ML19282C585

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Annual Environ Radiological Monitoring Program Rept,1978.
ML19282C585
Person / Time
Site: North Anna Dominion icon.png
Issue date: 03/27/1979
From: Hopper D, Queener R, Smith E
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19282C583 List:
References
NUDOCS 7903300361
Download: ML19282C585 (90)


Text

{{#Wiki_filter:- a6 ANNUAL EINIRONMENTAL OPERATING REPORT RADIOLOGICAL REPORT FOR THE NORTH ANNA POWER STATION Jan. 1, 1978 - Dec. 31, 1978 Prepared by hh

                                     'R. F. Que'dner-Heallih Physicst Approved by         .hfl, fd(2hl D. M. Hopper- S'uhdrvisor Health Physics
                                               . k.

E. R. Smith, Jr. Superintendent Technic 1 Sg M4 dNs W. 'R . Cartwr .-Station Manager

e FORWARD THIS REPORT IS SUBMI'ITED AS REQUIRED BY APPENDIX B TO OPERATING LICENSE, ENVIRONMENTAL TECHNICAL SPECIFICATIONS FOR NORTH ANNA POWER STATION UNITS 1 AND 2, VIRGINIA ELECTRIC ANb POWER COMPANY DOCKET NOS. 50-338, 50-339 SECTION 5.6.1.1

WTELEDYNE ISOTOPES IWL-6343-432 ( VIRGINIA ELECTRIC AND POWER COMPANY P.O. BOX 402 b!INERAL, VIRGINIA 23117 NORTil ANNA POWER STATION ENVIRONMENTAL RADIOLOGICAL F!ONITORING PROGRAh!

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1978 DESCRIETION OF Tile OPERATIONAL PROGRN1 AND QUARTERLY REPORTS AND ANALYSIS Prepared by TELEDYNE ISOTOPES SO VAN BUREN AVENUE WESTWOOD, NEW JERSEY 07675 [

WTblEDYNE ISOTOPES ( TAllLE OF CONTENTS , Page li LIST OF TABLES LIST OF FIGURES 1 INTR 0l UCTION 2 DESCRIPTION .0F Tile OPERATIONf,L PP0GR/01 2 - Tile RADIOLOGICAI. ENVIRON >1 ENTAL PROGRA.\1 . 11 ABSTRACTS OF ANALYTICAL PROCEDURES I4 ABSTRACTS OF RADI0 ASSAY PROCEDURES 18 QUALITY CONTROL OF ANALYSIS SU> NARY OF QUARTERLY RESULTS AND DISCUSSION 19 A,B ,C,D EXCEPTIONS AND SPECIAL EVENTS 20 A,B,C,D ( AIRBORNE EXPOSURE PATilWAY 28 A,B,C,D DIRECT EXPOSilRE PATI!WAY 31 A,B,C,D WATERBORNE EXPOSURE PATliWAY 38 A,B,C ,D INGESTION EXPOSURE PATilWAY 42 A,B,C ,D CONCLUSIONS 44 REFERENCES A-1 APPENDIX A - DATA TABLES - FIRST QUARTER 1978 B-1 APPENDIX B - DATA TABLES - SECOND QUARTER 1978 C-1 APPENDIX C - DATA TABLES - T!!IRD QUAPifER 1978 D-1 APPENDIX D - DATA TABLES - FOURTil QUARTER 1978 E-1 CRITICAL RECEPTOR SURVEY DATA FOR 1978 (

TCTELEDYNE ISOTOPES LIST OF TABLES Page TABLE 1 Operational Radiological Environmental Monitoring Program 3 TABLE 2 Sacpline Station Identification and Location 8 TABLE 3 Lower Limits of Detection (LLD) 15 TABLE 4 REMP Summary - Airborne Exposurc 22 TABLE 5 REMP

SUMMARY

- Direct Exposure                                   30 TABLE 6  REMP Summary - Waterborne Exposure                              33 TABLE 7  REMP SU:CIARY - Ingestion Exposure                              40 TABLE 8  Radiation Dose to the Individual from Natural and Aritifical    43 Sources LIST OF FIGURES 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 Cc-144 (1977-1978)           21 FIGURE 4 Direct Exposure - Environmental TLD (1977-1978)                 29 FIGURE S Waterborne Exposure - Tritium (1977-1978)                       32 FIGURE 6 Ingestion Exposure - Sr-90 (1977-1978)                          39

TTELEDYNE  : 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 compilation of the data generated to satisfy the monitoring requirements. This program is based on the technical specifications requiring the collection and analysis of var-ious sample media to provide information on the type and quantity of radio-activity in certain indicator organisms or critical pathways. The operational program became mandatory on April 5,1978 upon granting of the operating li-cense for the North Anna Power Station Unit 1. Virginia Electric and Power Company is responsible for the col-1ection of the samples required for the program and Teledyne Isotopes is respoasibic for the analysis of each sampic 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 1,1978 through December 31, 1978. These quarterly data summaries will include a compilation of the radioactivities reported for each sample type and pathway and a summary of the mean, range, and detections / total for each sample type and'radionuclide. From the data summaries, a radiological environmental monitoring program ( summary 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 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 granted requiring the transi' tion 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-tions (Table 1) were phased into the program during the January 1 - Flarch 31, 1978 quarter. The overall objectives (Ref. 7) of the operational radiological envirunmental monitoring program are to identify changes of radioactivity in the vicinity of the North Anna Power Station and to provide information on the types and quaatity of radiation in certain critical pathways and indicator organisms as a basis for evaluating radiation exposure from sta-tion operation. 1

TTELEDYNE . ISOTOPES DESCRIPTION OF Tile OPERATIONAL PROGRAM { THE RADIOLOGICAL ENVIRODfENTAL PROGRMI The .lescription 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 Tcledyne Isotopes for the analytical phase of the progran. 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,:usually 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 axialytical data: from the interim data reports, (2) summaries of the environmental radi.ological 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 releasc point are listed in Table 2 (Ref. 8 ) and shown on Figure 1 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 analyzed for gross beta activity, Quarterly composites of these particulate air samples are analy::ed for Sr-89, Sr-90 (second quarter'only), and gammacemit-tbg nuclides by high resolution Ge(Li) gamma spectrometry. Air sampling stations are located on Figures I and 2 and listed in Table 1. Lapse time recorders are usedtto calculate actual air volumes. Radiogas (Radioiodine) Charcoal cartridges are collected from sampling stations 3, 21, 23, 24 weekly. The cartridges are analyzed for radioiodine by distillation and beta counting. Charcoal cartridge sampling locations are shown on Figures 1 and 2. ( 2

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TTELEDYNE ISOTOPES ( Direct Radiation Environmental direct radiation levels are monitored by thern-oluminescent dosimeters (TLD) using a multi-arca, 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 somples are collected monthly from locations'I2, 13, 14 and analyzed for I-131 by chemical separation and gamma isotopic emit-ters by high resolution Ge(Li) gamma spectrcmetry. Quarterly milk sampics are analyzed 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 co11ceted quarterly from the Environmental Laboratory well and analy:cd 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 surf ace 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 analyzed for tritium, iodine-131, and gamma isotopes. The second quarter surface water sampics or composites are also analyzed for Sr-89, Sr-90.

Fish Fish are co11ceteo annually near the beginning of the season from two locations and analyzed for ganma emitting nuclides by high resolution Ge(Li) gamma spectrometry. Fish sampling sites are at locations 8 and 9 on Figure 1. Terrestrial Vegetation _ Samples of green Icafy vegetation (cultivated or weeds) are collected annually during the harvest frnm two locations, Stations 21 and 23. These samples are analy:cd for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. S. i l. Soil samples are collected from locations near the airborne stations every three years and analy:cd for gamma emitting nuclides f by high resolution Ge(L1) 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:cd for Sr-89, Sr-90. 3

TTELEDYNE ISOTOPES Sediment / Silt ( Silt sampics 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) gamma spectrometry. Sediment / silt samples are analyzed annually for Sr-89, Sr-90. ( ( 4

TABLE 1 NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY A:Q/0R SAMPLE MAP NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS AIRBORNE _ Particulates Site or site boundary: 1,21, Continuous sampler Weekly gross beta en 22, 23 (2/3 running time each filter, quarterly Ccmmunities: 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-131 en radiciodine

                  ,                                                               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 Gamma dose quarterly WATERBORNE Reservoir: 9 Monthly Gamma {sotopicradio-Discharge: 8 iodine H-3 quarterly composite, Sr 89-90 second quarter composite North Anna River: d ll Quarterly Gamma isotopic, H-3 on Ground (well): lA collection, Sr 89-90 second quarter sample

TABLE 1 NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AND/0R SAMPLE MAP' NUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS AQUATIC Reservoir: 9 Semiannually Gamma isotopic on Sediment Discharge: 8 collection, Sr 89-90 North Anna River: 11 - annually Shoreline Vicinity of: 9 INGESTION a a milk Nearest Dairies: 12, 13, 14 Monthly Radioiodine ,e, Gamma , isotopic monthly, Sr 89-90 quarterly Non-dairy activity b Radiciodineb ,e Calculated dose , Gamma b dependent D isotopic Sr 89-90 b Fish Reservoir: 9 . Annually, near Gamma isotopic (Bass, or sunfish Discharge: 8 beginning of season orcrappieandcatfish) Green Leafy 21, 23 Annually during Gamma isotopic on vegetation, collection cultivated or harvest e - weeds. Naturally occurring O _M

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NORTH ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY AND/0R SAMFLE MAP 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-child pathway. Should a dairy be located within the 1 mrem isodose line the sampling 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 accumulated calculated thyroid 15 mrem isodose lines based on the 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, efforts to obtain samples from the owners of the animals will be put forth. If scmples 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 15 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.
c. Radiciodine analyses will be done by chemical separation.

TABLE 2 SAMPLING STATION IDENTIFICATION AND RELATIVE POSITION TO EFFLUENT RELEASE POINT STATION DISTANCE DECREES AND NUMBER LOCATION MILES COMPASS DIRECTION REMARKS 1 On Site 0.2 42 NE 3 Mineral 7.1 243 USW 4 Warcs Crossroads 5.1 287 WNW 5 Cood Hope Church , 4.2 20 NNE 6 Levy 4.7 115 ESE 7 Eumpaso 7.3 167 SSE m 8 Discharge Lagoons 1.1 148 SSE 9 Lake Anna, upstream 2.2 320 NW ' Control 11 North Anna River, downstream 5.8 128 SSE 12 Holladay Dairy 8.3 310 NW 13 Fredericks Hall 5.6 205 SSW 14 Trice Dairy 3.2 202 SSW 21 Route 685 1.0 301 Enal 22 Route 700 1.0 242 WSW 23 Aspen Hills 0.9 158 SSE. 24 Orange 22.0 325 NW Control

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     "RTELEDYNE ISOTOPES

( ABSTRACTS OF THE ANA1XTICAL PROCEDURES 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 (Tabic 3) and associated accuracies required by the nuclear industry in compliance with technical specifications. . Air Particulates Gross Beta Transfer filter to a 2-inch diameter planchet and assay in a Beck-man Sharp h'ide Beta II automatic alpha / beta counter. Gamma Isotopic Analysis . Composite station filters are combined quarterly and radioassayed on a high resolution, high efficiency Ge(Li) detector. Radiogas Iodine-131 k Two precedures are used for the analysis of charcoal cartridges for iodine-131. FETHOD 1., If the charcoal used is NOT impregnated with elemental iodine, iodide carrier is added and leached with NaOH. The stabic iodide and I-131 is then stripped and extracted as iodine and precipitated as PdI 2' mounted on a nylon planchet, and assayed bf low level tet.. counting. FETHOD 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 analyzed by high resolution gamma spectrometry (Ge(Li)) by integration of the I-131 photopeak. Direct Radiation (TLD) CaSO4

Dy thermoluminescent dosimeter packets consisting of the four-area RadiGuard badge are placed at monitoring locations. At the end of the monitoring period, the dosimeters are returned to Teledyne Isotopes for readout. Results are reported in mR for the collection period or mR/ collection time period.

Milk. Iodine-131 Stable iodide carrier is added to an aliquot of milk and the io-dide and 1-131 is removed by anion exchange resin. The iodine is stripped 11

TTELEDYNE . ISOTOPES with Na0l! solution, treated with hydroxylamine hydrochloride and nan 0 , and I 7 extracted into CHC1 as free iodine (I,). It is then back extracted into 3 NallS03 solution and precipitated as PdI 2 . The precipitate is mounted on a 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-card precipitate. To the filtrate and oxalic acid, followed by NH 4 0H 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 SrCO , mounted on a nylon planchet and counted in a low level beta counter for kr-89 and/or the Y-90 ingrowth. Gamma Isotopic Analysis Transfer 1 liter of milk to a 1-11ter wrap-around Marinelli ceunt-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 zinc 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 One liter of sample is transferred to a 1-liter Marinelli wrap-around counting beaker and counted on a Ge(Li) detector. Surface Water Tritium An aliquot of sample is converted to hydrogen by gas reduction in a hot zine furnace, mixed with methane counting gas and is radioassayed util-izing 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 shiciding. ( 12

T TELEDYNE ISOTOPES k 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. Fish Gamma Isotopic Analysis Remove the edible portions by filleting the fish and homogenizing 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. Vegetation / Terrestrial (Green Leafy) Gamma Isotopic Analysis Completely fill a 300 m1 bottle with a green Icafy vegetation. Record sampic 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 m1 bottle with soil, record the sampic weight, and 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 IINO3 ; 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 Nil 40ll until alkaline. Add sat-urated Na2 CO, solution to precipitate SrC0 3, and centrifuge and discard supernate. dissolve precipitate in llNO3 and evaporate to almost dryness. Proceed with Sr-89, Sr-90 purification procedures using fuming nitric acid, an Fe(Oll)3 scavenge, etc. i 13

TTELEDYNE , ISOTOPES ABSTRACTS OF THE RADI0 ASSAY PROCEDURES The lower limits of detection for radionuclides by the radioassay procedures are listed in Table 3. 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. Ge(Li) Gamma Spectrometry Based upon the specific media to be analyzed, samples are counted in 1-liter wrap-around Marinelli type containers, 300 m1 bottles or 2-inch filter paper source geometries on 55 cc Ge(Li) detectors coupled to multi-channel spectrometers. AlI 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 half-life for Y-90 and by multiple counts for Sr-89. ( Tritium

             ..An aliquot of distilled sample is added to scintillat, ion 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 Ceiger 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 be.ta-gamma coincidence spectrometer. Rare Cases Purified fractions are assayed in internal gas proportional counters. ( 14

77'TELECW'NE . IcOTOPES ( TABLE 3.2 LOWER LIMITS OF DETECTION BY llIGli RESOLUTION Ge(Li) GAMMA SPECTROSCOPY ENVIRO.\71 ENTAL SAMPLES h'ater (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 ( 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 SE-02 6 La-410 2E+01 4E-02 2E+01 Ce-141 2E+01 4E-02 3 Cc-144 8E+01 2E-01 2E+01 Ra-226 6E+0] 1E-01 1E+01 Th-228 1E+01 2E- 02 1E+01 ( 16

TTELEDYNE ISOTOPES ( TABLE 3 LONER LDIITS 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 PdI    2 . The non-impregnated with elemental iodine charcoal cartridges must be used when chemical separation is required.
    *** The LLD values listed in this tabic are at the mid-collection time. Sampics must be counted within one half-life after collection for these LLD values to be applicable.

3.29 6 E 4.66 0 at LLD = 1 at (Ref. 10) 2.22 (V)(c)(DF) 2.22 (V)(c)(DF)(Y) k where 8= background = cpm At = counting time = min. dpm 2.22 = conversion factor = pC1 V= volume or weight of sample c= counter efficiency DF = decay factor of the radionuclide from mid-collection to mid-count time Y= chemical yicId LLD = lower limit of detection at the mid-co11cetion time { 17

TTELEDYNE , ISOTOPES 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 01/15/78, of the manual. has been issued to the Virginia Electric and Power Company.

The Quality Control Manual ecntains (a) Specifications for the handling and processing of sampics and the documentation required for calculating and reporting the results of the analysis. (b) The organization 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 sampics. (e) A section on accuracy checks containing summaries of inter-comparison data with EPA cross check programs

2. Laboratcry Procedure Control Approved laboratory procedures are followed at Teledyne Isotopes for the analysis of each samples media for specific radionuclides. Copics of the following procedures were issued to the Virginia Electric and Power Company: Detemination of Jadiostrontium, Detemination of Radioiodine, Detection of Gross Alpha and/or Gross Beta, Detemination of Gamma Spectra, Detemination of Tritium.

