the radiation environment can be attributed to operations of the NAPS. .
| |
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| b NO N D
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| .# . . - e.
| |
| --I h E -$ 9 N
| |
| .a
| |
| # b96 N N B NO 64 S O
| |
| 3877 19 78 1979 1980 1981
| |
| .
| |
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| |
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| |
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| |
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| _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _
| |
| .
| |
| %
| |
| TABLE 5 RADIOLOGICAL BNVIRONNENTAL MONITORING PROGRAN SUNNARY VIRGINIA RLECTRIC 4 PONER CO. .
| |
| j CONTROL LOCATION - STATION 24 NORTH ANNA PONER STATION
| |
| -
| |
| ORANGE - 22.0 MILES, 325 DEG. *
| |
| '
| |
| PATHNAY-DINECT EXPOSURE SAMPLE -TLD ENVIRONMENTAL RADGdS UNITS -ar/ Jay
| |
| :
| |
| LOCATION WITil HIGHEST MEAN CONTROL LOCATION NON- REPORTING PERIOD ANALYSIS NO LIMIT OF ALL INDICATOR SAMPLES MEAN ROUTINE
| |
| * DETECTION MEAN MEAN RANGE STATION FRACTION RANCR RANCE
| |
| ,
| |
| PRACTION STATION DESCRIPTION PRACTION 0.19 0.26 0.13 0 06/26/79-09/25/79 GANNA 12 *2mrt2mr 0.13-0.26 06 001/001 -- --
| |
| DOSE 12/12 LEVY-4.7 MILES, 115 Deg. 001/001
| |
| *d h
| |
| .
| |
| O e
| |
| - , - , , ,,_y ,,
| |
| | |
| TTELEDYNE ISOTOPES
| |
| | |
| ==SUMMARY==
| |
| OF QUARTERLY RESULTS AND DISCUSSION WATERBORNE EXPOSURE PAilidAY (JULY 1,1979 - SEPTEMBER 30, 1979)
| |
| SURFACE WATER (STATIONS 08, 09)
| |
| Iodine-131 and gamma activities in surface water remained below the limits of detection. Tritium activity at the Discharge Lagoon was -
| |
| 1030 pCi/ liter and at Station 9 (2.2 miles upstream) was 740 pCi/ liter.
| |
| The higher than background activity at Station 09 (upstream) suggests sluggish flow of the surface water. See Figure 5, the plot of the tritium- activities at Station 8 (Discharge Lagoon). The preoperational tritium activity at Station 8 was approximately 150 pCi/ liter. During ,
| |
| this quarter the tritium activity at Station 8 was 1030 pCi/ liter, higher than monitored previously but below the required ten times preoperational warning level.
| |
| GROUND WATER (STATION 1A)
| |
| Ground water samples collected from the environmental well on site at NAPS did not contain measureable levels of gamma emitters that could be released from the NAPS. The tritium activity was 100 pCi/well indicating
| |
| ,
| |
| no waterborne contamination of the ground water.
| |
| RIVER WATER (STATION 11)
| |
| The river water sample from station 11 contained tritium at 790 pCi/ liter a high activity considering the distance of 5.8 miles from the Discharge Cooling outlet for Station 8 to the river water Station 11. The other monitored radionuclides at station 11 were below the limits of detection indicating that tritium was the only waterborne release from NAPS.
| |
| .
| |
| .
| |
| 29-C l -.
| |
| l
| |
| | |
| . _ . . . _ . . . _ . _ .
| |
| TTELEINNE I
| |
| | |
| ==SUMMARY==
| |
| OF QUARTERLY RESULTS AND DISCUSSION AQUATIC PATHWAY (JULY 1,1979 - SEPTEMBER 30, 1979)
| |
| SEDIMENT / SILT (STATION 08, 09, 11)
| |
| Aquatic sediment samples were monitored for ga=ma emitters and for Sr-89, Sr-90 during this quarter of 1979. Sr-90 at below the limits of detection was monitored in one of the sediment samples. K-40, Ra-226, and Th-228 were monitored by gamma spectrum analysis and are of terrestrial ori gin.
