ML20112K128
| ML20112K128 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1982 |
| From: | Harrell E, Mary Johnson, Stafford A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| References | |
| NUDOCS 8504090349 | |
| Download: ML20112K128 (18) | |
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4 l ANNUAL EINIRONMENTAL OPERATING REPORT i RADIOLOGICAL REPORT q . NORTH ANNA POWER STATION JAN.1,1982 - DEC. 31,1982 . i ? e
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Prdpared by: U3 (dw M.-L. Johnson, @istant Health
; Physics Supervisor ,
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1 Approved by: ,
'A. H. Staffofd, Sup ' or .
Health Physics g s' I f. i- -
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e E. W. Harref, Station' Manager j j North Anna?ower Station - y, f j!i
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DESIGNATED ORIGINAD \ !- 8504090349 821231 Ce-trie..
. By IN" PDR ADOCK 05000338- " ~
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W TELEDYNE-ISOTOPES - TABLE OF CONTENTS
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111E RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PAGE
. LIST OF TABLES 11 LIST OF FIGURES 11 INTRODUCTION' ,1 -
DESCRIPTION OF THE PROGRAM '2 ABSTRACTS OF ANALYTICAL PROCEDURES 11
-ABSTRACTS OF RADI0 ASSAY PROCEDURES
- 14 QUALITY CONTROL OF ANALYSES 18 RADIATION DOSES FROM NATURAL AND ARTIFICIAL SOURCES 19 O '
REFERENCES 20 f
SUMMARY
AND DISCUSSION OF QUARTERLY RESULTS FIRST QUARTER 1982 1A
- SECOND QUARTER 1982 -
IB THIRD QUARTER 1982 1C _1 FO'URTH QUARTER 1982~ ID APPENDICES __ DATA BY. SAMPLE TYPE, STATION AND COLLECTION DATES l FIRST QUARTER 1982 Al SECOND QUARTER 1982 B1 , THIRD QUARTER 1982 C1 FOURTil QUARTER 1982' D1 e
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MTELEDYNE . ISOTOPES ' 9~ ' INTRODUCTION 7
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The North Anna Power ' Station consists of two pressurized water reactors of i 947 megawatts located in Mineral, Virginia. Monitoring of the environment began prior..to operation in January of 1977 and has continued to the present. Unit One began op'eration in April 1978; Unit'Two reached full operation in .
-December 1980.
Outlined;in this document is the description of the radiological environ-
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mental (monitoring. program conducted by Virginia Electric and Power _ Company - for the North ~ Anna Power Station, and a summary of the data generated to
. satisfy; the ' monitoring requirements. ..This program is based on the technical specifications requiring the'collectionLand analysis of various sample media
' to' provide information on the type and quantity of radioactivity in certain indicator organisms or critical pathways. e ' Virginia Electric and Power. Company is responsible for the collection of i the samples required for the program and Teledyne Isotopes is responsible for the analysis of each sample and submission of the reports of analyses. , Quarterly summaries of the data reported for each sample type is appended to this document. These quar.terly data. summaries include a summary of the radioactivities
- reported for each sample type and pathway and a tabulation of the mean,
' range,. and number _of-detections measured among the-total number of samples for each s' ample type and radionuclide. From the data summaries, a radiological
' environmental monitoring report' as specified in Regulatory Guide 4.8 (Ref.1) has been prepared and used as the basis for evaluating the radiation exposur'.. -
re'sulting from the North = Anna Power Station operations. The radiological environmental monitoring program (REMP) specifications are described in Appendix B to the Operating License (Ref. 7) and the required analyses and ' specifications are listed in Table 1. !? Jhe'overa11 objectives .(Ref. 7) of the operational radiological environ- , mental monitoring-program are to' identify changes of radioactivity in.the
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j vicinity of the ~ North- Anna Power Station and to provide information on the
} types and_ quantity of radiation in certain critical pathways and indicator
'l _ organisms as a basis for evaluating radiation. exposures to the population
- . from the NAPS'op'erations.