( 18

WTELEDYNE ISOTOPES

SUMMARY

OF QUARTERLY RESULTS AND DISCUSSION , . EXCEPTIONS AND SPECIAL EVENTS (JANUARY 1, 1978 - MARCII 31, 1978) EXCEPTIONS The operational program for the North Anna Power Station requires the weekly analysis of I-131 in charcoal filters with air volumes of approx-imately 125 cubic neters and sensitivities of less than 0.024 pCi/Cu. M. (see Table 1 in the Description of the Program) . During the preoperational program most of the charcoal filters were impregnated with elemental iodine necessitating the analysis for I-131 by high resolution gamma spectrometry. By this procedure the limits of detection were lower than the 0.025 pCi/Cu. M. However, the collection periods and the volumes were at least 10 times longer. In addition, the activities were calculated to the end of the collection time. For the operational program, 125 cubic meters of air and calculation to mid-co11cetion were specified to insure against exceeding the sensitivity of 0.025 pCi/Cu. M. This requires the chemical separation of iodine and low level beta counting of the sample --a procedure possibic only with noniodine im-pregnated charcoal. By using nonimpregnated charcoal and processing by chemical separation, the limits of detection are lower than 0.01 pCi/Cu. M. for 125 cubic meters of air and calculation to mid-collection time and counting within S days after collection. It is recommended that nonimpregnated with elemental iodine charcoal cartridges be used and chemical separation be employed to insure compliance with the L.T. 0.025 pCi/Cu. M. specification. SPECIAL EVENTS On March 14, 1978 the Peoples Republic of China detonated an atmospheric nuclear device at the Lop Nor atomic test site. The reported yield of this nuclear device was approximately 10 kilotons. The operational program for the site was implemented in anticipation of initial criticality of Unit i. 19-A

TTELEDYNE - ISOTOPES . SUFMARY OF QUARTERLY RESULTS AND DISCUSSION EXCEPTIONS AND SPECIA: EVENTS (APRIL 1,1978 - JUNE 30,1978) EXCEPTIONS The use of stable iodine impregnated charcoal filters continued during the second quarter of 1978 necessitating radioassay by high resolu-tion gamma spectrometry for I-131. The lower sensitivity gamma spectrometry precludes its use and requires the higher sensitivity of chemical separation of iodine and the use of non-impregnated charcoal filters. Non-impregnated charcoal filters are on order by Vepco and will be used when received. SPECIAL EVENTS On April 5,1978 the operating license for the North Anna Power Station Unit I was granted and the operating phase of the radiological en-vironmental monitoring program is in effect. 19-B

   "mTELEDYNE ISOTOPES

( SU5 MARY PF QUARTERLY RESULTS AND DISCUSSION EXCEPTIONS AND SPECIAL EVENTS (JULY 1,1978-SEPTEMBER 30, 1978) EXCEPTIONS Charcoal filters not impregnated with stabic iodine were phased into the NAPS operations beginning August 1, 1978. The use of these charcoal filters pernits the analysis for I-131 by the more sensitive radiochemical analytical procedure and the linits of detection are lower than the specification of L.T. 0.02S pCi/Cu.ft. SPECIAL EVENTS No unusual events occurred during the third quarter of 1978 that could be interpreted as possibly related to the operations of the North Anna Power Station. The last atmospheric nuclear test in the northern hemisphere was conducted on March 14, 1978 by the Peoples Republic of China. Most of the short lived and early fallout in North Anna already was detected prior to this 3rd quarter of 1978. k > 19-C

'WTELEDYNE

  • ISOTOPES EXCEPTIONS AND SPECIAL EVENTS (OCTOBER 1, 1978 - DECEMBER 31, 1978)

EXCEPTIONS No exceptions were noted during this quarter to affect the radiological environmental conitoring program conducted at the North Anna Power Station of tiac Virginia Electric and Power Company. SPECIAL EVENTS On December 13, 1978, the Peoples Republic of China detonated an atmospheric

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nuclear device at the Lop Nor test site in Central Asia. ( ( 19-D

    'r/TELEDYNE ISOTOPES SU M RY OF QUARTERLY RESULTS AND DISCUSSION

( AIRBORNE EXPOSURE PA'lW AY (JANUARY 1,1978 - MARCil 31, 1978) AIR PARTICULATE Filters were collected weekly from stations 01, 03, 05, 07, 21, 22, 23 and 24 and analyzed as required in Table 1. In addition, sampics from stations 02, 04 and 06 were collected and analyzed even though not required in the radiological monitoring program (Ref. 7) Summarized in Tabic 4 are the radionuclides detected on the air parti-culate filters. Gross beta and Cc-144 activities are plotted on Figure 3. The gross beta activity increased sharply during the week of 03/21-03/28, the result of the atmospheric nuclear detonation on March 14, 1978 by the Peoples Republic of China. Gamma analysis of the quarterly composite of the air particulate filters from each station showed Zr-95, Ru-103, Cs-137, Cc-141 and Cc-144 at levels slightly higher than during the fourth quarter of 1977. The small in-crease of Cc-144 is shown on Figure 3. The radionuclides detected as air parti-culates are fission products attributed to fallout from the Chinese atmospheric nuclear tests during 1976, 1977 and on March 14, 1978. AIR RADI0 IODINE ( , Charcoal filters were co11ceted from stations 03, 21, 23 and 24 as specified in Table 1. In addition charcoal filters were collected at stations 01, 02, 04, 05, 06, 07 and 22 providing additional analysis not required by the ERMP. As discussed under " Exceptions", the limits of detection for I-131 ex-ceeded the MDL of 0.025 pCi/Cu. M. because of the use of elemental iodine impregnated charcoal. Recommendations have been made to correct this deficiency. Iodine-131 was detected in nine of the eleven charcoal filters exposed during the week of 03/21-03/28 at a mean level of 0.07 pCi/Cu. M. See the summary tabic.for I-131 in charcoal filters in Appendix "A" for the compilation of data and see Tabic 4 in this section for an overall summary and comparison. SOIL Sampics were not scheduled for analyses during this quarter. Analyses of soil sampics are required' once every three years at stations 01, 03, 04, 05, 06, 07, 21, 22, 23 and 24. These stations are also co11cetion sites for air particulate sampics with the exception of stations 04 and 06. PRECIPITATION Sample analysis are not required as a part of the environmental monitoring program for the North Anna Power Station environs. The analysis of precipitation samples for gross beta activity at Station 01 are additional ( analysis and provide information useful for interpreting pathways for airborne exposures to radionuclides. 20-A

"RTELEDYNE - ISOTOPES SU.4!ARY OF QUARTERLY RESULTS AND DISCUSSION ( AIRBORNE EXPOSURE PATHh'AY (APRIL 1,1978 - JUNE 30,1978) AIR PARTICULATE Filters were co11ceted weekly from Stations 01 through 07 and 21 through 24 and analyzed as specified in Table 1. Summarized in Table 4 are the radionuclides detected on the air particulate filters (quarterly averages). Gross beta activity and the shorter-lived gamma isotopes (Ru-103, Zr-95, I-131) decreased from the levels monitored during the first quarter. The longer-lived radionuclides (Cs-137 and Cc-144) from the Chinese atmospheric nuclear tests 'of 1977 and March 14, 1978 were - monitored at higher levels compared to the first quarter measurements. Plotted on Figure 3 are the gross beta activities and the Cc-144 activity monitored on air particulate filters. AIR RADI0 IODINE Charcoal filters were collected weekly from Stations 01 through 07 and 21 through 24 and analyzed for I-131. No I-131 was detected during the second quarter of 1978 compared to nine positive readings during the first quarter (see Table 4). ( PRECIPITATION Rainfall samples were collected from Station 01 (Onsite) and are measured for inches of rainfall and then monitored for gross beta and tritium. The deposition of gross beta emitting was 1.4 nCi/sq.m. during the second quarter compared to 2.2 nCi/sq.m. during the first quarter. J 20-B

TTELEDYNE ISOTOPES ( SUE!ARY OF QUARTERLY RESULTS AND DISCUSSION AIRBORNE EXPOSURE PATilNAY (JULY 1,1978-SEPTEJfBER 30, 1978) AIR PARTICULATE Summari:cd in Tabic 4 are the radionuclides detected on the air particulate filters. During this third quarter 1978 the gross beta activity decreased progressively from July through September (See . Figure 3) . Ce-144 also decreased to 0.0089 pCi/Cu.M. ,' the lokest quarterly activity for 1978. From these results the airborne exposure at NAPS was nominal during the 3rd quarter of 1978. AIR RADI0 IODINE No detections of I-131 were monitored during the 3rd quarter of 1978 at NAPS. Starting August 1, the non-impregnated stable iodine cartridges were used permitting analysis by radiochemical procedures and resulting in a lower limit of detection of L.T. 0.024 pCi/Cu.M. Since this date we are confident no sources of I-131 higher than the LLD were detected. k PRECIPITATION Rainfall sample were collected during the 3rd quarter. The gross beta activity is consistent with activities during the 1st and 2nd quarters. s 9 ( 20-C

'PTELEDYNE , ISOTOPES SUSB!ARY OF QUARTERLY RESULTS AND DISCUSSION ( AIRBORNE EXPOSilRE PATIIWAY (OLTOBER 1,1978 - DECEMBER 31, 1978) AIR PARTICULATE The gross beta particulate activity of air sampics flowing through paper filters remained at low 1cycls compared to the activities monitored in the previous quarters of 1978 and in 1977. In addition the gamma activities of fission products and of Cc-144 in particular were below the limits of detection. See Figure 3 for plots of the gross beta and the Ce-144 activities during 1977 and 1978. Summarized in the REMPS table 4 are the data compilation of the nuclides monitored for the operational program at the North Anna Nuclear Power Station (NAPS) . The data in Table 4 is for each of the four qua:ters of 1978. AIR RADI0 IODINE No detections of I-131 in air samples flowing through charcoal filters were monitored during this quarter. The pattern of no detectabic radiodine both at close in to NAPS sites and at distant collection stations justifies the conclusion that the airborne releases from NAPS are negligible and are below the detection limits specified in the NAPS operating specifications. PRECIPITATIO_N ( Rainfall samples collected during this quarter also contained low levels of beta activity per liter of sample. These values are less than half of the activity monitored in rainfall during the previous three quarters (see Table 4) . SOIL No soil sampics were analyzed during 1978. The schedule requires analysis of soi samples once every three years. ( 20-D

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TABLE 4 T TELEDYNEISOTOPES RADIO!I)GICAL ENVIRONMENTAL MONITORING PROGRAM SLMt\RY Airborne Exposure Pathway VIRGINIA ELECTRIC AND POWER COMPANY NORTil ANNA POWER STATION MINERAL, VIRGINI A 23117 PATitNAY OR ANALYSIS DETECTION ALL INDICATOR SM!PLES 14 CATION WIT 11 HICI!EST MEAN CONTROL LOCATIONS REPORTING SAMPLE TYPE NO. LOWER LIMIT MEAN RANCE FRACTION STATION MEAN RANCE ' FRACTION MEAN RANGE FRACTION PERIOD Air Parti- Cross beta 143 0.0076 0.17 0.01-1.6 140/143 5, 7 0.22 26/26 0.10 0.03-0.13 11/13 12/27/77-03/28/78 culates 143 0.13 0.01-0.31 143/143 6, 23 0.16 0.04-[16 0.07- 3 26/26 0.14 0.06-0.27 13/13 03/28/78-06/27/78 154 0 05 0.01-0.15 152/154 23 0.070 143 0.05 0.067 0.03-0.12 14/14 0.067 0.03-0.11 14/14 06/27/78-10/03/78 pCi/cu.m. 0.01-0.10 141/143 24 0.04-0.12 13/13 SAME AS HIGHEST 10/03/7S-01/02/79 nominal air volume = Gross beta 583 0.0076 0.10 0.01-1.6 576/583 5,7 0.22 0.04-1,6 26/26 0.10 0.03-0.13 11/13 12/27/77-01/02/79 125 cu.m. Annual 1st Quarter 1st Quarter Annual pCi/cu.m. S r-89 11 0.003 LLD - 0/11 - - - - LLD - - 2"d quarter only riominal air 03/28/78-06/27/78 volume = 1625cu.m. d ouarter oni Sr-90 13 0.0005 0.0025 11/11 2 03/28/78-06/27/g8 (0.0007-0.00041) 24 0.0041 - 1/1 SAME AS FfC"EST U pC1/cu.m. Gamma 11 - - Isotopic Be-7 - 0.012 0.06 Q O2 -0.09 10/11 23 0.09 - 1/1 0.07 - 1/1 12/27/77-03/28/78 0.11 0.07-0.15 10/11 22 0.15 - 1/1 0.11 - 1/1 03/28/78-06/27/78 nominal air 0.05 0.03-0.07 11/11 23 0.07 - 1/1 0.06 - 1/1 06/27/78-10/03/78 volume = 0.06 0.04-0.09 11/11 03 0.09 - 1/1 0.06- - 1/1 10/03/78-01/02/79 1625cu.m. Be-7 0.012 0.07 0.02-0.15 42/44 22 0.15 - 1/1 0.08 0.06-0.11 4/4 12/27/77- 01/02/79 Zr-95 - 0.0018 0.006 0.004-0.01 9/11 23 0.010 - 1/1 0.006 - 1/1 12/27/77-03/28/78 0.005 0.003-0.006 5/11 22 v.006 - 1/1 <0.003 - 0/1 03/28/78-c6/27/78 LLD - 0/11 - - - - LLD - 0/1 06/27/78-10/03/78 LLD - 0/11 LLD 0/1 10/03/78-01/02/79 Zr-95 0.0018 0.006 0.003-0.01 14/44 23 0.010 1/1 0.006 1/4 12/27//7-01/02/79' n n ~ Station 2- the control location

                -                                                                         m                                                                       -

TABLE 4 TTELEDYNE ISOTOPES RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SL%!ARY Airborne Exposure Pathway VIRGINIA ELECTRIC AND POWER COMPANY NOR111 ANNA PCKER STATION MINERAL, VIRGINIA 23117 PATHWAY OR ANALYSIS DETECTION ALL INDICATOR SAMPLES LOCATION WIT 1! !!!GHEST MEAN CONTROL LOCATIONS REPORTING SAMPLE TYPE NO. LOWER L1?!!T MEAN RANCE FRACTION STT. TION MEAN RANGE ' FRACTION IMEAN* RANGE FRACTION PERIOD Air Parti- Ru-103 - 0.0012 0.014 0.01-0.02 9/11 02 0.021 - 1/1 LLD - 0/1 12/27/77-03/23/73 culates LID - 0/11 - - - - LLD - 0/1 03/23/78-06/27/7S (cont.) 1.LD - 0/11 - -. -- -- LLD -- 0/1 06/27/73-10/03/78 LLD -- 0/11 -- -. LLD 0/1 pCi/cu.m. 10/03/7S-01/02/79 Ru-103 0.0012 0.014 0.01-0.02 9/44 02 0.021 1/1 LLD 0/4 12/27/77 01/02/79 Ru-106 ' - 0.049 0.019 0.016-0.023 2/11 23 0.023 1/1 LLD 0/1 12/27/77-03/23/78 0.016 0.013-0.018 4/11 06 0.018 - 1/1 LLD - 0/1 03/28/78-05/27/78 LLD --- 0/11 LLD 0/1 06/27/78-10/03/78 LLD --- 0/11 -- --- - -- LLD -- 0/1 10/03/78-01/02/79 I:l Ru-106 0.049 0.017 0.013-0.023 6/44 23 0.023 - 1/1 LLD - 0/4 12/27/77-01/02/79 I-13 - 0.002** 0.035 0.03-0.04 3/11 06 0.039 1/1 LLD 0/1 LLD 0/11 12/27/77-03/28/78 1/1 LLD - 0/1 03/28/75-06/27/73 LLD -- 0/11 -- -- -- LLD 0/1 06/27/78-10/03/78 LLD -- 0/11 LLD 0/1 10/03/78-01/02/79 I-131 0.002** 0.03S 0.03-0.04 3/44 06 0.039 -- 1/1 LLD 0/4 12/27/77 01/02/79 Cs-137 - 0.0012 0.0024 0.002-0.004 1/11 23 0.0037 1/1 0.0023 1/1 12'27/77-03/2S/78 0.0032 0.003-0.004 10/11 01 0.004 - 1/1 0.003 - 1/1 03/28/78-06/27/73 0.001S 0.001-0.002 2/11 05 0.0018 -- 1/1 0.0017 -. 1/1 06/27/78-10/03/78 0.0021 - 1/11 03 0.0021 - 1/1 LLD - 0/1 10/03/78-01/02/79 Cs-137 0.0012 0.0026 0.001-0.004 20/44 01 0.004 1/1 0.0023 0.002-0.003 3/4 12/27/77 01/02/79 Station 24 is the control location

  ** At the end of the collection period for a quarterly composite

TABLE 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRN( SLM%RY TTELEDYNE ISOTOPES Airborne Exposure Pathway VIRCINI A ELECTRIC ANP POWER COMPANY NORTl! ANNA POWER STATION MINERAL. VIRGINIA 23117 LOCATION WIT 11 !!!CllEST MEAN CONTROL IDCATIONS REPORTING Pall:WAY OR ANALYSIS DETECTION ALL YNDICAT@ SAltPLES FRACTION STATION MEAN RANCE FRACTION MEAN _' RANCE FRACTION PERIOD I SAMPLE 'IY P E NO. LOWER LIMIT MEAN RANCE Air Parti- 3s-140 0.008** O 330 0.02-0.04 5/1< 07 0.037 - 1/1 LLD - A/1 12/27/77-03/28/78 culate I.LD - 0/11 - - - - LLD - 0/1 03/28/78-06/27/78 (e nt.) 1.LD - 0/11 - - - - LLD - 0/1 06/27/78-10/03/78 pCi/cu.m. LLD - 0/31 - - - - LLD - 0/1 10/03/78-01/02/79 Ba-140 0. 00 $ a 0.030 0.02-0.04 5/J4 07 0.037 - 1/1 LLD - 0/4 12/27/77 01/02/79 Ce-141 v. E - a n o n.01-0.02 8/11 03 0.016 - 1/1 LLD - 0/1 12/27/77-03/28/78 LLD - c.- l' - - - - LLD - 0/1 03/28/78-05/27/78 LLD - 0/1 06/27/78-10/03/78 LLD - 0/11 - - - - LLp . o/11 . . . . LLD - 0/1 10/03/78-01/02/79 Ce-141 0.0018 0.012 0.01-0.02 8/44 01 0.016 - 1/1 LLD - 0/4 12/27/77-01/02/79 Ce-144 0.012 0.021 0.01-0.03 11/11 23 0.029 - 1/1 0.021 - 1/1 12/27/77-03/28/78 0.030 0.02-0.04 10/11 03 0.038 - 1/1 0.027 - 1/1 03/28/78-06/27/78 0.009 0.06-0.01 3/11 05 0.011 - 1/1 0.009 - 1/1 06/27/78-10/03/78 LLD - 0/11 - -

                                                                                                                     -     LLD              -

0/1 10/03/78-01/02/79 Ce-144 0.012 0.020 0.01-0.04 24/44 03 0.038 - 1/1 0.019 0009-0.027 3/4 12/27/77-01/02/79

  "    At the end of the collection period for a quarterly composite
             -                                                                       A                                                                 ^              ,

TABLE 4 TTEi.EDYNE ISOTOPES RADIOLOGICAL ENVIR0h?tENTAL MONITORING PROGRAM STS!ARY Airborne Exposure Pathway VIRGINIA ELECTRIC AND PCNER C0"tPANY NORTl! ANNA PCKER STATION MINERAL VIRCINIA 23117 PATlX\Y OR ANALYS!S DETECTION ALL I!!DICATOR SAftPLES LOCATION WIT 11 HIG!!EST MEAN CONTROL LOCATIONS REPORT 155 SAMPLE TYPE NO. LOWER LIMIT MEAN RANGE FRACTIQN STATION MEAN RANCE FRACTION MEAN RA*:CC FRACTION PERIOD Air I-131 143 0.025* 0.070 0.04-0.12 9/143 23 0.12 - 1/13 DI - - 12/27/77-03/2S/78 Radio- 143 0.3* L1,D - 0/143- - - * - LLD - - 03/28/78-06/27/78 lodin2 154 0.025'* LLD - 0/154 - - - - LLD - 0/14 06/27/78-10/03/78 pC1/cu.m. 143 0.025 LLD - 0/143 - - - - LLD - 0/13 10/03/75-01/02/79 nominal air volume = 125 cu.m. 1-131 583 0.025 LLD - 9/583' - LLD 0/27 12/27/77-01/02/79 U pf-equipment malfunction

    ' Charcoal filters counted on Ge(Li) gamma spectrometer and calculated from the end of collection period.
      ** Non iodine impregnated charcoal used from 08/01/78 and analyzed by radiochemical separation.