| |
| .
| |
| A portion of the Cs-137 is of terrestrial origin and the remainder of Cs-137 and the Cs-134 are probable releases from operations of NAPS.
| |
| Both of these radionuclides were detected at Station 08 (Discharge Lagoon) and at Station 09 (Lake Anna Upstream 2.2 Miles, 320 deg) .
| |
| Under the discussion of waterborne releases Stations 08, 09, and 31 also showed releases of tritium attributed probably to NAPS. The detection of Cs-134 and Cs-137 at stations 08 and 09 suggest the pathway as waterborne followed by settling and/or precipiation of the Cs-134 and .
| |
| !
| |
| Cs-137 in the aquatic environment.
| |
| / The range of Cs-134 activity was 0.0699 to 0.0827 pCi/gm dry, a factor of four above the limits of detection of 0.0200. These levels of activity pose no dose threat to the population using the waters close to these sampling stations. However detection in the environment of probable radio-nuclides frem opeations of NAPS reinforces the need for routine monitoring of sediment for plant related releases.
| |
| 4 SHORELINE SOIL (STATION 09)
| |
| Soil monitored at station 09 contained gamma emitters of K-40, Cs-137 and Th-223. No Cs-134 was detected in the shoreline sample but was detected in the sediment sample from this station.
| |
| .
| |
| .
| |
| 29-C-1
| |
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| |
| * FIGURE 5 !
| |
| ; as
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| |
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| |
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| |
| 4 NCitDI ANNA POWER STATION l i
| |
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| |
| rt-iti i .i + t 3. : .: i-WATERBORNE EXPOSURE PATHWAY '
| |
| i
| |
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| |
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| |
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| TABLE 6 Ran30 LOGICAL ENVIRChPEAIAL PCNITORING PROGRAM SUPPA9Y PAIPWAY_ WATERBORNE COMPILATION - CUARTERLV SUPP4RY VIRGINIA ELECTRIC & PohER CCMPANY 5 APPLE _ WATER - CROUND CONTRCL - PREVICL5 3 (UARTERS NORTH ANNA P0bER SIATICA UNils - PCl/L11ER ANALYSIS NO LIMIT OF ALL IN0lCATOR'5 APPLES LOCATICN blTP FIGHFST PEAN CONTROL LOCATICA h0N- REPCRTING PERIOD GETECTION MEAN X E-00 PEAN X E-00 MEAN x E-C0 BCLTINE PEAN X E-00 R ANG E STATICH FRACTlfh RANGE RAAGE FRACil0N STATilk CESCRIPIION FRACTICA
| |
| _________________________ _____________________ ______________.______________________ _____________________ ____ _____________
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| ,
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| I l-138 2 10.0 LT 30.0 0 09/11/79-09/26/79 LT 10.0 -LT 30.0 (C0 /CO2 ,
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| .
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| C5-137 2 9.00 LT 8.00 0 09/17/79-09/26/79 -
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| LT 6.0C -LT 8.00
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| . CC0/002 * .
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| !
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| t TH-228 2 10.0 128. 128. 0 09/17/79-09/26/79 128. -
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| 124. 01 001/001 128. - 124.
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| C01/002
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| . I
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| '
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| H-3 2 ICO. 440. 190. 0 09/11/79-09/26/79 100. -
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| 750. 11 001/0Cl 190. - 790.
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| (02/002 NORTH ANNA ReCCWNS-5.8 Pl.128 OEC.55
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| TABLE 6 i
| |
| it RADICLOGICAL EAVIRONPEkIAL PCNITORING PROGRAP
| |
| | |
| ==SUMMARY==
| |
| i l
| |
| D Af rW ay- ACUATIC COMPILATICN - CUARTERLY
| |
| | |
| ==SUMMARY==
| |
| VIRGINIA ELECTRIC E POWER CCPPANY !
| |
| 5 AMPLE - SECIMENT/5lLT CONTROL - LANE Atha.uPS-2.2 Mt.320 CEC.NW HOATH ANNA P0kEA SIATICN u4115 - PCl/GP DAY i kCN- REPCRilkG PERl00 NO LIMIT OF Att INDICATOR 5 APPLES LOCATICA blip PICHEST MEAM CONTROL LOC A TICA 3 ON AL Y S 8 5 ROLilNE DEIECil0N MEAN N E-0C MEAN X E-00 MEAN X E-C0 !