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TTELEDYNE ' ISOTOPES . DESCRIPTION OF THE OPERATIONAL PROGRAM 9 THE' RADIOLOGICAL ENVIRONMENTAL PROGRAM i The description 'of the operational radiological environmental anal-4 ysis program is presented in this section. Personnel of VEPC0 collect 4 the samples specified in Table 1 and ship them to Teledyne Isotopes for i the analytical phase of the program. Interim data reports are submitted ' by Teledyne Isotopes-as the analyses are completed, normally within 33 days of the 'date of receipt of samples (Ref. 9). Summary reports are is-sued 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 analytical data from the interim data reports, -(2) . summaries of the environmental radiological analysis for each media listing ~ the mean and range of detected radio-nuclides and the ratio of detected radionuclides to total measurements, 4 (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 I contains the' technical- specification requirements for the North Anna Power Station (Ref.7).
' Sampling station identifications and relative positions to the ef-fluent release 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 measure-i ments on the~ following media.
- AIRBORNE PATHWAY
.i ^ Airborne Particulates Particulate filters are collected weekly from air sampling stations 1, 2, 3,'4, 5, 5A, 6, 7, 21, 22, 23, 24 and analyzed for < gross beta activity. Quarterly composites of these' particulate air . . samples are analy; zed for Sr-89, Sr-90 (second quarter only), and gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. Air samp1ing stations are-located on Figures 1 and 2 and listed in
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1 , Table.l. Lapse time recorders are used to calculate actual air volumes. 'The control station is Station 24. Radioiodine Charcoal cartridges are collected from sampling stations,1, 2,
- 3,; 4, 5, SA, - 6, 7, 21, 22, 23, 24 weekly. The cartridges are anal-
'yzed for radioiodine by' distillation..nd beta counting. Charcoal cartridge. sampling locations are shown on Figures 1 and 2. Station s 24 is the control station.
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T TELEDYNE ISOTOPES Groundwater
'~ / Water samples are collected quarterly from the Environmental Laboratory Well 1A and analyzed for tritium and for gamma emitting nuclidestby high resolution Ge(Li) gamma spectrometry. The second quarter sample is also analyzed for Sr-89, Sr-90.
AQUATIC PATHWAY . . Sediment / Silt i i Sed.iment and silt samples are_ collected semiannually from Stations 8, 9, and-11. They are analyzed for gamma emitting nuclide.s by high resolution Ge(Li) gamma spectrometry. The samples are analyzed an-nually for. Sr-89 and Sr-90. Station 9 is the control station. Shoreline Soil A shoreline soil sample is collected semiannually from Station 9
'and analyzed for gamma isotopes by a high resolution Ge(Li) spectrometer. A sample is analyzed annually for Sr-89 and Sr-90.
INGESTION PATHWAY Milk Milk samples are collected monthly from locations 12, 13, 14A, and analyzed for I-131 by chemical separation. Gamma isotopic emitters are analyzed by' high resolution Ge(Li) gamma spectrometry. Quarterly composites of milk samples are analyzed for Sr-89, Sr-90. Milk sampling locations are listed in Table 1 and shown in Figures 1 and 2. Fish Fish are collected annually near the beginning of the season from two locationsLand analyzed for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. Fish sampling sites ate at locations 8 and 9 on Figure 1.,
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Terrestrial Vegetation Samples of green leafy vegetation (cultiv tad or weeds) are
' collectedannually during the harvest from two locat.ons, Stations 21 and 23. These sampics are analyzed for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry.