Thus 99 of 154 samples meet the L.L.D. of 0.025 pel/Cu.M.

TABLE 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRMI S15 NARY TTELEDYNE ISOTOPES Airborne Exposure Pathway VIRGINIA ELECTRIC AND PO*iER COMPANY NCRT11 ANNA POWER STATION MINERAL. V!RCIN! A 23117 CONTROL LOCATIONS REPORTING DETECTION ALL INDICATOR SMtPLES IDCATION WITilllICl!EST MEAN FRACTION PERICD FAT 1DfAY OR ANALYSIS AANCE FRACTION PEAN RANCE NO. LOWER LIMIT MEAN RANCE FRACTION STATION MEAN SU!PLE TYPE Soil

  • Sr-89 0.8 pCi/gm. dry Sr-90 0.5 Gamma Isotopic -

K-40 - 0.2 Cs-137 - 0.02 Ra-226 - 0.1 Th-228 - 0.02

  • Soil samples are analyzed once every three years.

No analysis scheduled during Jan.1-March 31,1978 quarter. No analysis scheduled during April 1 - June 30,1978 quarter.. No analysis scheduled during July 1-September 30, 1978 quart er. No analysis scheduled during October 1-December 31, 1978 quarter. m  % ,

              -                                                                 m                                                                -

TABLE 4 TTELEDYNE ISOTOPES RADIOLOGICAL ENVIRON'! ENTAL MONITORING PROGRAM StJMMARY Airborne Exposure Pathway INDIAN POINT STATION Atmospheric Pathway PAT!NAY OR ANALYSIS DETECTION ALL INDICATOR SAMPLES LOCATION WITilitICl!EST MEAN

  • C0h7ROL LOC?.TIONS REPORTING SAMPLE TYPE NO. LOWER Ln!!T MEAN RANCE TRACTION STATION MEAN RANCE TRACTION MEAN RANCE TRACTION PERIOD
  **Precipi-        -            3 totion pC1/ liter    Gross beta      -

0.08 25 15-37 3/3

  • Single co11cetion station 01/01/73-03/31/78 inches of rainfs11 - - -

3.03 0.2-5.5 3/3 nC1/sq.m Cross beta - - 2.2 0.08-3.2 3/3 pCi/ liter Cross beta 0.08 14 12-18 3/3

  • Single collection sta. ion 04/01/73-06/30/78 inches of -

g rainfall 4.1 2.9-5.0 - 9 nCi/sq.m 1.4 1.5-1.5 pCi/ liter Gross beta 0.08 23 13-41 3/3

  • Single collection station 07/01/78-09/30/73 inches of rainfall 3.0 0.9-5.7 nCi/sq.m 1.3 0.8-2.3 pCi/ liter Cross beta 0.08 9.3 1.4-25 3/3
  • Single collection station 09/29/78-12/30/78 inches of rainfall 1.7 0.5-2.6 -

nCi/sq.m 0.16 0.08-0.30 pCi/ liter it-3 100 110 - 1/1 Semiannual composite 01/01/78-06/30/78 H-3 100 100 - 1/1 Semiannual composite 07/01/78-12/30/78 Sanples collected from station 01

 ** Not required for the operational program

TTELEDYNE ' ISOTOFF,S SU5DnRY OF QUARTERLY RESULTS AND DISCUSSION DIRECT EXPOSURE PATilWAY (JANUARY 1,1978 - MARCl! 31,1978) ENVIRONMENTAL GA>BM DOSE Environmental Gamma Dose IcVels were monitored by TLD at stations 01, 03, 04, 05, 06, 07, 21, 22, 23 and 24 in accordance with the program in Table 1 (see Reference 7) . In addi': ion TLD measurements were obtained at station 02. Sumarized in Table 5 and on Figure 4 are the average gamma exposure dose levels at the collection stations. No change in the average gama dose has been observed from the previous three quarters - see the comparison with the previous three quarters tables in Appendix "A".

                              .                                                      (

( 28-A

TTELEDYNE lSOTOPES SUSDtARY OF QUARTERLY RESULTS AND DISCUSSION ( DIRECT EXPOSURE PATilh'AY (APRIL 1,1978 - JUNE 30,1978) ENVIRONMENTAL GA>BIA DOSE . Environmental gamma dose levels were monitored with TLD badges at Stations 01 through 07 and 21 through 24 as outlined in Table 1. The average gamma dose during the second quarter is 0.30 mR/ day and is sum-marized in Table 5 and plotted on Figure 4. The aver. age gamma dose for the nine month period 09/20/77-06/27/78 is 0.25 mR/ day. The average of the fourth quarter 1977 and the first and second quarter of 1978 gamma dose is 0.22 mR/ day compared to the corresponding 0.25 nR/ day for the nine month period. The high environmental dose during the second quarter 1978 could result from washdown and ground deposition of fission radionuclides from the March 14, 1978 atmospheric nuclear test by the Peopics Republic of China, k . ( 28-B

'71'TEUE0h(NE - ISOTOPES SU> NARY OF QUARTERLY RESULTS AND DISCUSSION DIRECT EXPOSURE PATHWAY [ (JULY 1,1978-SEPTEMBER 30, 1978) ENVIRONMENTAL GASMA DOSE The average environmental gamma dose rate decreased to 0.19 mr/ day during the 3rd quarter of 1978, During the 2nd quarter the dose rate was the highest (0.30 mr/ day) since the 1st quarter of 1977. This high gamma dose during the 2nd quarter and sharp drop during the third quarter is in agreement with measure-ments at other facilities in the north eastern section of the U.S. ( ( 28-C

T#TELEDYNE ISOTOPES

SUMMARY

OF QUARTERLY RESULTS AND DISCUSSION I DIRECT EXPOSURE PATilNAY (October 1,1978 - December 31, 1978) ENVIRONMENTAL GA>MA DOSE Average environmental gamma radiation dose levels at the stations also used for airborne activity measurements increased from 0.19 mr/ day during the third quarter to 0.21 mr/ day during the fourth quarter of 1978. Plotted on Figure 4 are the quarterly average environmental dose IcVels for 1977 and 1978 and summarized in the REMPS Table 5 a~re the nean, range, and detections for the four quarters of 1978. k ' ( 28-D

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              -                                                                       m                                                                a TABLE 5 TTELEDYNE ISOTOFES                                   RADIOLOGICAL ENVIRONMENTAL MONIT0! TING PROGRAM 

SUMMARY

Direct Exposure Pathway VI9CT::! A ELICTP.IC AND POLT.R CO*!PNT

.LRTI: AN':A Prall!: STA110N MINLitAL, VIRGI'.1 A 23117 PATI:WAY ON ANALYSIS DETECTION ALL INDICATOR SAS*PLES LOCATION WITil HIC 11EST MEAN CONTROL LOCATIONS REPORTING SU:t'I.E TYPE NO. LOWER LDtIT MEAN RANCE FRACTION STATION MEAN RANCE FRACTION MEAN
  • RANCE FRACTION PERIOD T t.D Camma Dose 11
  • 2mr22mr 0.18 0.14-0.22 11/11 23 0.22 .- 1/1 0.14 -

1/1 12/27/77-03/23/73 mR/ day 11 0.30 0.24-0.39 11/11 22 0.39 - 1/1 0.24 - 1/1 03/28/78-06/27/73 11 0.19 0.14-0.25 11/11 06 0.25 - 1/1 0.16 1/1 06/27/73-09/26/78 11 0.21 0.15-0.30 11/11 05 0.30 - 1/1 0.15 7 1/1 09/26/78-12/26/78 Gamma Dose

  • 2mr22mr 0.22 0.14-0.39 44/44 _22 ~0.39 -

1/1 0.17 0.14-0.24 4/4 12/27/77-12/26/78 TLD Gamma Dose 11 0.25 0.19-0.32 11/11 06 0.32 - 1/1 0.19 - 1/1 09/20/77-06/27/78 mR/ day Station 24 is the control location.

  • 2mr 2 2mr per dosimeter

TTELEDYNE . ISOTOPES SU3 MARY OF QUARTERLY RESULTS AND DISCUSSION WATERBORNE EXPOSURE PNDIWAY ( (JANUARY 1,1978 - StARCl! 31, 1978) SURFACE WATER Samples were collected from station 09, reservoir; from station 08, discharge cooling; and from station 11, North Anna River. These three samples were analyzed as outlined in Table 1 and the results are summarized in Tabic 6. Presented on Figure 5 is the tritium activity from station 08, the discharge cooling water. The tritium activ_ity of 110 pCi/ liter is consistent.with preoperational measurements (see References 2 through 6). GROUND WATER Ground water (well water) samples were collected at station IA, the Environmental Laboratory Well and analyzed for tritium and gamma. emitting nuclides. All activities in ground water were below the limits of detection and t_he results are summarized in Table 6. AQUATIC SEDIMENT AND SHORELINE SOIL Samples were collected from station 08, near the discharge cooling water for the NAPS, from station 09 at the reservoir and from station 11, the North Anna River. In addition, a soil sample was collected in the vicinity of ( station 09, the reservoir. Sediment and shoreline soils were analyzed for gamma emitting radio-nuclides and the results are tabulated in Appendix "A" and siamarized in Tabic 6. Usual gamma emitting radionuclides in sediments ate K-40, Cs-137, Ra-226 and Th-228, and the levels of activity are of the san e magnitude as monitored during the preoperational program. ( 31-A

TcTELEDYNE ISOTOPES SUSNARY OF QUARTERLY RESULTS AND DISCUSSION WATERBORNE EXPOSURE PATIINAY (APr4L 1, 1978 - JUNE 30, 1978) SURFACE WATER Sampics co11ceted from the reservoir (Station 09), the discharge cooling (Station 08), and the North Anna River (Station 11) were analyzed for 11-3, gamma isotopic , I-131, Sr-89, and Sr-90. The program summary for these radionuclides is presented in Tabic 6 and the 11-31cyc1 in the dis-charge cooling is plotted on Figure 5. All radionuclides are at or below the environmental preoperational IcVels. GROUND WATER Samples were collected at the Environmental Laboratory Well (Station I A) and analyzed for 11-3, gamma isotopic, Sr-89 and Sr-90. All radionuclides in these samples remained at or below the limits of detection and the results are summarized in Table 6. k 31-B

TTELEDYNE . ISOTOPES SUSB!ARY OF QUARTERLY RESULTS AND DISCUSSION I WATERBORNE EXPOSURE PATHWAY (JULY 1,1978-SEPTEMBER 30, 1978) SURFACE WATER Samples collected from stations 03,09, and 11 were analyzed for I-131, H-3 and gamma isotopes. The H-3 level at Station 08, the Surface Water discharge cooling, increased to 700 pCi/ liter the highest activity monitored at this locatior (see Figure 5). At Station 11, the North Anna River Station, the H-3 activity wa,s 870 pCi/ liter and at Station 09, the Reservoir Station, the H-3 activity.was 420 pei/ liter, These H-3 activities are greater than monitored for the previous quarters of !978 and could be the result of releases, subject to verification, from the NAPS. No I-131 or gamma emitting nuclides were detected in surface water samples inferring that possible releases from NAPS were nominal and non-detectable. GROUND WATER Samples collected at the Environmental Well (Station I A) contains no radioactivities of H-3 or gamma emitters above the limits of detection. The results are summarized in Table 6. ( AQUATIC SEDIMENT AND SHORELINE SOIL The aquatic sediment sampics .an'1 shoreline sampics from the vicinity of station 09 were monitored for gamma emitting radionuclides and Sr-89,Sr-90. Only radionuclides characteristic of sediment and soil were detected and the activity levels- were in the same order of . magnitude as observed in previous years. No radienuclides attributed to NAPS were detected. ( 31-C

TTELEDYNE ISOTOPES SU.\ NARY OF QUARTERLY RESULTS A"D DISCUSSION WATERBORNE EXPOSURE PATIINAY (OCTOBER 1, 1978 - DECEMBER 31, 1978) SURFACE WATER Radionuclides in surface water samples from stations 08,09, and 11 remained at the IcVels monitored in the July-September 1978 quarter. Plotted in Figure S is the tritium activity at station 08, surface water discharge cooling. The activity of tritium at this station remains at 760 pCi/ liter, the trend observed in the previous quarter. Tabulated in the REMPS Tabic 6 are the summaries of detected radioactivities activities monitored during each quarter of 1978. The increase of radioactivity due to operations of the NAPS is detected for tritium and is plotted in Figure 5 for station 08. In addition the tritium level at the reservoir (Station 09) is also higher at 600 pCi/ liter compared to 380 and 420 pCi/ liter monitored in the 2nd and 3rd quarters. The tritium activity at Station 11, North Anna River is 890 pCi/ liter compared to 870 pCi/ liters monitored in the 3rd quarter. No changes in the gamma isotopic, iodine-131 or Sr-89 activities were monitored during,

   . 1978 indicating no detectabic releases of these radionuclides from NAPS by the

( waterborne pathway. GROUND WATER Ground water samples from Station 1A, the Envrionmental Well, contain no detectable levels of monitored radionuclides that could be attributed to operations of NAPS. In fact the radioactivitics of ground water sampics remain below the limits of detection for tritium, gamma isotopes, and for Sr-89, Sr-90. ( 31-D

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TABLE 6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRM! SLMMARY E GNE Waterborne Exposure Pathway Surface Water VIRGINIA ELECTRIC AND POWER COMPANY NORT11 ANNA POKER STATION MINErdt, VIRGINIA 23117 CONTROL LOCATIONS REPCRTING ANALYSIS DCTECTION ALL INDICATOR SMtPLES LOCATION WITil llIG11EST MEAN PATl!KAY OR RANCE FRACTION MEAN RANGE FRACTION PERIOD TYPE NO. LOWER LIMIT MEAN RANCE FRACTION STATION ttEAN SAMPLE 0/3 Single Station 01/01/7S-03/31/78 Discharge 1-131 3 0.5 LLD - 04/01/78-06/30/73 Cooling 3 LLp - o/3 07/01/78-09/30/78 Station 3 1.tp _ 0/3 12/20/73 03 3 Lt.D - 0/3 LLD 0/12 Single Station 01/01/78-12/20/78 pCi/ liter 1-131 12 0.5 - 110 1/1 Single Station 01/01/78-03/31/78 11- 3 1 100 - 04/01/78-06/30/78 1 100 LLD - 0/1 07/01/78-09/30/78 1 100 700 - 1/1 10/19/78-12/20/78 1 100 760 - 1/1 730 700-720 3/4 Single Station 01/01/78-12/20/78 11- 3 4 100 0/3 Single Station 01/01/78-03/31/78 O Gamma 3 Table 3 LLD - 04/01/78-00/30/7s Isotopic 3 Table 3 LLD - 0/3 07/01/78-09/30/78 3 Tabic 3 LLD - 0/3 10/01/78-12/20/78 3 Table 3 LLD - 0/3 Single Station Gamna 01/01/78-12/20/73 Isotopic Table 3 LLD - 0/12 Single Station 12 0/3 Single Station 01/01/78 03/31/7s Reservoir I-131 3 0.5 1.1.D - 04/01/7S-06/30/73 Station 3 LLD - 0/3 07/01/78-09/30/74 09 3 LLD - 0/3 3 0/3 10/01/78-12/20/7S LLD - pCi/ liter 01/01/7S-12/31/78 I-131 12 0.5 LLD - 0/12 Single Station 11 - 3 1 100 LLD - 0/1 Single Station 01/01/78-03/31/78 1 100 380 - 1/1 04/01/78-06/30/78 1 100 420 - 1/1 07/01/78-09/30/78 1 100 600 - 1/1 10/19/78-12/20/73 II- 3 4 100 467 380-600 3/4 Single Station 01/01/78-12/20/73

TABLE 6 . RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SL3 MARY TTELEDYNE ISOTOPES " Waterborne Exposure Pathway Surface Water VIRGINIA ELECTRIC AND POWER COMPANY NCR711 ANNA POWER STATION MINERAL, VIRGINIA 23117 ALL INDICATOR SAMPLES LOCATION WITil IIIGHEST MEAN CONTROL LOCATIONS REPCRT!ht: PATl!WAY CR ANALYSIS DETECTION

  • TYPE NO. LONER LIMIT PEAN RANGE FRACTION STATION MEAN RANGE FRACTION MEAN RANCIT ' f%tCTION
  • PERIOD .