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| [ PEAN M E-00 R ANGE STATICN FRACTith RANCE RANGE ,
| |
| FRACTION STATI(k [ESCRIPfl0N FRACTICN l
| |
| . _ _ _ _ _ - __=
| |
| 1
| |
| !
| |
| 13.0 24.5 1.69 0 09/17/79 -C9/17/79 O-40 3 0.500
| |
| * 6.94 - 24.5 11 001/001 24.5 -
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| 24.5 7.45 - 7.69 C03/003 NORTH ANNA R,CCWNS-5.8 FI.128 CEG.55 001/C01 , ,
| |
| : !
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| t 0.2CC LI 0.200 0 09/17/79 -C9/17/ 23 1-131 3 0.0300 II LT 0.2C0 -Li 0.2CC LT 0.200 -LI 0.200
| |
| * CCC/C03 00C/C01 .
| |
| i 0.0743 0.0827 0.0827 0 09/17/79 -09/17/79 C5-134 3 0.0200 0.0827 0.0827 - 0.0827 C.0699 - 0.0827 09 001/001 C.0827 -
| |
| CC2/003 LARE AANA.UP5-2.2 Pl.120 CEG.NW C01/001 0.24C 0.371 0.371 0 09/17/a9-09/17/79 C5-137 3 0.0200 C.371 - 0.371 0.371 - 0.371 0.110 - 0.371 09 001/001
| |
| * CO2/003 LANE AANA.UPS-2.2 Pl.320 DEG.NW 001/001
| |
| .
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| 8 M
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| h
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| 1.08 1.33 0.844 0 09/17/79 -09/17/79 RA-226 3 0.100 0.144 - 0.844 0.844 - 1.33 08 001/001 1 33 -
| |
| 1.33 CO2/003 DISCHARGE LACC[h5-1.1 NI.148 DEC.55E 001/C01 0.805 0.958 0.R62 0 09/17/79-09/17/79 TH-228 3 0.0200 0.E62 - 0.862 0.596 - 0.958 08 001/001 C.958 - 0.518 C03/003 DISCHARGE LAGCfkS-1.1 Mt.148 DEG.55E Col /001 SR-89 3 0.80 L.T. 1.0 L.T. 1.0 L.T. 1.0 000/003 0.039 0.039 SR-90 3 0.08 0.039 0.039 +1 001/003 0.039 0.039 NORTil ANNA R. DOWNS 5.8 Nt 128 Dog.
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| 001/003
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| TTELEMNE NS t
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| See River Water Station Number 11 listed under Ground Water on page 31-C.
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| Note: No gamma emitters were detected in River Water from Station 11. The tritium activity for the River Water was 790 pCi/ liter. ,
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| TTELEDYNE ISOTOPES SIM4ARY OF QUARTERLY RESULTS AND DISCUSSION ,
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| INGESTION EXPOSURE PAThMAY (JULY 1,1979 - SEPTEMBER 30, 1979)
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| MILK (STATION 12, 13, 14)
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| Milk samples were analy:ed for low levels of I-131 (L.T. 0.5 pCi/ liter),
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| for Sr-89, Sr-90 and for gamma emitters especially X-40 and Cs-137. Summari:ed in Table 7 are the radionuclides detected in milk and plotted on Figure 6 is the quarterly ~ average of 3.6 pCi/ liter of Sr-90 in milk. All radionuclides de-tected in milk are at the expected levels of activities. Thus we conclude that no radionuclides in milk can be attributed to operations of NAPS.
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