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Soil s_ j Soil samples are collected from locations near the airborne stations every three years and analyzed for gamma emitting nuclides by high resolution Ge(Li) gamma spectrometry. The stations are 1,'3, 4, 5, 6, 7, 21, 22, 23, and 24. Stations 1, 21, 22, 23, and 24 are also analyzed ~for Sr-89, Sr-90. The control station is Station 24. Precipitation Rain water is collected monthly from Station 1 and analyzed for gross beta activity.- The deposition of matter in nanoCuries per
. square meter is reported from the gross beta activity and the amount of rainfall. A semiannual composite is prepared and analyzed for.
tritium and gamma emitting nuclides. DIRECT RADIATION TLD Environmental direct radiation levels are monitored by thermoluminescent dosimeters (TLD) using a multi-area, phosphor teflon CaSO 4 :Dy dosimeter. Dosimeters are placed at each location and. excharges are made quarterly. TLDs are located at stations 1, 2, 3, 4, 5, 5A, 6, 7, 21, 22, 23, 24 -(See Table 1 and Figures 1 and 2) .
, Station 24 is the control station.
. WATERBORNE' PATHWAY River Water tt A sample of river water is collected quarterly at Station 11,
-t downstream on the North Anna River. It is analyzed for tritium and gamma emitting nuclides at collection. The second quarter sample
'is analyzed for Sr-89, Sr-90.
ii Surface Water n
- l Surface water samples are collected monthly from Station 8 (Discharge) and Station 9_ (Reservoir) and analyzed for iodine-131 and gamma isotopes. A quarterly composite is prepared and analyzed for tritium. The second quarter composite is analyzed for Sr-89, Sr-90 in addition to tritium. The control station is Station.9.
The State of Virginia coll'ects two samples of surface water monthly which are analyzed for gross beta activity and gamma emit-ting nuclides. At least once per quarter the samples are analyzed for tritium. The results can be compared with the results of the j samples collected by the North Anna Power Station. 4
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'TTELEDYNE ISOTOPES O
i VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM FOR 1982
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- Prepared by D TELEDYNE ISOTOPES 50 VAN BUREN AVENUE WESTWOOD, NEW JERSEY 07675
TTELEDYNE , ISOTOPES l l
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. ABSTRACTS OF THE ANALYTICAL PROCEDURES
.1 I
The following are abstracts of the radionuclide separation, puri-fication, and measurement techniques used by Teledyne Isotopes. These tech-
- niques have been~ developed to meet the detection sensitivities (Table 3) and
-associated accuracies required by the nuclear industry in compliance with :
. technical specifications. ,
' Air Particulates
- Gross Beta
- Transfer' filter to a 2-inch diameter planchet and assay in a Beck-l man Sharp Wide 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 4 Iodine-131. - .
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Two procedures are used for the analysis-of charcoal cartridges for iodine-131. METHOD 1. -If the charcoal used is NOT impregnated with elemental-i iodine,: iodide carrier is added and leached with NaOH. The stable iodide and I-131 is then stripped and extracted as iodine and precipitated as PdI2 ' mounted 'on a nylon planchet, and assayed by low level beta counting. ! METHOD 2. -If the charcoal used in the filters is impregnated with iodine,,the chemical yield of 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.
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~Direct P.adiation 4(TLD)
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.CaSO 4
- 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 mil 11 roentgen for the collection period or [ mR/ collection' time period.
- r. Milk.'
' Iodine-131 i
! L. . Stabl.e; iodide carrier 'is added to an aliquot of milk and the io-dide_and I-131-is removed by anion exchange resin. -The iodine is stripped . 4 _w ma--,i.% y r g y=.y - - y , _ c- -
WTELEENNE - ISMOPES with Na0C1 solution, reduced with hydroxylamine hydrochloride, an'd V extracted into CllC1 # as free iodine (I2 ). It is then back-extracted into NallS0 3 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 add oxalic acid, followed by NH OH until thesolutionisalkalineinordertoprecipitatecalciumandstronfiumoxalates. This precipitate is filtered and ashed, and the ash is dissolved in nitric acid. Strontium is purified by. repeated precipitations as nitrate in concen-trated HNO3 . Barium and iron scavenges are performed and stable yttrium carrier added ,.followed by a 5 to 7 day period for Y-90 ingrowth. The yttrium is precipitated 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 SrC03, mounted on a nylon planchet and counted in a low level beta counter for Sr-89.and/or the Y-90 ingrowth.