SAMPt.E Reservoir Gamma 3 Tabic 3 LLD - 0/3 Single Station 01/01/78-03/31/78 Station isotopic 3 1.LD - 0/3 04/01/78-06/30/78 09 3 Lt.D 0/3 07/01/78-09/30/78

                                                                   /                                                                            12/20/78-pC1/11 te r Gamma Isotopic 12      Tabic 3      LLD                0/12           Single Statios                                                  01/01/78-12/20/78 North Anna 11-3           1     100         LLD        -

0/1 Single Station 01/01/78-03/31/78 River 1 100 . 1/1 04/01/78-06/30/78 Station 1 870 - 1/1 07/01/78-09/30/78 11 1 890 - 1/1 10/01/78-12/31/73 pCi/ liter 11- 3 4 100 620 - 3/4 Single Station 01/01/78 12/20/78 Ga ma 1 Table 3 LLD - 0/1 Single Station 01/01/78-03/31/78 1sotopic 1 Table 3 LLD - 0/1 04/01/78-06/30/78

                                                                    !I                                                                           07/01/78 09/30/78 fable        L                    /!                                                                           12/20/78 Gamma             Table 3     LLD       -

0/4 Single Station 01/01/78-12/20/73 Isotopic Surface Sr-89* 2 5 LLD - 0/2 Station 08 and 09 LLD 0/2 04/01/78-06/30/78 vlater pCi/ liter Sr-90* 2 1 LLD - 0/2 STATION 08 and 09 LLD 0/2 04/01/78-06/30/78

  • Required only on the second quarter composite of Stations 08 and 09. ,

n m ~ .

n m n. TABLE 6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SlMt.ARY . TTELEDYNE ISOTOPES Aquatic Exposure Pathway Station 01 A VIRGINIA ELECTRIC AND POWER COMPANY NORTl! ANNA POWER STATION MINERAL, VIRGINI A 23117 CONTROL LOCATIONS REPORTING ALL INDICATOR SAMPLES LOCATION WIT 11 IIIGl!EST MEAN FRACTION PERIOD PATI 1%AY OR ANALYSIS DETECTION RANCE FRACTION PEAN RANCE RANCE FRACTION STATION MEAN SAMPLE TYPE NO. LOWER LIMIT MEAN Single Station 03/78 Well Water 11-3 1 100 LLD - 0/1 09/78 LLD 0/1 Single Station Singlo Station 12/78 LLD - 0/1 pCi/ liter 11 - 3 100 Single Station 03/78 Camma 1 Tabic 3 LLD - 0/1 06/78

              !sotopic                       Lt.D       -       0/1            "       "

09/78 LLD - 0/1 10/78 LLD - 0/1 Single Station Single Station 12/78 Camma Table 3 LLD - 0/4 Isotopic Single Station 06/78 S r-89I ") LLD 0/1 1 S Single Station - 06/78 LLD . 1/1 S r-90(*) 1 1 (a) Second quarter only,

. TABLE 6 TTELEDYNE ISOTOPES RADIOLOGICAL ENVIR0hMEhTAL MONITORING PROGRAM SLHMARY Waterborne Exposure Pathway VIRGINIA ELECTRIC AND POWER COMPANY NORTil ANNA POWER STATION MINERAL, VIRGINIA 23117 PA11tWAY OR ANALYSIS DETECTION ALL INDICATOR EAMPLES LOCATION WIT!! IIIGllEST MEAN CONTROL LOCATIONS REPORTING SAMPLE 1YPE NO. LOWER LIMIT MEAN RANCE FRACTION STATION MEAN RANGE FRACTION MEAN RANGE FRACTION PERIOD Sediment / Gamma 3 - Sitt Isotopic pCi/gm. dry K-40 - 0.5 17 6-44 2/3 08 44 - 1/1 5.7 - 1/1 03/78 0.5 8 3 17 3/3 11 17 - 1/1 3.0 - 1/1 09/78 Cs-137 - 0.02 0.0S 0.05-0.12 2/3 11 0.12 - 1/1 0.05 - 1/1 03/78 0.35 - J/3 09 0.35 - 3/1 0.35 - 1/1 09/73 Ra-226 - 0.1 1.0 0.7-1.4 2/3 OS 1.4 - 1/1 0.65 - 1/1 03/78 0.3 LLD - 0/3 -- .- - - 09/78 Th-228 - 0.02 0.74 0.53-0.90 3/3 08 0.90 - 1/1 0.53 - 1/1 03/78 0.02 0.79 - 1/3 OS 0.79 LLp 1/1 - 0/1 09/78 Sr-89 .3 1.0 LLD - 0/3 - - - 1/1 LLD - 0/1 03,09/78

  • S r-90 '3 0,08 0.06 1/3 09 0.06 -

1/1 Same as highest 03,09/73

  • Composite STATION 09 is the control location n m n .

RADIOLOGICAL ENVIRONMENTAL MONITORING PROCRMI SLSOMRY TTELEDYNE ISCTOPES , V!!CINIA ELECTRIC AND POWER C05fPANY NOR111 ANNA PotiER STATION MINERAL. VIRGIN!A 23117 CONTROL IJDCATIONS REPORTING PAT 11XAY OR ANA!.YSIS DETECTION ALL INDICATOR SAMPLES LOCATION WIT 11 !!ICl!EST MEAN STATION MEAN RANCE FRACTION FfEAN RANCE FRACTION PERIOD SM'P! E TYPE NO. LONER LI5flT MEAN RANCE FRACTION Soil from Ganma - Shoreline Isotopic 1 - - I'Ci/gm . d ry K-40 - 0.S 7.3 - 1/1 Singic location - Station 09 03/78 0.S 4.6 - 1/1 Single location - Station 09 09/78 Cs-137 - 0.02 LLD - 0/1 Single location - Station 09 03/78 0.02 0.23 - 1/1 Single location . Station 03 09/73 Ra-226 - 0.1 LLD - 0/1 Single location - Station 09 03/78 0.1 2.4 - 1/1 Single location . Station 09 09/78 Th-228 - 0.02 0.26 - 1/1 Single locatien - Station 09 03/78 0.02 1.6 - 1/1 Single location - Station 09 09/78 0/1_ Single location - Station 09 03,09/73

  • S r- 89 1 0.8 LLD -
                      *Sr-90         1    0.0S          LLD       -

0/1 Single location . Station 09 03,09/73

  • Composite

'WTELEDYNE ISOTOPES

SUMMARY

OF QUARTERLY RESULTS AND DISCUSSION INGESTION EXPOSURE PATIINAY (JANUARY 1,1978 - MARCil 31, 1978 MILK Samples were collected from stations 12, 1.3 and 14 and monitored for low levels of I-131 ( 0.5 pCi/ liter) for gamma emitting radionuclides, and for Sr-89, Sr-90. The IcVels of activity of detected radionuclides are tabulated in Appendix "A" and summari cd in Table 7. Presented on Figure 6 is the Sr-90 activity in milk at levels consistent with preoperational values. FISil Sampics were not scheduled for analysis during this quarter. Analysis is required annually at the beginning of the season for gamma isotopes. GREEN LEAFY VEGETATION Samples were not schedul?d for analysis during this quarter. The specifications require analysis annually during harvest. ( ( 38-A

   "PCTELEDYNE ISOTOPES SU> NARY OF QUARTERLY RESULTS AND DISCUSSION

( INGESTION EXPOSURE PATillfAY (APRIL 1,1978 - JUNE 30,1978) MILK Milk samples are collected from Stations 12,13, and 14 and moni-tored for low levels of I-131 (0.5 pCi/ liter) for gmama isotopes and for Sr-89/Sr-90. Summarized in Tabic 7 are the average activities required under the program summary. No changes in the levels of activity were moni-tored during the second quarter of 1978 compared to the first quarter of 1978. FISit Fish sampics are analyzed annually for gamma isotopes at the beginning of the fishing season on sampics from Stations 09 and 10. A single detection of Cs-137 at 0.05 pCi/gm wet was made on one fish sample. No other gamma emitters were monitored in fish samples from the North Anna Power Station environs. ( ( 38-B

T TELEDYNE ISOTOPES SU) MARY OF QUARTERLY RESULTS AND DISCUSSION ( INGESTION EXPOSURE PATilh'AY (JULY 1,1978-SEPTEMBER 30, 1978) MILK Milk sampics collected from stations 12, 13, and 14 were monitored for low levels of I-131, Sr-89,Sr-90 and gamma emitting radionuclides. No I 131 was detected, consistent with no detections of I-131 in other pathways. Sr-89 was below the limits of detection indicating no recent releases of fission products to the environs. Sr-90 monitored at an average of 4.4 pei/ liter compares favorably with measurements during 1977 and the previous quarters cf 1978. Both K-40 and Cs-137 in milk during this quarter are the same as the results monitored during the first two quarters of 1978. In summary, no radio-nuclides in milk (ingestion pathway) were affected by any possible releases from NAPS. FISil No analysis were scheduled during the third quarter for fish samples. (- (

   %tTELEDYNE ISOTOPES SUSBfARY OF QUARTERLY RESULTS AND DISCUSSION

( INGESTION EXPOSURE PATIIWAY (OCTOBER 1,1978 - DECE5!BER 31,1978) MILK Milk samples from thrce collection stations were analyzed during this quarter. Plotted on Figure 6 is the quarterly average of Sr-90 in nilk. The average Sr-90 activity is 2.2 pei/ liter, a level lower than nonitored during previous quarters of 1977 or 1978. Summarized in Tabic 7 are the analysis performed for radionuclides in milk. No changes were measured in activities of the nonitored radionuclides indicating no detectable levels of radionuclides from NAPS in milk sampics. FISil No analysis were scheduled during this quarter. ( 38-D

                                                                                                                                                                                                                                                                                                                                                                                                                                                                             ~

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n n n TABLE 7 RADIOWGICAL ENVIROWENTAL MONITORING PROGRAh! SLWARY TTELEDYNE ISOTOPES - Ingestion Exposure Pathway VIRGIN!A ELECM IC AND POWER CS!PANY NCR111 ANNA POWER STATION MINERAL. VIRGINI A 23117 CONTROL LOCATIONS REPORTING ANALYSIS DETECTION ALL INDICATOR SAMPLES LOCATION Willi HIG1 TEST >!EAN PATHWAY OR RANGE FRACTION

  • FERIOD NO. LOWER L1? TIT MEAN RANCE TRACTION STATION MEAN RANCE FRACTICN MEAN S U!P LE TYPE Mi1L I-131 9 0.5 LLD -

0/9 - LLD - LLD - 0/9 Jan. .Feb. 55 r. ' 78 0.5 LLD 0/9 . LLD - LLD - 0/9 April-June 1978 9 - 0/9 07/01/7S-09/30/78 pCi/ liter 9 0.5 LLD - 0/9 -- LLD - LLD -- 9 0.5 LLD - 0/9 - - - LLD - 0/9 10/01/78-12/31/78 I-131 36 0.5 LLD - 0/36 - - - - - - Jan.-Dec. 1978 Sr-39 3 8 LLD 0/3 - LLD - - LLD - 0/3 March 1978 LLD 0/3 - LLD - - LLD - 0/3 June 1973 3 - 3 LLD - 0/3 - LLD -- -- LLD -- 0/3 Sept.1978 3 7 LLD - 0/3 - - - - LLD 0/3 Dec. 1978 S r- S9 12 - LLD - 0/12 - - - - - 7 - 1978

$             Sr-90           3  0.8            3.6     2.6-4.4    3/3            14        4.4          -

1/1 3.4 - 9/9 March 1978 3 - 3.2 2.7-3.9 3/3 13 3.9 - 1/1 3.0 - 9/9 June 1978 3 -- 4.4 3.6-5.5 3/3 14 S.5 -- 1/1 3.6 2.6-4.4 10/10 Sept.1978 3 - 2.2 1.2-3.1 3/3 14 3.1 - 1/1 3.4 5.0-3.6 9/9 Dec. 1978 Sr-90 12 0.S 3.4 2.2-4.4 12/12 14 - - - - - - 1978 K-40 9 200 1!76 1070-1300 8/9 14 1247 1210-1300 3/3 1146 1127-1180 9/9 J an . -Ma r. 1975 9 - 1037 843-1240 9/9 12 1220 1180-1240 3/3 1203 1152-1242 9/9 April-June 1973 9 -- 1108 1023-1213 9.9 12 1213 1200-1230 3/3 1132 843-1300 22/23 07/01/73-09/30/73 9 - 1170 984-1460 9/9 14 1260 1160-1460 3/3 1160 343-1300 9/9 Jan.-Sept. 1978 K-40 36 200 1135 843-1460 35/36 14 - - - - - - 1978 Cs-137 9 9 10.7 9.2-12.3 2/9 14 10.7 9.2-12.3 2/3 6.6 S.1-S.5 9/9 Jan.-)Sr. 1978 7.7-16 1/3 8.5 8/15 April-June 1978 9 - 11 4/9 14 16 - 6.6-9.6 Camma 9 -. 10 9.9-11 3/9 14 11 9.8-11.6 2/3 10.0 6.6-16 11/23 07/01/78-09/30/78 9 - 11 9.3-12 2/9 13 11 9.3-12 2/3 8.4 5.1-16 28/47 Jan.-Sept. 1978 Cs-137 36 - 10 7.7-16 11/36 14 - - - - - - 1973

  • Previous three quarters

TABLE 7 TTELEDYNE ISOTOPES RADIOLOGICAL ENVIRONMENTAI. MONITORING PROGRAM StM1ARY Injestion Exposure Pathway VIRGINIA ELECTRIC AND POWER C0t!PANY NORTil ANNA POWER STATION MINERAL. VIRGINTA 23117 CONTROL LOCATIONS REPORTING ANALYSIS DETECTION ALL INDICATOR SAMPLES LOCATION WITH !!!Cl!EST MEIN PATilWAY OR RANCE FRACTICN MEAN RANCE FRACTION PERIOD TYPE NO. LOWER LIMIT MEAN RANGE FRACTION STATION MEAN SMtP LE April 1978 Fish Gamma 2 . LLD - 0/1 pCi/gm wet K-40 - 0.5 LLD - 0/2 - - -

                                                                                                              -    0.05       -

1/1 April 1978 Cs-137 - 0.02 0.05 - 1/2 - - - b Food /Carden Gamma 2 - . . . ,, Crops (nci/gm wet) BE-7 0.2 0.90 0.4-1.4 2/2 , g,pg, 3973 K-40 0.5 5.74 5.7-5.8 2/2 Sept. 1973 Cs-137 0.02 11D - 0/2 g,pg,3973 Control location is Station 09 for fish. O A

TTELEDYNE ISOTOPES CONCLUSIONS (January 1,1978-March 31,1978) For the first quarter (January 1 - March 31,1978) the analysis per-formed to satisfy the provisions of the Environmental Radiological Monitoring Program (ERNP) in the vicinity of the Nortn Anna Power Station (NAPS) are pre-sented in this report. The activity levels of the detected radionuclides remained witnin ranges measured during the preoperational program (see Ref. 6). Thus, the radioactivities measured during this first quarter are the baseline environmental IcVels anc no radionuclides were measured that could by generated by the NAPS. Possible sources of environmental radioactivity and exposure at NAPS are: (1) environmental natural activity, (2) releases from the nuclear power station, (3) worldwide fallout from atmospheric nuclear devices, and (4) ex-posures and released from. medical and industr.ial sources. The ERMP at NAPS is structured to permit evaluation of and assignment to each of these sources of any measured dose or radioactivity. Thus, the detection of iodine-131 during the week of 03/21/73 - 03/28/78 was assigned to worldwide fallout from the Fhrch 14, 1978 atmospheric nuclear detonation by the Peoples Republic of China at Lop Nor, Central Asia. The uniform and widespread distribution of the iodine-131 in nine of the ten operating collection stations supports this conclusion. In addition, iodine-131 fallout was reported by most investigators :hroughout the United States during this period. During this quarter iodine-131 was detected in the airborne exposure pathway (charcoal filters) and not in the waterborne or ingestion pathways. If detected IcVels of radioactivity were measured in water or milk, the dose to the maximum exposed individual (infants) can be calculated from Regulatory Guide 1.109 (Ref. 12). , Thus the correlation of radioactivity with dose level is available in the literature in compilations such as the EPA - Radiological Quality of the Environment in the United States (Ref.11) . Dose levels from natural and arti-ficial sources are listed in Table 8 and taken from Ref. 11. The average ambient external gamma dose in Virginia is listed as 55 mrem / year in Table S. The ambient external gamma dose measured in the environs of NAPS was 0.18 (365) = 66 mr/ year. 42-A

TTELEDYNE LSOTOPES CONCLUSIONS (April 1,1978-June 30,1978) Presented in this report are the analyses performed during the second quarter (April 1 - June 30,1978) to satisfy the provisions of the Environmental Radiological Monitoring Program (ERMP) in the vicinity of the North Anna Power Station (NAPS) . Comparing the data for this quarter with that from the preoperational program justifies the conclusion that the IcVels of radioactivities have remained the same. No radionuclides were n:asured that could be attributed to operations of NAPS. All radio-nuclides detected in the environs of NAPS are at the baseline environmental levels and duplicate results obtained for the preoperational program. Also detected were fission products from the atmospher.ic nucicar tests by the Peoples Republic of China in 1977 and on March 14, 1978 and detec-ted in the atmospheric pathway. Possible sources of environmental radioactivity and exposure of the population are (1) environmental natural radioactivity, (2) releases from nuclear power stations, (3) worldwide fallout from atmospheric nuclear

   -evices, and (4) exposures and releases from medical and/or industrial sources. The ERMP at NAPS is structured to permit evaluation and assign:.ent to these sources of measured doses or radioactivities. Average radiation doses to the individual from natural and artificial sources are listed in Table 8.

J 42-B

TTELEDYNE ISOTOPES CONCLUSIONS ( (JULY 1,1978-SEPTEMBER 30,1978) Appended to this report are the analyses performed during the third quarter of 1978 for the Environmental Radiological Monitoring Program in the environs of the North Anna Power Station of the Virginia Electric and Power Company. The results generated during this quarter show no measurabic effect from operations of the power station, with the possibic exception of increased H-3 1cvels in surface water at the Discharge Lanoons (Station 08), Lake Anna, Upstream (Station 09) and North Anna River, downstream (Station 11). However to verify the source and pathuay of the distribution of the H-3, additional measurements must be generated for future monitoring periods. The possibic sources of natural and 2rtificial environmental radioactivity have been reviewed previously and are listed in Table 8. ( ( 42-C

'FrTELEDYNE ' ISOTOPES CONCLUSIONS (October 1, 1978 - December 31, 1978) ( The results of the Radiological Environmental Monitoring Program conducted at the North Anna Power Station of the Virginia Electric and Power Company in-dicate no detectable levels of nuclear plant related radionuclides other than tritium in the environs. The tritium levels at the three surface water stations (08,09, and 11) have increased during 1978 and the maximum H-3 Icvel was 890 pCi/ liter at Station 11 (North Anna River) during the third quarter of 1978. The maximum H-3 level at the Reservoir (Station 09) was .600 p'Ci/ liter and the dose implications to the maximum exposed individual (assume a child) from ingestion of reservoir water can be calculated from Reg. Guide 1.109 (Ref 12) . From Reg. Guide 1.109 the ingestion dose factor for a child is 2.03 E-07 mrem /pCi ingested and the annual ingestion of water is 510 liters / year, thus the ingestion dose to a child is 0.062 mrem / year. A total body dose of 0.062 nrem/ year is neglibic compared to the K-40 internal constituent of the body of 17 mrem / year (see Table 8) . Thus we conclude that the detectable measurement of 600 pCi/ liter of tritium in drinking water poses no radiation dose implication to man based on the dose factors compiled in Reg. Guide 1.109. [ An atmospheric nuclear test was conducted by the Peoples Republic of China on December 13, 1978. No early fallout from this test was detected in airborne samples collected through the end of the quarter on December 31, 1978. ( 42-D

TTELEDYNE lSOTOPES ( TABLE 8 RADIATION DOSE TO Tl!E INDIVIDUAL FROM NATURAL AND ARTIFICI AL SOURCES (FROM REF. II) 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 (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, Tabic 2-9 of body for beta, and gamma witole body Global fallout - total annual        4.4 mrem / year            Page 131, Table 4-10 per capita body dose, est. 1980

( 43

TTELEDYNE ISOTOPES REFERENCES (

1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8
        " Environmental Technical Specifications for Nucicar Power Plants,"

December 1975.

2. Quarterly reports on the Environmental Radiological Monitoring Pro-gram (ERMP) at the North Anna Power Station prepared by Teledyne 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 (IWL-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-026S-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 Program - July 1, 1974 - September 30, 1977 IWL-5343-426. Prepared for Virginia Electri'c and Power Company (NAPSI. (
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. 50-33S and 50-336.
8. Virginia Electric and Power Company, Radiological Environmental Moni-toring Manual, June 1977.
9. Teledyne Isotopes, " Environmental Radiation Analysis Quality Control Manual," IWL-0032-361, 1975, Copy No. 14 issued to Virginia Electric and Power Company.
10. Energy Research and Development Administration, ilASL Procedures Manual, (llASL-300, D-03) .
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,
           " Calculation of Armual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Ap-pendix I," October 1977.

( 44

           -                                                    A                                                         -
  'Tr'TELJEDYNE ISCTTC) PES APPENDIX D TABLE OF CONTENTS             OCTOBER 1-DECEMBER 31, 1978 0

EXPOSURE ANALYTICAL SUSS'JutY PREVIOUS THREE PATHWAY SAMPLE ANALYSIS DATE TABLES QUARTERS TABLES Airborne Air Particulate Cross Beta (even) D-2:D-22 See the REMPS Tables in See the RE5t?S Tables Camma Isotopic (odd) D-3:D-23 the section on Quarterly in the section on Results and Discussion. Quarterly Results and Air Radiciodino I-131 (even) D-2:D 22 The fourth quarter result Discussion. The first satisfies this requirement. three quarters of 1978 Precipitation Cross Beta D-24 satisfy this requiremet H-3 D-25 Camma Isotopic D-25 Direct TLD Gamma Dose D-26 Waterborne Discharge Water (8) I-131 D-27 c2 Camma Isotopic D-27 L H-3 D-29 Reservoir Water (9) I-131 D-28 Camme Isotopic D-28 11- 3 D-29 North Anna River Camma Isotopic D-30 Il-3 D-30 Well Water (01) Camma Isotopic D-31

                                              !!-3                         D-31 Ingestion          Milk                I-131                        D-32:D-34 Camma Isotopic               D-32:D-34 Sr-89, Sr-90                D-35

NORTH ANNA POWER STATION TTE1.EDYNE ISOTOPES A. AIR PARTICULATE G OIARCOAL FILTERS STATION NUMBER 01 AP FILTER MID COUNT CHARCOAL FILTER MID COUNT COLLECTION DATE TIME GROSS 8 ETA TIME I-131 START STOP DATE (pCi/Cu.M) DATE (pCi/Cu.M) DATE DATE VOLUME UNITS 1.8 +-0.8 E-02 10/17 L.T. 6. E-03 10/03/78 10/10/78 1.40E 02 CU. M. 10/20 2.4 +-0.6 E-02 10/26 L.T. 7. E-03 10/10 10/17 1.35E 02 CU. M. 10/27 11/01 4.9 +-0.8 E-02 10/31 L.T. 9. E-03 10/17 10/24 1.19E 02 CU. M. 10/24 10/31 SAMPLE NOT COLLECTED NONE 11/15 7.8 +-0.9 E-02 11/14 L.T. 1. E-02 10/31 11/07 1.23E 02 CU. M. 5.4 +-0.8 E-02 11/21 L.T. 9. R-03 o 11/07 11/14 1.40E 02 CU. M. 11/21 4.1 +-0.8 E-02 11/28 L.T. 8. L-03 11/14 11/21 1.35E 02 CU. M. 11/30 12/08 3.6 +-0.7 E-02 11/30 L.T. 9. E-03 11/21 11/28 1.37E 02 CU. M. 12/14 2.7 +-0.7 E-02 12/13 L.T. 8. E-03 11/28 12/05 1.39E 02 CU. M. 12/26 3.1 +-0.7 E-02 12/18 L.T. 1. E-02 12/05 12/12 1.39E 02 CU. M. 12/30 3.8 +-0.6 E-02

                                                                                                  ~

12/27 L.T. 2. E-02 12/12 12/19 1.39E 02 CU. M. 01/04 3.0 +-0.6 E-02 01/04 L.T. 1. E-02 12/19 12/26 1.35E 02 CU. M. 2.7 +-0.8 E-02 01/10 L.T. 9. E-03 12/26 01/02 1.39E 02 CU. M. 01/12 y e

n n n

                                                                                                               ~

TTELEDYNE ISOTOPES non7dANNAPOWERSTATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pC1/Cu. M.) STATION NUMBER 01 DATE COLLECTED: FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER GAMMA SPECTRUM ANALYSIS: BE-7 7.85+-2.24E-02 9.64+-2.70E-02 4.45+-1.95E-02 4.78+-1.26E-02 K-40 L.T. 5. E-02 L.T. 3. E-02 L.T. 4. E-02 L.T. 4. E-02 MN-54 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 CO-58 L.T. 3. E-03 L.T. 2. E-03 L.T. 2 E-03 L.T. 2. E-03 FE-59 L.T. 8. E-03 L.T. 8. E-03 L.T. 5. E-03 L.T. 4 E-03 CO-60 L.T. 2. E-03 L.T. 1. E-03 L.T. .2. E-03 L.T. 2 E-03 ZN-65 L.T. 5. E-03 L.T. 3. E-03 LgT. 4 E-03 L.T. 4 E-03 ZR-95 2.15+-2.21E-03 L.T. 4. E-03 L.T. 3. E-03 L.T. 2. E-03 RU-103 4.35+-2.64E-03 L.T. 5. E-03 L.T. '3. E-03 L.T. 2. E-03 RU-106 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 1. E-02 I-131 L.T. 7. E-02 L.T. 2. E 00 L.T. 3. E-02 L.T. 2. E-02 CS-134 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 CS-137 L.T. 2. E-03 4.09+-1.23E-03 L.T. 2. E-03 L.T. 1. E-03 BA-140 L.T. 2. E-02 L.T. 1. E-01 L.T. 9. E-03 L.T. 1. E-02 CE-141 L.T. 7. E-03 L.T. 8. E-03 L.T. 5. E-03 L.T. 2. E-03 CE-144 2.50+-1.17E-02 3.60+-0.72E-02 L.T. 1 E-02 L.T. 6. E-03 RA-226 L.T. 3. E-02 L.T. 2. E-02 L.T. 3. E-02 L.T. 1. E-02 TH-228 L.T. 3. E-03 L.T. 2 E-03 L.T. 2. E-03 L.T. 1. E-03

NORT11 ANNA POWER STATION TTELEDYNE ISOTOPES A. AIR PARTICULATE G O!ARCOAL FILTERS STATION NUMBER 02 AP FILTER HID COUNT CitARCOAL FILTER HID COUNT COLLECTION DATE TIME GROSS BETA TIME I-131 START STOP DATE (pCi/Cu.M') DATE (pCi/Cu.H) DATE VOL15tE ' UNITS DATE 2.4 +-0.8 E-02 10/17 L.T. 6. E-03 10/03/78 10/10/78 1.34E 02 CU. M. 10/20 3.6 +-0.6 E-02 10/25 L.T. 7. E-03 10/10 10/17 1.36E 02 CU. M. 10/27 2.9 +-0.7 E-02 10/31 L.T. 8. E-03 10/24 1.08E 02 CU. M. 11/01 10/17 5.1 +-0.7 E-02 11/09 L.T. 1. E-02 10/31 1.38E 02 CU. M. 11/10 10/24

5. 3 + -0. 7 E-02 11/14 L.T. 7. E-03 10/31 11/07 1.35E 02 CU. M. 11/15 4.5 +-0.7 E-02 11/21 L.T. 9. E-03 11/14 1.39E 02 CU. M. 11/21 11/07 2.6 +-0.7 E-02 11/28 L.T. 1. E-02 11/21 1.35E 02 CU. M. 11/30 11/14 3.2 -0.7'E-02 12/05 L.T. 1. E-02 11/28 1.36E 02 CU. M. 12/08 11/21 3.0 +-0.7 E-02 12/13 L.T. 9. E-03 12/05 1.39E 02 CU. M. 12/14 11/23 3.5 +-0.7 E-02 12/18 L.T. 8. E-03 12/12 1.37E 02 CU. M. 12/26 12/05 3.9 +-0.7 E-02 12/27 L.T. 1. E-02 12/19 1.39E 02 CU. M. 12/30 12/12 4.6 +-0.7 E-02 01/04 L.T. 1. E-02 12/26 1.33E 02 CU. M. 01/04 12/19 4.0 +-0.9 E-02 01/11 L.T. 8. E-03 1.37E 02 CU. M. 01/12 12/26 01/02 O M ,
    -                                                   m                                              -

TTELEDYNE ISOTOPES NORTH ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pCi/Cu. M.) STATION NUMBER 02 DATE COLLECTED: FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER CAM 5.A SPECTRUM ANALYSIS: BE-7 L.T. 4. E-02 7.67+-1.94E-02 2.81+-1.04E-02 4.16+-1.00E-02 K-40 L.T. 5. E-02 L.T. 2. E-02 L.T. 4. E-02 L.T. 2. E-02 MN-54 L.T. 2. E-03 L.T. 1. E-03 L.T. 1. r-03 L.T. 9. E-04 CO-58 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 1. E-03 FE-59 L.T. 7. E-03 L.T. '7. E-03 L.T. 5. E-03 L.T. 3. E-03 CO-60 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 ZN-65 L.T. 5. E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 2. E-03 ZR-95 5.41+-2.53E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 1 E-03 RU-103 2.09+-0.36E-02 L.T. 4 E-03 L.T. 2. E-03 L.T. 1. E-03 RU-106 L.T. 2. E-02 1.44+-0.69E-02 L.T.  ?. E-02 L.T. 8. E-03 I-131 L.T. 8. E-02 L.T. 1. E 00 L.T. 2. E-02 L.T. 2. E-02 CS-134 L.T. 2. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 8 E-04 CS-137 L.T. 2. E-03 2.95+-0.65E-03 L.T. 1. E-03 L.T. 1. E-03 BA-140 2.86+-1.34E-02 L.T. 2. E-01 L.T. 1. P-02 L.T. 1. E-02 CE-141 1.43+-0.60E-02 L.T. 5. E-03 L.T. 3. E-03 L.T. 2. h-03 CE-144 2.12+-1.26E-02 2.46+-0.37E-02 L.T. 8. E-03 L.T. 3. E-03 RA-226 L.T. 3. E-02 L.T. 9. E-03 L.T. 2. E-02 L.T. 9. E-03 TH-228 L.T. 3. E-03 L.T. 1. E-03 L.T. 14 E 03 L.T. 1. E-03

Wttt.htNNt ISU(OPES NORTil ANNA POWER STATION A. AIR PARTICULATE G CllARCOAL FILTERS STATION NUMBER 03 HID COUNT AP FILTFD MID COUNT Cl{ARCOAL FILTER C01. LECT 10N D,*TE I-131 TIME CROSS BETA TIME START STOP (pCi/Cu.M) DATE VOLINE UNITS DATE (pCi/Cu.M) DATE DATE 10/03/78 10/10/73 1.34E 02 CU. M. 10/20 4.8 +-0.9 E-02 10/17 L.T. 6. E-03 CU. M. 10/2, 5.6 +-0.7 E-02 10/25 L.T. 7. E-03 10/10 10/17 1.37E 02 1.28E 02 CU. M. 11/01 7.0 +-0.8 E-02 10/31 L.T. 1. E-02 10/17 10/24 1.38E 02 CU, M. 11/10 5.1 +-0.7 E-02 11/09 L.T. 1. E-02 10/24 10/31 1.42E 02 CU. M. 11/15 1.0 +-0.1 E-01 11/14 L.T. 9. E-03 10/31 11/07 o 11/07 11/14 1.35E 02 CU. M. 11/21 6.9 +-0.8 E-02 11/21 L.T. 8. E-03 1.36E 02 CU. M. 11/30 5.4 +-0.8 E-02 11/28 L.T. 7. E-03 11/14 11/21 CU. M. 12/08 5.4 +-0.8 E-02 12/05 L.T. 1. E-02 11/21 11/28 1.27E 02 1.37E 02 CU. M. 12/14 4.8 +-0.8 E-02 12/13 L.T. 9. E-03 11/28 12/05 CU. M. 12/26 4.9 +-0.8 E-02 12/18 L.T. 8. E-03 12/05 12/12 1.34E 02 CU. M. 12/30 5.0 +-0.7 E-02 12/27 L.T. 1. E-02 12/12 12/19 1.37E 02 CU. M. 01/04 6.8 +-0.8 E-02 01/04 L.T. 9 E-03 12/19 12/26 1.33E 02 CU. M. 01/12 5.2 +-0.9 E-02 01/10 L.T. 7. E-03 126 01/02 1.37E 02

             -                                               n                                                       ,           .
                                                            ;r

n n n N ORT!! ANNA POWER STATION .

 'rcTELEDYNE ISOTOPES QUARTERLY COMPOSITE OF AIR PARTICULATES' (pCi/Cu. M.)

STATION NUMBER 03 TilIRD QUARTER FOURTH QUARTER DATE COLLECTED: FIRST QUARTER SECOND QUARTER . CAMMA SPECTRUM ANALYSIS: S.93+-1.15E-02 8.46+-1,69E-02 4.85+-2.45E-02 9.50+-3.05E-02 BE-7 L.T. 4. E-02 L.T. 2. E-02 L.T. 4. E-02 K-40 L.T, 6. E-02 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 MN-54 L.T. 1. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 3. E-03 CO-SS L.T. 3. E-03 L.T. 4. E-03 L.T. 9. E-03 L.T. 1. E-02 FE-59 E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 2. CO-60 L.T. 3 E-03 L.T. 3. E-03

6. E-03 L.T. 4. E-03 ZN-65 L.T.

E-03 L.T. 2. E-03 L.T. 2. E-03 4.54,-2.270-03 L.T. 5. ZR-95 L.T. 2. E-03 L.T. 2. E-03 L.T. 6. E-03

  • RU-103 1.52+-0.48E-02 E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 3. E-02 L.T. 2.

RU-106 L.T. 2. E 00 L.T. 1. E-02 L.T. 3. E-02 1-131 L.T. 1. E-01 L.T. 2. E-03 L.T. 1. E-03 L.T. 1. E-03 CS-134 L.T. 3. E-03 3.49+-1.11E-03 L.T. 1. E-03 2.11+-1.10E-03 CS-137 L.T. 3. E-03 E-01 L.T. 1. E-02 L.T. 1. E-02 L.T. 3. .-02 L.T. 2. BA-140

2. E-03 L.'. 3. E-03 1.63+-0.55E-02 L.T. 1. E-02 L.T.

CE-141 6.35+-3.34E-03 L.T. 6. E-03 2.21+-1.36E-02 3.77+-0.80E-02 CE-144 E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 4. E-02 L.T. 2. RA-226 E-03 L.T. 1. E-03 L.T. 2. E-03 E-03 L.T. 2. Til-228

                                    .T. 4.