Gamma Isotopic Analysis
. Transfer 1 liter of milk to a 1-liter wrap-around Marinelli count-ing beaker and~ radioassay on a high resolution Ge(Li) detector.
j 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 internalElow level gas proportional counter. Very low levels of activity can be . detected due to the sophistication of. the counting eq'uipment, the electronics, and the shielding.
Gamma Isotopic Analysis One liter of sample is transferred to a 3-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 zinc furnace, mixed with methane counting gas and is radioassayed stil-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 shielding.
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' Gamma Isotopic Analysis One liter of sample is transferred to a 1-liter Marinelli wrap-around counting beaker and counted on a Ge(Li) detector.
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 mi bottle with a green leafy vegetation. Record sample weight and radioassay on a Ge(Li) detector. Calculate the ob-served gamma emitting nuclides in pCi/gm wet. Soil and Sedimedt/ Silt-Gamma Isotopic . Analysis _ j Fill a 300 m1 bottle with soil, record the sample 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 HNO3 ; then heat.the sample
. for 2 hours to leach strontium from the soil. Filter the resulting solution, wash the precipitation with hot water, and discard the residue. Evaporate
[ 3 the' filtrate to a few milliliters and add NH4 0H until alkaline. Add sat-
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.j . urated Na 2C0z solution to precipitate SrC0 ,3 and. centrifuge and discard supernate.- Dissolve' precipitate in HNO3 and evaporate to'almost dryness. Proceed with Sr-89, Sr-90 purification procedures using fuming. nitric acid, q an Fe(OH)3 scavenge, etc.' , 'k . J s
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N'TELEDYNE' ISOTOPES I
.fl ABSTRACTS OF THE RADI0 ASSAY PROCEDURES _'
The' lower limits of detection for radionuclides by the radioassay i procedures are listed in Table 3. Gross Beta _ Evaporated or solid phase aliquots are transferred to a 2-inch J - 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 l
~ filter pa'per source geometries on 55 cc Ge(Li) detectors coupl channel spectrometers. 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. l C l Tritium An aliquot of distilled sample is added to scintillation cocktail and counted in a liquid scintillation spectrometer, or converted to the L gaseous phase and counted in an internal gas proportional counter dep on sensitivity requirements. l' > Iodine-131 Mounts-are counted in a low level gas flow thin window Geiger coun-U Nuclide purity is established by counting over at least one half-life. ter. Positive detections-of I-131 are also verified by counting on a. beta-gamma coincidence spectrometer. il '
!- Rare Gases _
l Purified fractions are assayed,in internal gas proportional counters. i l l ( .
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- NTELEDYNE
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. lSOTOPES ,
y TABLE 3 LOWER LIMITS OF DETECTION l
* ** LLD 6 Sampled Volume ;
Sample Analysis Reporting Units Required i 1.- Airborne Particulate 3 2.5x10jpCi/m Gross Alpha -125 m
; Gross Beta. 7.6 x 10 pCi/m
. Ge(Li) Gamma Isotopic See Table 3.2 1625 m3
- 2. Airborne lodine -2 Charcoal Cargridge I-131 **2.4 x 10 pCi/m 125 m l 3. . Direct Radiation TLD Environmental Badge 2 mR 2 mR .
- 4. Milk Sr-90 0.8 pCi/1 4 liters I-131 by Chemical Separation 0.5 pCi/1 Ge(Li) Gamma Isotopic (Cs-137) See Table 3.2 Cs-137 Chemical Separation 3 pCi/1
- 5. -Well Water Gross Alpha 0.5 pCi/1 2 liters Gross. Bet.a 0.5 pCi/1 4
Tritium:(gas count) 100 pCi/1 Ge(Li) Gamma ~ Isotopic See Table 3.2
- 6. Surface Water .