NOR11! ANNA POWER STATION TTEt.EDYNE ISOTOPES A. AIR PARTICULATE G OLARCOAL FILTERS STATION NUMBER 04 MID COUNT AP FILTER MID COUNT CmRCOAL FILTER COLLECTION DATE TD!E GROSS BETA TIME I-131 START STOP DATE (pCi/Cu.M) VOLUME UNITS DATE (pCi/Cu.M) DATE DATE 3.0 +-0.9 E-02 10/17 L.T. 7. E-03 10/10/78 1.34E 02 CU. M. 10/20 10/03/78 4.2 +-0.7 E-02 10/26 L.T. 7. E-03 10/17 1.35E 02 CU. M. 10/27 10/10 4.0 +-0.6 E-02 10/31 L.T. 7. E-03 10/24 1.38E 02 CU. M. 11/01 10/17 1.9 +-0.6 E-02 11/09 L.T. 1. E-02 10/24 10/31 1.36E 02 CU. M. 11/10 4.7 +'-0.7 E-02 11/14 L.T. 8. E-03 11/07 1.34E 02 CU. M. 11/15 10/31 4.2 +-0.7 E-02 11/21 L.T. 1. E-02 11/14 1.34E 02 CU. M. 11/21 11/07 ? 3.6 +-0.7 E-02 11/28 L.T. 9. E-03 11/21 1.36E 02 CU. M. 11/30 = 11/14 3.4 +-0.7 E-02 12/05 L.T. 1. E-02 11/28 1.36E 02 CU. M. 12/08 11/21 3.3 +-0.8 E-02 12/13 L.T. 8. E-03 12/05 1.36E 02 CU. M. 12/14 11/28 3.5 +-0.7 E-02 12/18 L.T. 1. E-02 1.37E 02 CU. M. 12/26 12/05 12/12 3.1 +-0.6 E-02 12/27 L.T. 1. E-02 12/19 1.39E 02 CU. M. 12/30 12/12 5.0 +-0.7 E-02 01/04 L.T. 1. E-02 12/26 1.32E 02 CU. M. 01/04 12/19 4.5 +-0.9 E-02 01/10 L.T. 1. E-02 01/02 1.385 02 CU. M. 01/12 12/26

                                                           ^                                                   _
    -                                                  m                                                    .

'AFTELEDYNE IS7 TOPES NORTH ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pC1/Cu. M.) STATION NUMBER 04 DATE LOLLECTED: FIRST QUARTER SECOND QUARTER THIRD OUARTER FOURTH QUARTER G A\tM A SPECTRUM ANALYSIS: BE-7 2.31+-1.00J-02 L.T. 3. E-02 4.18+-2.09E-02 4.44+-1.37E-02 K-40 L.T. 3. E-02 L.T. 3. E-02 L.T. 5. E-02 L.T. 3. E-02 MN-54 L.T. 1. E-03 L.T. 1. E-03 L.T. 3. E-03 L.T. 1. E-03 CO-58 L.T. 2. E-03 L.T. 2. E-03 L.T. 6. E-03 L.T. 2. E-03 FE-59 L.T. 4. E-03 L.T. 9. E-03 L.T. 6. E-03 L.T. 5. E-03

                                                                               '
  • U-03 CO-60 L.T. 1. E-03 L.T. 1. E-03 '2. L.T. 2. E-03 ZN-65 L.T. 3. E-03 L.T. 3. E-03 L.T. 5. E-03 '. . T . 3. E-03 ZR-95 L.T. 2. E-03 L.Y. 3. E-03 L.T. 3. E-03 L.T. 2. E-03 RU-103 L.T. 2. E-03 L.T. 5. E-03 L.T. 4. E-03 L.T. 2. E-03 kU-106 L.T. 1. E-02 L.T. 1. E-02 L.T. 2. E-02 L.T. 1. E-02 I-l' 1 L.T. 3. E-02 L.T. 2. E 00 L.T. 5. E-02 L.T. 2. E-02 CS >34 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 CS-137 L,T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 BA- 40 L.T. 1. E-02 L.T. 1. E-01 L.T. 1. E-02 L.T. 9. E-03 CE-141 L.T. 2. E-03 L.T. 9. E-03 L . T'. 6. E-03 L.T. 2. E-03 CE-144 8.57+-4.06E-03 L.T. 9. E-03 L.T. 1. E-02 L.T. 5 E-03 RA-226 L.T. 1. E-02 L.T. 2. E-02 L.T. 3. E-02 L.T. 1. E-02 Tif - 2 2 8 L.T. 1. E-03 L.T. 2. E-03 L.T. 3. E-03 L.T. 1. E-03

NOR711 ANNA POWER STATION TTELEDYNE ISOTOPES A. AIR PARTICULATE f. C!lARCOAL FILTERS STATION NGtBER 05 AP FILTER MID COUNT C!lARCOAL FILTER MID C0 TNT COLLECTION DATE CROSS BETA TIME 1-131 TDIE START STOP DATE (pCi/Cu.M) DATE (pCi/Cu.M) DATE DATE VOLTA!E ' UNITS 3.2 +-0.8 E-02 10/17 L.T. 5. E-03 10/03/78 10/10/78 1.32E 02 CU, M. 10/20 10/27 4.6 +-0.7 E-02 10/26 L.T. 7. E-03 10/10 10/17 1.34E 02 CU. M. CU. M. 11/01 4.8 +-0.7 E-02 10/31 L.T. 1. E-02 10/17 10/24 1.37E 02 CU. M. 11/10 3.9 +-0.7 E-02 10/09 L.T. 1. E-02 10/24 10/31 1.37E 02 11/15 7.1 +-0.8 E-02 11/14 L.T. 1. E-02 10/31 11/07 1.34E 02 CU. M. CU. M. 11/21 6.0 +-0.8 E-02 11/21 L.T. 8. E-03 11/07 11/14 1.39E 02 CU. M. 11/30 5.3 +-0,.B E-02 11/28 L.T. 7. E-03 11/14 11/21 1.31E 02 CU. M. 12/08 3.3 +-0.7 E-02 12/05 L.T. 7 E-03 11/21 11/28 1.43E 02 12/14 4.5 +-0.8 E-02 12/13 L.T. 1. E-02 11/28 12/05 1.43E 02 CU. M. 12/26 4.4 +-0.7 E-02 12/18 L.T. 7. E-03 12/05 12/12 1.40E 02 CU. M. 1.38E 02 CU. M. 12/30 d.4 +-0.7 E-02 12/27 L.T. 2. E-02 12/12 12/19 01/04 5.6 +-0.7 E-02 01/04 L.T. 1. E-02 12/19 12/26 1.35E 02 CU. M. 01/12 4.6 +-0.9 E-02 01/10 L.T. 7. E-03 12/26 01/02 1.35E 02 CU. M. a h

     ~                                                 m                                                     n k

TTELEDYNE ISOTOPES NORTl! ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pci/Cu. M.) STATION NUMBER 05 DATE COLLECTED: FIRST QUARTER SECOND QUARTER TitIRD QUARTER FOURTil QUARTER GAMMA SPECTRUM ANALYSIS: BE-7 6.05+-2.04E-02 1.22+-0.27E-01 5.67+-1.02E-02 5.96+-1.22E-02 E-02 L.T. 2. E-02 K-40 L.T. 4 E-02 L.T. 2. E-02 L.T. 2. E-03 L.T. E-03 L.T. 9. E-04 L.T. 1. E-03 MN-p4 L.T. 2. 2. E-03 L.T. E-03 L.T. 1. E,03 L.T. 1. E-03 CO-58 L.T. 2. 3. FE-59 L.T. 6. E-03 L.T. 9. E-03 L.T. 3 E-03 L.T. 4. E-03

2. L.T. 2. E-03 L.T. 9. E-04 L.T. 1. E-03 o CO-60 L.T. E-03 L.T. 4. E-03 L.T. 2. E-03 L.T. 3. E-03 ZN-65 L.T. 4. E-03 2R-95 L.T. 3. E-03 5.17+-2.37E-03 L.T. 3 E,03 L.T. 1. E-03 RU-103 1.83+-0.33E-02 L.T. 5. E-03 L.T. 1. E-03 L.T. 2. E-03 E-02 L.T. 2. E-02 L.T. 8. E-03 L.T. 9. E-03 RU-106 L.T. 2.

L.T. 5. E-02 L.T. 2 E 00 L.T. 2. E-02 L.T. 2. E-02 1-131

2. E-03 L.T. 1. E-03 L.T. 9. E-04 L.T. 1. E-03 CS-134 L.T.

2.74+-1.37E-03 3.28+-0.83E-03 1.7D+-0.79E-03 L.T. 1. E-03 CS-137 2.78+-1.56E-02 L.T. 2. E-01 L.T. 6. E-03 L.T. 1. E-02 BA-140 1.09+-0.46E-02 L.T. 7. E-03 L.T. 2. E-03 L.T. 2. E-03 CE-141 2.82+-0.96E-02 3.44+ 0.54E-02 1.10+-0.40E-02 L.T. 4. E-03 CE-144 RA-226 L.T. 2. E-02 L.T. 1. E-02 'L . T . 1. E-02 L.T. 9. E-03 Tif- 2 2 8 L.T. 3. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03

TTELEDYNE ISOTOPES NORIll ANNA POWER STATION A. AIR PARTICULATE 6 OfARCOAL FILTERS STATION NW!BER 06 COLLECTION DATE MID COUNT AP FILTER HID COUNT CIIARCOAL FILTER START STOP TIME CROSS BETA TIME 1-131 DATE DATE VOLmtE UNITS DATE (pCi/Cu. -l) DATE (pCi/Cu.M) 10/03/78 10/10/78 1.35E 02 CU. M. 10/30 1.4 +-0.8 E-02 10/17 L.T. 8. E-03 10/10 10/17 1.36E 02 CU. M. 10/27 3.8 +-0.6 E-02 10/26 L.T. 8. E-03 10/17 10/24 1.38E 02 CU. M. 11/01 2.0 +-0.5 E-02 10/31 L.T. 9. E-03 10/24 10/31 1.37E 02 CU. M. 11/10 5.9 +-0.8 E-02 11/09 L.T. 8. E-03 10/31 11/07 1.37E 02 CU. M. 11/15 5.8 +-0.7 E-02 11/14 L.T. 1. E-02 11/07 11/14 1.41E 02 CU. M. 11/21 3.0 +-0.6 E-02 11/21 L.T. 8. E-03 11/14 11/21 1.33E 02 CU. M. 11/30 4.3 +-0.8 E-02 11/28 L.T. 6. E-03 11/21 11/28 SAMPLE NOT COLLECTED NONE 11/28 12/05 1.35E 02 CU. M. 12/14 3.6 +-0.8 E-02 12/13 L.T. 7, E-03 12/0S 12/12 1.36E 02 CU, M. 12/26 3.4 +-0.7 E-02 12/18 L.T. 9. E-03 12/12 12/19 1.41E 02 CU. M. 12/30 3.6 +-0.6 E-02 12/27 L.T. 1. E-02 12/19 12/26 1.33E 02 CU. M. 01/04 5.1 +-0.7 E-02 01/04 L.T. 9. E-03 12/26 01/02 1.39E 02 CU. M. 01/12 3.3 +-0.8'E-02 01/30 L.T. 8. E-03 n - a

e m n TTELEDYNE ISOTOPES NORTil ANNA POWER STATION . QUARTERLY COMPOSITE OF AIR PARTICULATES (pCi/Cu. M.) STATION NUMBER 06 DATE COLLECTED: FIRST QUARTER SECOND QUARTER

  • T!!IRD QUARTER FOURTil QUARTER GAMMA SPECTRUM ANALYSIS:

DE-7 6.35+-1.40E-02 1.13+-0.22E-01 4.76+-1.40E-02 4.86+-1.566-02 K-40 L.T. 2. E-02 L.T. 4. E-02 L.T. 4. E-02 L.T. 4 E-02 MN-54 L.T. 1. E-03 L.T. 4. E-03 L.T. 1. E-03 L.T. 1. E-03 CO-58 L.T. 1. E-03 L.T. 7. E-03 L.T. 2 E-03 L.T. 2. E-03 FE-59 L.T. 5. E-03 L.T. 3. E-02 L.T. 5. E-03 L.T. 5. E-03 e

CO-60 L.T. 2. E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 1. E-03 u

ZN-65 L.T. 3. E-03 L.T. 1. E-02 L.T. 4. E-03 L.T. 3. E-03 ZR-95 6.54+-1.64E-03 3.73+-0.37E-02 L.T. 2. E-03 L.T. 2. E-03 RU-103 9.37+-1.91E-03 L.T. 4. E-03 L.T. 2. E-03 L.T. 2. E-03 RU-106 ' L.T. 1. E-02 1.77+-0.87E-02 L.T. 1. E-02 L.T. 1. E-02 I-131 3.91+-2.20E-02 L.T. 1. E 00 L.T. 2. E-02 L.T. 3. E-02 CS-134 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03 CS-137 1.93+-0.65E-03 3.63+-0.90E-03 L.T. 1. E-03 L.T. 1. E-03 BA-140 L.T. 2. E-02 L.T. 1. E-01 L.T. 1. E-02 L.T. 1. E-02 CE-141 1.18+-0.17E-02 L.T. 6. E-03 L.T. 3. E-03 L.T. 4. E-03 CE-144 2.36+-0.386-02 2.48+-0.41E-02 L.T. 7. E-03 L.T. 9. E-03 RA-226 L.T. 1. E-02 L.T. 1. E-02 L.T. 1. E-02 L.T. 2. E-02 Til- 2 2 8 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03

NORT!! ANNA POWER STATION TTELEDYNE ISOTOPES A. AIR PARTICULATE G C!!ARCOAL FILTERS STATION NUMDER 07 MID COUNT AP FILTER MID COUNT Cl!ARCOAL FILTEP COLLECTION DATE TIME GROSS BETA TIME I-131 STAR 1 STOP DATE (pCi/Cu.M) DATE (pCi/Cu.M) DATE DATE VOLUME UNITS 10/03/78 10/10/78 1.38E 02 CU. M. 10/20 3.0 +-0.9 E-02 10/17 L.T. 6. E-03 10/10 10/17 1.39E 02 CU. M. 10/27 4.7 +-0.7 E-02 10/26 L.T. 7. E-03 10/17 10/24 1.40E 02 CU. M. 11/01 6.5 +-0.8 E-02 10/31 L.T. 7. E-03 10/24 10/31 1.41E 02 CU. M. 11/10 4.3 +-0.7 E-02 11/09 L.T. 1. E-02 10/31 11/07 1.38E 02 CU. M. 11/15 7.7 +-0.8 E-02 11/14 L.T. 8. E-03 11/07 11/14 1.43E 02 CU. M. 11/21 7.0 +-0.8 E-02 11/21 L.T. 1. E-02 11/14 11/21 1.37E 02 CU. M. 11/30 4.8 +-0.8 E-02 11/28 L.T. 9. E-03 11/21 11/28 1.39E 02 CU. M. 12/08 3.8 +-0.7 E-02 12/05 L.T. 7. E-03 11/28 12/05 1.41E 02 CU. M. 12/14 3.7 +-0.8 E-02 12/13 L.T. 1. E-02 12/05 12/12 1.41E 02 CU. M. 12/26 4.2 +-0.7 E-02 12/18 L.T. 9. E-02 12/12 12/19 1.44E 02 CU. M. 12/30 4.2 + 0.7 E-02 12/27 L.T. 1. E-02 12/19 12/26 1.36E 02 CU. M. 01/04 5.2 +-0.7 E-02 01/04 L.T. 8. E-03 12/26 01/02 1.41E 02 CU. M. 01/12 4.0 +-0.9 E-02 01/11 L.T. 7. E-03 o O- O $

    -                                                 A                                            -

TTELEDYNE ISOTOPES NORTH ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pCi/Cu. M.) STATION NUMBER 07 DATE COLLECTED: FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER GAMMA SPECTRUM ANALYSIS: BE-7 6.44+-1.31E-02 1.24+-0.25E-01 4.71+-1.22E-02 6.61+-1.59E-02 K-40 L.T. 2. E-02 L.T. 2. E-02 L.T. 2. E-02 L.T. 3. E-02 MN-54 L.T. 1. E-03 L.T. 1. E-03 L.T. 9. E-04 L.T. 1. E-03 CO-SS L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 FE-59 L.T. 4. E-03 L.T. S. E-03 L.T. 3. E-03 L.T. 4 E-03 CO-60 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E 3 L.T. 1. E-03 e ZN-65 L.T. 3. E-03 L.T. 3. E-03 L.T. 3. E-03 L.T. 3. E-03 w ZR-95 6.02+-1.33E-03 5.86+-2.23E-03 L.T. 1 E-03 L.T. 1 E-03 RU-103 1.89+-0.21E-02 L.T. 5. E-03 L.T. 1. E-03 L.T. 2 E-03 RU-106 L.T. 1. E-02 1.74+.0.95E 02 L.T. 8. E-03 L.T. 1. E-02 1-131 3.50+-2.16E-02 L.T. 1. E 00 L.T. 2. E-02 L.T. 3 E-02 CS-134 L.T. 1. E-03 L.T. 1. E.03 L.T. 1. E-03 L.T. 1. E-03 CS-137 2.42+-0.60E-03 3.07+-0.75E-03 L.T. 1. E-03 L.T. 1. E-03 BA-140 3.67+-1.26E-02 L.T. 1. E-01 L.T. 9. E-03 L.T. 1. E-02 CE-141 1.14+-0.18E-02 L.T. 6. E-03 L.T. 2. E 03 L.T. 3. E-03 CE-144 2.13+-0.34E-02 3.32+-0.50E-02 L.T. 5. E-03 L.T. 7. E-03 RA-226 L.T. 9. E-03 L.T. 1. E-02 L.T. 1 E-02 L.T. 2. E-02 TH-228 L.T. 1. E-03 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03