Gross Beta 0.5 pCi/1 2 liters Tritium.(gas count) 100 pCi/1 Ge(Li) Gamma Isotopic See Table 3.2
- 7. . Fish: Flesh
- Gross Beta pluc K-40 0.1 pCi/gm wet (2) 1 Kg Ge(Li) Gamma Isotopic See Table 3.2 Sr-89 *0.8 pCi/gm Sr-90 *0.5 pCi/gm
- 8. Vegeta1! ion (corn, leaf,~ food, terrestrial, aquatic)
Ge(Li) Gamma Isotopic - See Table 3.2 (2) 1- Kg Sr-89 0.8 pCi/gm Sr-90. 0.5 pCi/gm .
-9. Soil
- Ge(Li) Gamma Isotopic See Table 3.2 .1 Kg- -
'10. Silt ~
.Ge(Li) . Gamma Isotopic See Table 3.2 (2) 1 Kg:
Sr-89 0.8 pCi/gm Sr-90 0.5 pCi/gm 15
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' 'lSOTOPES
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i TABLE 3.2 , LOWER LIMITS OF DETECTION BY HIGH RESOLUTION Ge(Li) GAMMA SPECTROSCOPY ENVIRONMENTAL SAMPLES , Water (1 liter) Soil 6 Vegetation Filters Nuclide' 'pci/1 (400 gm) pCi/gm pCi/ total filter Be-7 8E+01 2E-01 2E+01 K-40 2E,+02 SE-01 SE+01 Cr-51 8E+01 2E 8E+01 Mn-54 8 2E-02 2
, Co-58 8 2E-02 2 Fe-59 IE+01 4E-02 3
__ ! Co-60 8- 2E-02 2
'Zr 1E+01 4E-02 3 Ru-103- 8 2E-02 2 Ru-106 8E+01 2E-01 8E+01 I-131 10 3E-02 2 Cs-134 9 2E-02 2 Cs-137 9 2E-02 2 Ba-140 3E+01 8E-02 6 La-410 - 2E+01 4E-02 -2E+01 Ce-141- 2E+01 4E-02 3
-Ce-144' 8E+01 2E-01 2E+01 Ra-226 -
6E+01 1E-01 1E+01 1E+01 2E-02 1E+01 Th-228 j o . a 16
d TTELEDYNE -
- ISOTOPES i~'
TME 3 LOWER LIMITS OF DETECTION 1 i
- 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 aon the wet versus ash weight. factor.
** Analysis by chemical separation and beta counting of PdI2 . The non-
. impregnated with elemental iodine charcoal cartridges must be used when chemical separation is required.
*** The LLD values listed in this table are at the mid-collection time. Samples must be counted within one half-life after collection for these LLD values to be applicable.
4*00 # ]I LLD = 3 , (Ref. 10) 2.22 (V)(c)(DF) 2.22 (V)(c)(DF)(Y) where S= background = cpm At = counting time = min. d
'2.22 = conversion factor =
V= volume or weight of sample c= counter efficiency ) i DF = decay factor of the radionuclide from , i
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-mid-collection.to mid-count time ; ^}
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.F Y= chemical yield LLD = lower limit of detection at the mid-I collection' time l
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\~/ QUALITY CONTROL OF ANALYSIS i
Important elements of the Quality Control Program at Teledyne Iso- l 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 01/15/80, of the manual has been issued to the Virginia Electric and Power Company.
~ The Quality Control Manual contains (a) Specifications for the handling and processing of samples and the documentation required for calculating and reporting the results af the' analysis.
pa (b) The or'ganization chart of the Environmental Analysis . Group at Teledyne Isotopes and the resumes of supervisory personnel.