NOR11I ANNA POWER STATION TTELEDYNE ISOTOPES A. AIR PARTICULATE G CllARCOAL FILTERS STATION NUMBER 21 AP FILTER MID COUNT CilARCOAL FILTER MID CO'JNT I-131 CGLLECTION DATE TIM 5 CROSS BETA TIME START STOP (pCi/Cu.M) DATE (pCi/Cu.M) UNITS DATE DATL DATE VOLtMC 1.4 +-0.6 E-C2 10/17 L.T. 9. E-03 10/10/78 1.34E 02 CU. M. 10/20 10/03/78 E-03 4.7 +-0.7 E-02 10/26 L.T. 6. 10/17 1.35E 02 CU. M. 10/27 10/10 3.7 +-0.7 E-02 10/31 L.T. 9. E-53 1.28E 02 CU. M. 11/01 10/17 10/24 2.1 +-0.6 E-02 11/09 L.T. 9. E-03 1.34E 02 CU. M. 11/10 10/24 10/31 6.3 +-0.8 E-02 11/14 L.T. 8. E-03 1.36E 02 CU. M. 11/15 10/31 11/07 5.8 +-0.8 E-02 11/21 L.T. 9. E-03 1.32E 02 CU. M. 11/21 y 11/07 11/14 3.5 +-0.7 E-02 11/28 L.T. 6. E-03 1.36E 02 CU. M. 11/30 11/14 11/21 3.9 +-0.7 E-02 12/05 L.T. 1. E-02 1.35E 02 CU. M. 12/08 11/21 11/28 4.6 +-0.8 E-02 12/13 L.T. 1. E-02 1.36E 02 CU. M. 12/14 11/28 12/05 4.7 +-0.8 E-02 12/18 L.T. 1. E-02 1.36E 02 CU. M. 12/26 12/05 12/12 3.9 +-0.7 E-02 12/29 L.T. 1. E-02 1.39E 02 CU. M. 12/30 12/12 12/19 5.8 +-0.8 E-02 01/04 L.T. 1. E-02 1.32E 02 CU. M. 01/04 12/19 12/26 4.5 +-0.9 E-02 01/11 L.T. 1. E-02 1.36E 02 CU. M. 01/12 12/26 01/02 n n -

TTELEDYNE ISOTOPES N0kTil ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pCi/Cu. M.) STATION NUMBER 21 SECOND QUARTER T111RD QUARTER FOURTH QUARTER DATE COLLECTED: FIRST QUARTER GAMMA SPECTRUM ANALYSIS: 7.39+-2.83E-02 3.92+-0.87E-02 6.28+-2.07E-02 BE-7 6.24+-1.08E-02 E-02 L.T. 2. E-02 L.T. 4 E-02 K-40 L.T. 2. E-02 L.T. 4. E-03 L.T. 8. E-04 L.T. 2. E-02 MN-54 L.T. 1. E-03 L.T. 5. L.T. 1. E-02 L.T. 1. E-03 L.T. 3. E-03 CO-58 L.T. 1. E-03

3. E-02 L.T. 3. E-03 L.T. 7. E-03 FE-59 L.T. 4. E-03 L.T.

L.T. 6. E-03 L.T. 1. E-03 L.T. 2. E-03 CO-60 L.T. 1. E-03 ? L.T. 1. E-02 L.T. 2. E-03 L.T. 4. E-03 ZN-65 L.T. 3. E-03 O

1. E-02 L.T. 1. E-03 L.T. 3. E-03 ZR-95 5.78+-1.33E-03 L.T.

E-03 L.T. 1. E-03 L.T. 4 E-03 RU-103 1.69+-0.19E-02 L.T. 6. E-02 L.T. 2. E-02 L.T. 7. E-03 L.T. 2. E-02 RU-106 L.T. 1. L.T. 2. E 00 L.T. 2. E-02 L.T. 5. E-02 1-131 L.T. 3. E-02

1. E-03 L.T. 2. E-03 L.T. 7. E-04 L.T. 2. E-03 CS-134 L.T.

2.69+-1.06E-03 1.27+-0.48E-03 L.T. 2. E-03 CS-137 1.93+-0.55E-03 E-01 L.T. 9. L-03 L.T. 2. E-02 BA-140 2.15+-0.98E-02 L.T. 2 E-03 L.T. E-03 L.T. 6 E-03 CE-141 1.07+-0.15E-02 L.T. 9. 1. 2.45+-0.76E-02 L.T. 3. E-03 L.T. 1. E-02 CE-144 1.94+-0.31E-02 L.T. 9. E-03 L.T. 2. E-02 L.T. 8. E-03 L.T. 3. E-02 RA-226

1. E-03 L.T. E-04 L.T. 3. E-03 T!!- 2 2 8 L.T. 1. E-03 L.T. 9.

NORIll ANNA POWER STATION TTELEDYNE ISOTOPES A. AIR PARTICULATE 5 O!ARCOAL FILTERS STATION NUMBER 22 AP FILTER MID COUhT OlARCOAL FILTER MID COUNT COLLECTION DATE TD!E GROSS BETA TD!E I-131 START STOP (pCi/Cu.M) VOLUMP UNITS DATE (pCi/Cu.M) DATE DATE DATE 1.4 +-0.8 E-02 10/17 L.T. 8. E-03 10/03/78 10/10/78 1.34E 02 CU. M. 10/20 5.1 +-0.7 E-02 10/26 L.T. 7. E-03 10/10 10/17 1.36E 02 CU. M. , 10/27 5.2 +-0.7 E-02 10/31 not analyzed 10/24 1.36E 02 CU. M. 11/01 10/17 6.3 +-0.8 E-02 11/09 L.T. 1. E-02 10/31 1.37E 02 CU. M. 11/10 10/24 7.0 +-0.8 E-02 11/15 L.T. 1. E-02 11/07 1.34E 02 CU. M. 11/15 10/31 5.3 +-0.8 E-02 11/21 L.T. 2. E-02 11/07 11/14 1.35E 02 CU. M. 11/21 6.9 +-0.9 E-02 11/29 L.T. 6. E-03 11/21 1.33E 02 CU. M. 11/30 11/14 5.1 +-0.8 E-02 12/05 L.T. 1. E-02 11/28 1.35E 02 CU. M. 12/08 11/21 4.1 +-0.8 E-02 12/13 L.T. 1. E-02 12/05 1.36E 02 CU. M. 12/14 11/28 3.8 +-0.7 E-02 12/18 L.T. 1. E-02 12/12 1.36E 02 CU. M. 12/26 12/05 6.3 +-0.8 E-22 12/29 L.T. 1. E-02 12/19 1.39E 02 CU. M. 12/30 12/12 5.9 +-0.8 E-02 Of704 L.T. 1. E-02 1.33E 02 CU, M. 01/04 12/19 12/26 5.1 +-0.9 E-02 01/12 L.T. 9. E-03 1.36E 02 CU. M. 01/12 12/26 01/02 n n ,

m o n TTELEDYNE ISOTOPES NORTH ANNA POWER STATION QUARTERLY COMPOSITE OF AIR PARTICULATES (pCi/Cu. M.) STATION NUMBER 22 DATE COLLECTED: FIRST QUARTER SECOND QUARTER T!!!RD QUARTER TOURTH QUARTER GAMMA SPECTRUM ANALYSIS: BE-7 4.62+-1.33E-02 1.47+-0.41E-01 4.76+-0.96E-02 5.25+-1.20E-02 K-40 L.T. 3. E-02 L.T. 5. E-02 L.T. 3. E-02 L.T. 3. E-02 MN-54 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 1. E-03 CO-58 L.T. 1. E-03 L.T. 4. E-03 L.T. 1. E-03 L.T. 2. E-03 FE-59 L.T. 3. E-03 L.T. 1. E-02 L.T. 4. E-03 L.T. 4. E-03 CO-60 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 ? ZN-65 L.T. 3. E-03 L.T. 6 E-03 L.T. 3. E-03 L.T. 4 E-03 G 6.44+-3.80E-03 L.T. 1. E-03 L.T. 2. E-03 ZR-95 6.72+-1.40E-03 RU-103 1.63+-0.21E-02 L.T. 1. E-02 L.T. 2. E-03 L.T. 2. E-03 RU-106 1.59+-0.79E-02 L.T. 2. E-02 L.T. 8. E-03 L.T. 1. E-02 I-131 3.12+-2.37E-02 L.T. 4. E 00 L.T. 2. E-02 L.T. 2. E-02 CS-134 L.T. 1. E-03 L.T. 2. E-03 L.T. 9. E-04 L.T. 1. E-03 05-137 1.98+-0.86E-03 2.86+-1.52E-03 1.30+-0.59E-03 L.T. 1 E-03 BA-140 3.36+-1.07E-02 L.T. 2. E-01 L.T. 1. E-02 L.T. 1. E-02 CE-141 1.12+-0.22E-02 L.T. 2 E-02 L.T. 2. E-03 L.T. 3. E-03 CE-144 1.47+-0.41E-02 3.64+-1.06E-02 L.T. 4 E-03 L.T. 6. E-03 RA-226 L.T. 3. E-02 L.T. 3. E-02 L.T. 8. E-03 L.T. 1. E-02 Til- 2 2 8 L.T. 1. E-03 L.T. 3. E-03 L.T. 8. E L.T. 1. E-03

TTELEDYNE ISOTOPES NORT11 ANNA POWER STATION A. AIR PARTICULATE 6 C11ARCOAL FILTERS STATION NUMBER 23 MID COUNT AP FILTER HID COUNT C!lARCOAL FILTER COLLECTION DATE CROSS BETA TD'E I-131 TIME START STOP DATE (pCi/Cu.M) DATE (pCi/Cu.M) DATE DATE VOLUME UNITS 3.0 +-0.9 E-02 10/17 L.T. 6. E-03 10/03/78 10/10/78 1.35E 02 CU. M. 10/20 5.1 +-0.7 E-02 10/26 L.T. 7. E-03 10/10 10/17 1.36E 02 CU. M. - 10/27 4.1 +-0.6 E-02 11/01 L.T. 1. E-02 10/17 10/24 1.40E 02 CU. M. 11/01 4.4 >-0.7 E-02 11/09 L.T. 7. E-03 10/24 10/31 1.38E 02 CU. M. 11/10 8.5 +-0.9 E-02 11/15 L.T. 1. E-02 10/31 11/07 1.37E 02 CU. M. 11/15 11/21 5.6 +-0.8 E-02 11/21 L.T. 1. E-02 11/07 11/14 1.38E 02 CU. M. 5.4 +-0.8 E-02 11/30 L.T. 1. E-02 11/14 11/21 1.35E 02 CU. M. 11/30 4.5 +-0.8 E-02 12/05 L.T. 7. E-03 11/28 1.34E 02 CU. M. 12/08 11/21 4.4 +-0.8 E-02 12/13 L.T. 6. E.03 12/05 1.34E 02 CU. M. 12/14 11/28 4.4 +-0.7 E-02 12/18 L.T. 8. E-03 12/12 1.35E 02 CU. M. 12/26 12/05 5.1 +-0.7 E-02 12/29 L.T. 1. E-02 12/19 1.38E 02 CU. M. 12/30 12/12 4.1 +-0.7 E-02 01/04 L.T. 1. E-02 12/26 1.31E 02 CU. M. 01/04 12/19 4.6 +-0.9 E-02 01/12 L.T. 7. E-03 01/02 1.36E 02 CU. M. 01/12 12/26 Ms A .* .

         ^                                               ^                                              -
   'AFTELEDYNE IS700 PES NORTH ANNA POWER STATION QUARTERLY COMPOSITE OF SIR PARTICULATES (pC1/Cu.M.)

STATION NUMBER 23 DATE COLLECTED: FIRST QUARTSR SECOND QUARTER T!!!RD QUARTER FOURTH QUARTER GAMMA SPECTRUM ANALYSIS: BE-7 b.46+-2-03E-02 1.09+-0.23E-01 7.38+-1.82E-02 6.03+-1.70E-02 K-40 L.T. 4. E-02 L.T. 2. E-02 L.T. 4. E-02 L.T. 4. E-02 MN-54 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 CO-58 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 L.T. 2. E-03 FE-59 L.T. 5. E-03 L.T. 8. E-03 L.T. 6. E-03 L.T. 5. E-03 CO-60 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-03 [ ~ ZN-65 L.T. 3. E-03 L.T. 3. E-03 3.12+-1.71E-03 L.T. L.T. 4 2. E-03 E-03 L.T. L.T. 3. 2. E-03 E-03 2R-95 1.04+-0.36E-02 RU-103 9.01+-2.70E-03 L.T. S. E-03 L.T. 3. E-03 L.T. 3. E-03 RU-106 2.29+-1.24E-02 1.27+-0.63E-02 L.T. 2. E-02 L.T. 1. E-02 I-131 L.T. 5. E-02 L.T. 1. E 00 L.T. 5. E-02 L.T. 4. E-02 CS-134 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03 CS-137 2.74+-1.35E-03 2.62+-0.64E-03 L.T. 2. E-03 L.T. 1. E-03 BA-140 L.T. 2. E-02 L.T. 2. E-01 L.T. 2. E-02 L.T. 6. E-03 CE-141 1.13+-0.38E-02 L.T. 5. E-03 L.T. 5. E-03 L.T. 5. E-03 CE-144 2.92+-0.82E-02 2.36+-0.37E-02 L.T. 1 E-02 L.T. 1. E-02 RA-226 L.T. 2 E-02 L.T. 9. E-03 L.T. 3. E-03 L.T. 2. E-02 s Til-228 L.T. 2. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 2. E-03

TTELEDYNE ISOTOPES NOR111 ANNA POWER STATION A. AIR PARTICUIATE G O!ARCOAL FILTERS STATION NUMBE. 24 C01. LECT 10N DATE MID COUNT AP FILTER MID CO'JNT C11ARCOAL FILTER START STOP TIFI GROSS BETA TIME 1-131 DATE DATE VOLUME UNITS DATE (pCi/Cu.M) DATE (pCi/Cu.M) 10/03/78 10/10/78 1.35E 02 CU. M. 10/20 4.4 +-0.9 E-02 10/17 L.T. 6. E-03 10/10 10/17 1.34E 02 CU. M. 10/27 6.6 +-0.8 E-02 10/27 L.T. 8. E-03 10/17 10/24 1.34E 02 CU. M. 11/01 8.0 +-0.9 E-02 11/01 L.T. 1. E-02 10/24 10/31 1.34E 02 CU. M. 11/10 6.4 +-0.8 E-02 11/10 L.T. 9. E-03 10/31 11/07 1.35E 02 CU. M. 11/15 1.2 +-0.1 E-02 11/15 L.T. S. E-03 11/07 11/14 1.34E 02 CU. M. 11/21 9,1 +-0.9 E-02 11/21 L.T. 1. E-02 11/14 11/21 1.35E 02 CU. M. 11/30 6.1 +-0.8 E-02 11/30 L.T. 1. E-02 11/21 11/28 1.34E 02 CU. M. 12/08 8.3 +-0.9 E-02 12/05 L.T. 7 E-03 11/28 12/05 1.34E 02 CU. M. 12/14 3.8 +-0.8 E-02 12/13 L.T. 9. E-03 12/05 12/12 1.34E 02 CU. M. 12/26 3.8 +-0.7 E-02 12/18 L.T. 9. E-03 12/12 12/19 1.34E 02 CU. M. 12/30 5.5 +-0.8 E-02 12/29 L.T. 1. E-32 12/19 12/26 1.34E 02 CU. M. 01/04 9.4 +-0.9 E-02 01/04 L.T. 9. E-03 12/26 01/04 1.73 E 02 CU. M. 01/12 4.3 +.0.7 E-02 01/12 L.T. 6. E-03 [% ". .

n n TTELEDYNE ISOIDPES NORTH ANNA POWER STATION

  • QUARTERLY COMPOSITE OF AIR PARTICULATES (pCi/Cu. M.)

STATION NUMBER 24 DATE COLLECTED: FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER GAMMA SPECTRUM ANALYSIS: BE-7 6.85+-1.22E-02 1.08+-0.26E-01 6.22+,1.24E-02 6.23+-1.14E-02 K-40 L.T. 2. E-02 L.T. 3. E-02 L.T. 3. E-02 L.T. 3. E-02 MN-54 L.T. 1. E-03 L.T. 1. E-03 L.T. 1 E-03 L.T. 1. E-03 CO-58 L.T. 1. E-03 L.T. 2. E-03 L,T. 2. F 03 L.T. 1. E-01 FE-59 L.T. 4. E-03 L.T 8. E-23 L.T. 4 E-03 L.T. 4 E-01 CO-60 L.T. 1. E-03 L.T. 1. E-03 L.T. 2. E-03 L.T. 1. E-01 ZN-65 L.T. 3. E-03 L.T. 4. E-03 L.T. 3. E-03 L.T. 3. E-01 2R-95 5.47+-1.32E-03 L.T. 3. E-03 L.T. 2. E-03 L.T. 1. E-01 e RU-103 L.T. 2. E-03 L.T. 5. E-03 L? 2 E-03 L.T. 2. E-01 RU-106 L.T. 1. E-02 L.T. 1. E-02 L.T. 2. E-03 L.T. 1. E-02 I-131 L.T. 4. E-02 L.T. 2. E 00 L.T. 3. E,02 L.T. 2. E-02 CS-134 L.T. 1. E-03 L.T. 1. E-03 L.T. 1 E.03 L.T. 1. E-03 CS-137 2.27+-0.54E-03 3.16+-1.20E-03 1.66+,0.83E,03 L.T. 1. E-03 BA-140 L.T. 2. E-02 L.T. 1. E-01 L.T. 1. E-02 L.T. 1. E-02 CE-141 L.T. 2. E-03 L.T. 9. E-03 L.T. 3. E-03 L.T. 2. E-03 CE-144 2.07+-0.29E-02 2.67+-0.80E-02 9.39+-5.25E-03 L.T. 5. E-03 RA-226 L.T. 8. E-03 L.T. 2. E-02 L.T. 1, E-02 L.T. 1. E-02 Tli- 2 2 8 L.T. 9. E-04 L.T. 2. E-03 L.T. 1. E-03 L.T. 1. E-03

  ';PTELEDYNEISOTOPES                                  NORT!! ANN A POWER STATION WATER-PRECIPITATION STATION NUMPER 1 NOVEMBER                     DECEMBER DATE COLL:                OCTOBER RADIOCllEMICAL ANA!.YSIS:                                                                                '

TOTAL RAINFALL 0.47 inches 1.5 +-0. 7 E 00 pCi/ liter 1.4 +-0.8 E 00 pCi/11ter GR-B 2.5 +-0.2 E 01 pCi/litor 9.1 +-5.2 E-02 nCi/sq.m 3.0 +-0.2 E-01 nC1/sq.m. 8.3 +-3.9 E-02 nC1/sq.m. GR-B ? 's O -

       -                                          m                   ~

T TELEDYNEISOTOPES NORT!! ANNA POWER STATION WATER-PRECIPITATION STATION NUMBER 01 COLLECTION DATE: 07/01-12/30 CAMMA SPECTRUM ANALYSIS: BE-7 L.T. 7. E 01 K-40 L.T. 2. E 02 MN-54 L.T. 6. E 00 CO-58 L.T. 7. E 00 TE-59 L.T. 1. E 01 CO-60 L.T. 7. E 00 ? y ZN-65 L.T. 1. E 01 ZR-95 L.T. 8. E 00 RU-103 L.T. 8. E 00 RU-106 L.T. 6 E 01 I-131 L.T. 2. E 01 CS-134 L.T. 7. E 00 CS-137 L.T. 7. E 00 BA-140 L.T. 2. E 01 CE-141 L.T. 2. E 01 CE-144 L.T. 7. E 01 RA-226 L.T. 2. E 02 Til-228 L.T. 1. E 01 TRITIUM ANALYSIS:

 !!- 3                     1.0 +-0.9 E 02

TTELEDYNE ISOTOPES NORTil ANNA POWER STATION DIRECT EXPOSURE TLD NET EXPOSURE TillRD QUARTER FOURTH QUARTER 9.2 MONTils FIRST QUARTER SECOND QUARTER 12/27/77-03/28/78 03/28/78-06/27/78 06/27/78 09/26/78 09/26/78-12/26/76 09/20/77-06/27/78 or ar/ day mR mR/ day STATION mR mp/d ay mR mR/ day tr nr/ day 0.33 20.9 0.23 21.1 0.23 78.4 0.28 01 18.7 0.205 29.8 12.4 0.14 1/. 8 0.16 58.4 0.21 02 13.8 0.152 24.8 0.27 14.8 0.16 15.5 0.17 61.3 0.22 03 12.9 0.142 26.4 0.29 14.1 0.15 13.3 0.15 60.7 0.22 04 14.3 0.157 26.3 0.29 28.7 17.1 0.19 27.7 0.30 61.6 0.22 05 13.9 0.153 0.32 22.4 0.25 23.6 0.26 89.5 0.32 06 19.9 0.219 33.4 0.37 0.31 33.9 0.15 16.3 0.18 62.7 0.22 07 15.3 0.168 28.5 0.26 17.8 0.20 15.9 0.17 62.7 0.22 21 14.8 0.164 23.4 35.3 0.39 19.1 0.21 22.3 0.25 80.6 0.29 22 19.5 0.214 0.28 18.2 0.20 24.0 0.26 86.4 0.31 23 20.3 0.223 25.4 21.5 0.24 14.9 0.16 13.7 0.15 54.1 0.19

      *24        12.3        0.135 27.6            0.J0         16.9      0.19                18.9     0.21         68.8        0.25 MEAN         16          0.18 0.24-0.39     -        0.14-0.25             -      0.15-0.30     -          0.19-0.32 (RANGE)      12-20       0.14-0.22       -

11/11 11/11 - 11/11 - 11/11 DETECTION / 11/11 11/11 - TOTAL The radiation dose is calculated as net mR/ day and is the average daily exposure of the dosimeters at the stations in North Anna. The dosimeters were annealed at the North Anne Power Station of the Virginia Electric and Power Company prior to exposure in the field thus cancelling an in-transit dose. After exposure and collection of the field dosimeters and prior to shipment to Teledyne Isotopes, the control dosimeters only were annealed and shipped with the field dosimeters to T1 providing a measure of the return in-transit dose. The net mR/ day ir the gross mR/ day of the Geld dosimeters minus the return in-transit dose of the control dosimeters.

    ' Control location.

n p - e

         ~                                        p.                                        ~

TTELEDYNE ISOTOPES NORTil ANNA POWER STATION , WATER-SURFACE (pCi/ liter) STATION NUMBER 08 DISCl!ARGE COOLING WATER . NOVEMBER DECEMBER DATE COLLECTED: OCTOBER RADIOCitEMICAL ANALYSIS: L.T. 4. E-01 L.T. 5. E-01 I-131 L.T. 2. E-01 GAMMA SPECTRUM ANALYSIS: L.T. 6. E 01 L.T. 8. E 01 BE-7 L.T. 9. E 01 L.T. 1. E 02 L.T. 2. E 02 K-40 L.T. 2. E 02 L.T. 6. E 00 L.T. 7. E 00 MN-54 L.T. 7. E 00 L.T. 7. E 00 L.T. 8. E 00 CO-SS L.T. 9. E 00 L.T. 1. E 01 L.T. 2. E 01 FE-59 L.T. 2. E 01 L.T. 6. E 00 L.T. 8. E 00 CO-60 L.T. 7. E 00 L.T. 1. E 00 L.T. 2. E 01 ZN-65 L.T. 2. E 01 L.T. 7. E 00 L.T. 9. E 00 2R-95 L.T. 9. E 00 L.T. 8. E 00 L.T. 1. E 01 RU-103 L.T. 1. E 01 L.T. 6. E 01 L.T. 7. E 01 RU-106 L.T. 7. E 01 L.T. 3. E 01 L.T. 3. E 01 1-131 L.T. 5. E 01 L.T. 7. E 00 L.T. 8. E 00 CS-134 L.T. 8. E 00 6 E 00 L.T. 8. E 00

8. E 00 L.T.

CS-137 L.T. L.T. 2. E 01 L.T. 2. E 01 BA-140 L.T. 2. E 01 L.T. 3. E 01

2. E 01 L.T. 2. E 01 ,

CE-141 L.T. L.T. 9 E 01 L.T. 6. E 01 L.T. 7. E 01 CE-144 L.T. 2. E 02 L.T. 2 E 02 RA-226 L.T. 2. E 02 L T. 1. E 01 L.T. 2. E 01 Tit - 2 2 8 L.T. 1. E 01

TTELEDYNE ISOTOPES NORTl! ANNA POWER STATION WATER-SURFACE (pci/ liter) STATION NUMBER 09 RESERVOIR WATER NOVEMBER DECEMBER DATE COLLECTED: OCTOBER RADI0 CHEMICAL ANALYSIS: L.T. 5. E-01 L.T. S. E-01 I-131 L.T. 3. E-01 GAMMA SPECTRUM ANALYSIS: . L.'. 8. E 01 L.T. 8. E 01 BE-7 L.T. 9. E 01 L.T. 2. E 02 L.T. 2. E 02 K-40 L.T. 2. E 02 L.T. 7. E 00 L.T. 7. E 00 e MN-54 L.T. 7. E 00 L.T. 7. E 00 L.T. 8. E 00 CO-59 L.T. 9. E 00 L.T. 2. E 01 L.T. 2. E 01 FE-59 L.T. 2. E 01 L.T. 8. E 00 L.T. 8. E 00 CO-60 L.T. 8. E 00 E 01 L.T. 2. E 01 L.T. 2. E 01 2N-65 L . T. . 2. L.T. 8. E 00 L.T. 7. E 00 ZR-95 L.T. 1. E 01 L.T. 9. E 00 L.T. 1. E 01 RU-103 L.T. 1. E 01 L.T. 7. E 01 L.T. 8. E 01 RU-106 L.T. 7. E 01 L.T. 3. E 01 L.T. 3. E 01 I-131 L.T. 7. E 01 L.T. 8. E 00 L.T. B. E 00 CS-134 L.T. 8. E 00 L.T. 8. E 00 L.T. 8. E 00 CS-137 L.T. 9. E 00 L.T. 2. E 01 L.T. 2. E 01 BA-140 L.T. 3. E 01 L.T. 2. E 01 L.T. 2. E 01 CE-141 L.T. 2. E 01 L.T. 6 E 01 L.T. 7. E 01 CE-144 L.T. 7. E 01 L.T. 1. E 02 L.T. 2. E 02 RA-226 L.T. 2. E 02 L.T. 1. E 01 L.T. 2. E 01 T!! - 2 2 "' L.T. 1. E 01 ,, - .

     -                     A                       -

NORTH ANNA POWER STATION WATER / SURFACE (pCi/ liter) 4th QUARTER COMPOSITE STATION !!-3 OS 7.6 +-1.0 E 02 09 6.0 +-1.0 E 02 7 0

TTELEDYNE ISOTOPES NORTil ANNA POWER STATION WATER-RIVER (pCi/ liter) STATION NUMBER 11 DATE COLLECTED: 12/20 GAMMA SPECTRUM ANALYSIS: BE-7 L.T. 6. E 01 K-40 L.T. 2. E 02 MN-54 L.T. 6. E 00 ? CO-58 L.T. 6. E 00 a L.T. 1. E 01 FE-59 C0-60 L.T. 6. E 00 ZN-65 L.T. 1. E 01 2R-95 L.T. 7. E 00 RU-103 L.T. 8. E 00 RU-106 L.T. 6. E 01 L.T. 2. E 01 1-131 CS-134 L.T. 7. E 00 CS-137 L.T. 7. E 00 BA-140 L.T. 1. E 01 L.T. 2. E 01 CE-141 CE-144 L.T. 7. E 01 RA-226 L.T. 2. E 02 Til-228 L.T. 1. E 01 TRIT,LJIM AN ALYSIS : ^ - , 11 - 3 8.9 +-1.0 E 02

n n ~ i TTELEDYNE ISOTOPES , NORTIl ANNA POWER STATION WATER-GROUND STATION NUMBER 01 DATE COLL: 12/28 GAMMA SPECTRUM ANALYSIS: BE-7 L.T. 8. E 01 X-40 L.T. 2. E 02 MN-54 L.T. 9. E 00 CO-58 L.T. 8. E 00 FE-59 L.T. 2. E 01 CO-60 L.T. 9. E 00 o 2N-65 L.T. 2. E 01 u ~ ZR-95 L.T. 1. E 01 RU-103 L.T. 1. E 01 RU-106 L.T. 8. E 01 1-131 L.T. 2. E 01 CS-134 L.T. 9. E 00 CS-137 L.T. 8. E 00 . BA-140 L.T. 1. E 01 CE-141 L.T. 2. E 01 CE-144 L.T. 9. E 01 RA-226 L.T. 2. E 02 Tit-228 6.32+-0.73E 01 TRITIUM ANALYSIS: 4.T. 1.0 E 02

   !!- 3

TTELEDYNE ISOTOPES NORTH ANNA POWER STATION MILK (pCi/ liter) STATION NUMBER 12 iDECEMBER OCTOBER NOVEMBER DATE COLLECTED: RA010 CHEMICAL ANALYSIS: L.T. 4. E-01 L.T. 4. E-01 I-131 L.T. 3. E-01 GAMMA SPECTRUM ANALYSIS: L.T. 7. E 01 L.T. 8. E 01 BE-7 L.T. 7. E 01 1.29+-0.23E 03 1.05+-0.17E 03 K-40 9.84+-1.32E 02 L.T. 8. E 00 L.T. 8. E 00 MN-54 L.T. 7. E 00 L.T. S. E 00 L.T. 8. E 00 CO-58 L.T. 7. E 00 E 01 L.T. 2. E 01 L.T. 2. o FE-59 L.T. 2. E 01 L.T. 9. E 00 L.T. 9. E 00 U CO-60 L.T. 8. E 00 L.T. 2. E 01 L.T. 2. E 01 IN-65 L.T. 2. E 01 L.T. 9. E 00 L.T. 8. E 00 2R-95 L.T. 7. E 00 L.T. 8. E 00 L.T. 1. E 01 RU-103 L.T. 8. 5 00 L.T. 7. E 01 E 01 L.T. 8. E 01 RU-106 L.T. 7. L.T. 2. E 01 E 01 L.T. 2. E 01 I-131 L.T. 1. L.T. 9 E 00 E 00 L.T. 9. E 00 CS-134 L.T. 8. L.T. 9. E 00 L.T. 1. E 01 CS-137 L.T. 7. E 00 L.T. 1. E 01 L.T. 1. E 01 BA-140 L.T. 1. E 01 L.T. 2. E 01 E 01 L.T. 2. E 01 CE-141 L.T. 2. L.T. 8. E 01 E 01 L.T. 7. E 01 CE-144 L.T. 6. L.T. 2. E 02 , L.T. 2. E 02 RA-226 L.T. 1. E 02 L.T. 1. E 01 E 01 L.T. 1. E 01 T!!-22A L.T. 1. ^ _. s

         -                                        ~                                     _

6 'TFTIIIII(NE ISCRTHMES NORTil ANNA POWER STATION MILK (pCi/ liter) STATION NUMBER 13 OCTOBER NOVEMBER DECEMBER DATE COLLECTED: RAD 10CifEMICAL ANALYSIS:

2. E-01 L.T. 5. E-01 L.T. 5. E-01 1-131 L.T.

GAMMA SPECTRUM ANALYSIS: L.T. 6. E 01 L.T. 8. E 01 BE-7 L.T. 6. E 01 1.19+-0.14E 03 K-40 1.05+-0.14E 03 1.22+-0.15E 03

6. E 00 L.T. 7. E 00 MN-54 L.T. 7. E6> L.T.

L.T. E 00 L.T. 8. EO CO-58 L.T. 7. E 00 6.

2. E 01 L.T. 2. E 01 L.T. 2. E 01 FE-59 L.T.

L.T. 7. E 00 L.T. 9. E OS CO-60 L.T. 8. E 00 E 01 L.T. 2. E 01 ZN-65 L.T. 2. E 01 L.T. 1. E 00 7. E 00 L.T. 9. E 00 ZR-95 L.T. 7. L.T.

7. E 00 L.T. 1 E 01 RU-103 L.T. 8. E 00 L.T.

L.T. 6. E 01 L.T. 8. E 01 RU-106 L.T. 6. E 01

1. E 01 L.T. 2. E 01 I-131 L.T. 1. E 01 L.T.

L.T. 9. E 00 CS-134 L.T. 7. E 00 L.T. 7. E 00 E 00 9.31+-4.98E 00 CS-137 1.22+-0.52E 01 L.T. 8. E 01 L.T. 1. E 01 L.T. 1. E 01 BA-140 L.T. 1. L.T. 2 E 01 L.T. 2. E 01 CE-141 L.T. 1. E 01

7. E 01 L.T. 9. E 01 CE-144 L.T. 6. E 01 L.T.

L.T. 2. E 02 L.T. 2. E 02 RA-226 L.T. 1. E 02

3. E 01 L.T. 2. E 01 T!!- 2 2 8 L.T. 1. E 01 L.T.

TTE1.EDYNE ISOTOPES NORTH ANNA POWER STATION MILK (pCi/ liter) STATION NUMBER 14 NOVEMBER DECEMBER DATE COLLECTED: OCTOBER RAD 10Ct!EMICAL ANALYSIS: E-01 L.T. 4. E-01 L.T. 4. E-01 1-131 L.T. 3. CAMMA SPECTRUM ANALYSIS: E 01 L.T. 7. E 01 BE-7 L.T. 8. E 01 L.T. 7. 1.17+-0.23E 03 1.46+-0.1SE 03 1.16+-0.16E 03 K-40 E 00 L.T. 7. E 00 L.T. 7. E 00 MN-54 L.T. 8. E 00 L.T. 7. E 00 L.T. 8. E 00 CO-58 L.T. 7. L.T. 2. E 01 L.T. 2. E 01 FE-59 L.T. 2. E 01 L.T. 8. E 00 L.T. 9. E 00 y CO-60 L.T. 9. E 00 E 01 L.T. 2. E 01 L.T. 2. E 01 2N-65 L.T. 2. E 00 L.T. 9. E 00 2R-95 L.T. 8. E 00 L.T. 8. E 00 L.T. 9. E 00 L.T. 8. E 00 RU-103 L.T. 9.

8. E 01 L.T. 7. E 01 L.T. 7. E 01 RU-106 L.T.

L.T. 2. E 01 L.T. 2. E 01 L.T. 2. E 01 I-131 L.T. 8. E 00 L.T. 8. E 00 CS-134 L.T. 9. E 00 E 00 L.T. 9. E 00 CS-137 L.T. 1. E 01 L.T. 8. L.T. E 01 L.T. 1. E 01 BA-140 L.T. 1. E 01 1 E 01 L.T. 2. E 01 CE-141 L.T. 2. E 01 L.T. 2. E 01 L.T. 6. E 01 L.T. 8. E 01 CE-144 L.T. 7. E 02 1. E 02 L.T. 2. E 02 RA-226 L.T. 2. L.T. L.T. 2. E 01 L.T. 2. E 01 T!!- 2 2 8 L.T. 1. E 01 n n -.

                                                                            ?

TTELEDYNE ISOTOPES NORTH ANNA POWER STATION MILK (pCi/ liter) FOURTl! QUARTER CCMPDSITE STATION SR-89 SR-90 12 L.T. 3. E 00 2.2 +-0.3 E 00 13 L.T. 2. E 00 1.2 +-0.3 E 00 14 L.T. 3. E 00 3.1 +-0.3 E 00 ? M

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