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(c) References to the routine' stability checks of backgrounds and check sources required for the calibration of the counting instruments used for radioassaying of samples. (d) References to the operational checks on blanks, spikes, splits, and cro.ss checks of samples.
-(e) A.section on accuracy checks containing summaries of inter-comparison data with EPA cross check programs
- 2. . Laboratory Procedure Control Approved. laboratory procedures are followed at Teledyne Isotopes for the analysis:of each samples media for specific radionuclides. Copies
- of the following procedures were issued to the Virginia Electric and Power Company:' Determination-of Radiostrontium, Determination of Radioiodine, Detection of-Gross Alpha and/or Gross Beta, Determination.of Gamma Spectra, Determination of Tritium.
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VTELEENNE ISOTOPES TABLE 8 s
-j RADIATION DOSE TO TllE INDIVIDUAL FROM NATURAL AND ARTIFICIAL SOURCES (FROM REF. 11)
Natural and Artificial Annual per Capita Source In Exposure Source- Whole Body Dose Ref. 11 ,
. Ambient external gamma 55 mrem / year Page 36, Table 2-13 (Virginia)
Medical bone marrow dose 103. mrad / year .Page 213, Table.8-3 to the adult population 1970 K internal constitutent 17 mrem / year Page 29, Table 2-9 of body for beta, and gamma whole body Global fallout - total annual 4.4 mrem / year Page 131, Table 4-10 4 per-capita body dose, est. 1980 4 h 4 i e 8 9 4
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T TELEDYNE- , ISOTOPES ' REFERENCES i /
- 1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8
" Environmental Technical Specifications for Nuclear Power Plants,"
December 1975.
- 2. Quarterly reports on the Environmental Radiological Monitoring Pro- ,
gram (ERMP) at the North Anna Power Station prepared by Teledyne Isotopes (IWL-0268-345 and 359 July-December 1974).
- 3. Quarterly reports on the ERMP at the North Anna Power Station prepared
.by Tele' dyne 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-0268-387, 394, and 395 January-December 1976).
- 5. Quarterly reports on the EHRP 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 y Virginia Electric and Power Company (NAPS).
- 7. Appendix B to Operating License, Environmental Technical Specifications for North Anna Power Station, . Units 1 and 2,-Virginia Electric and Power Company, Docket Nos.50-338 and 50-336,
- 8. Virginia Electric and Power Company, Radiological Environmental Monitoring Manual, June 1977.
- 9. Teledyne Isotopes, " Environmental Radidtion Anal / sis Quality Control Manual, "IWL-0032-361, 1975, Copy No. 14 issued to Virginia Electric
-and Power Company.
'10. Energy Research and Development Administration, HASL Procedures Manual, (HASL-300,D-08).
- 11. United States Environmental Protection Agency. " Radiological Quality of the Environment in the United States, 1977" EPA 520/1-77-009, September 1977.
- 12. United States Nuclear Regulatory Commission. Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor
> Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," October.1977. n 20
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"Fr1rELEDW'NE ,
ISC01) PES '
- 13. Quarterly reports of the REMP at the North Anna Power Station prepared by
-. Teledyne : Isotopes, IWL-6343-432, January 1, 1978-December 31, 1978.
- 14. Quarterly reports of the REMP at the North Anna Power Station prepared by Teledyne Isotopes IWL-7043-444, January 1, 1979-December 31, 1979.
- 15. U.S. Nuclear Regulatory Commission, Regulatory Guide 4.15 " Quality Assurance for Radiological Monitoring Programs -- Effluent Streams and the Environment", February, 1979. ,
- 16. Radiological Monitoring Program, North Anna Power Station, Annual Report IWL-8043-457, January 1, 1980 to December 31, 1980 prepared by Teledyne Isotopes.
- 17. Radiological Monitoring Program, North Anna Power Station, Annual Report IWL-8143-468, January 1, 1981 to December 31, 1981 prepared by Teledyne Isotopes.
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