ML20042E972
| ML20042E972 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1989 |
| From: | Dreyer E, Mary Johnson, Stafford A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-246, NUDOCS 9005070045 | |
| Download: ML20042E972 (131) | |
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VIuGINIA Eu:crute Axn POwl:n COMPANY Itwitwown,Viaos.or unnoi 1
i April 30, 1990 l
United States Nuclear Regulatory Commission Serial No. 90 246 l Attention: Document Control Desk ND/RMN:
Washington, D.C. 20555 Docket Nos. 50 338 50 339 License Nos. NPF-4 NPF 7
- Gentlemen: ;
1 VIRGINIA ELECTRIC AND POWER COMPANY .
NORTH ANNA POWER STATION UNITS 1 AND 2 :
ANNUAL RADIOLOGICAL ENY l t
Attached is the North Anna 1989 Radiological Environmental Monitoring Program Report which fulfills the requirements of Technical Specification 6.9.1.8 for the Annual -
Radiological Environmental Operating Report .
If you have any questions, please contact us.
Very truly yours, kgh.
W.L te@$ri Senior Vice President Nuclear Enclosure cc: United States Nuclear Regulatory Commission Region ll 101 Marietta Street, N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S Lesser NRC Senior Resident inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street ,
Richmond, Virginia 23219
, f005070045 09123j l kDR ADOCK 0500o33g FDC I
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VIRGINIA FI ECTRIC AND POWER COMPANY i NORTH ANNA POWFR STAT 1QM
- t RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM "
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FOR 1989 *** .
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Prepared by ,
VIRGINIA ELECTRIC AND POWER COMPANY and TELEDYNE ISOTOPES O 1
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i ANNtJAI. R ADIOLOGICAL ENVIRONMENTAI. OPER ATIN NORTH ANNA POWER STATION t
JANUARY 1,1989 to DECEMBER 31, 1989 4
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Prepared by: N Michabl. Johnson Superviser Radiological Analysis Reviewed bg: .
7 Erich W. Dreher Seperviser Health Physics Technical Services Approved by: - >
IIlanH.Shord O * ' i i > 'i -
TABLE OF CONTENTS SECTION IIT.LE P. AGE I. IN'UtODU CTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
II. S AMPLING AND ANALYSIS PR OG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
III. PROG RAM EXCEPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
IV.
SUMMARY
AND DISCUSSION OF 1989 ANALYTICAL RESULTS............. 22 ,
A. AIRBORNE EXPOSURE PATHWA Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23
- 1. Air Iodine /Pardculates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 2. Precipitation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 6 .
- 3. Soil.............................................................<................26 B. WATERBORNE EXPOS URE PATHWAY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 1.
G round/We ll Water. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 2. River Wa ter . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 3. S urface Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
C.
AQU ATIC EXPOSURE PATHWAY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 1. Sediment /S ilt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . 3 1 t
- 2. S horeline Soil . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
l l D.
INGESTION EXPOS URE PATHWA Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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- 1. Milk...............................................................................36
- 2. Fish.......s,......................................................................36
- 3. F oo d/V e g e t a t i 0 n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 1
t E. DIRECT RADIATION EXPOS URE PA'IEWA Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,40 t
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- 1. TLD D o s i m e t e rs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . j.
i V. CO N CLU S I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
VI.
p REFE REN CE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l i
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n TABLF OF CONTENTS (Cont.) i O SECTION t
T.IILE P.AfE VII. APPEND 1CES..............................................................................48 l APPENDIX A Radiological Environmental Monitoring............................. 48 Program Summary - 1989 t
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1 APPENDIX B - Data Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
APPENDIX C Land Use Census - 1989..............................................88 >
APPENDIX D Synopsis of Analytical Procedures....... ...... . ... ........ . . . .. . .. .. 95 i 1 r s
APPENDIX E EPA Interlaboratory Comparison Program........................109 i
LIST OF FIGUREE i
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- 1. Environmental S ampling 1.ocations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 r
- 2. Land U se Cen su s M ap . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '9 LIST OF TRENDING GRAPHS .
1.
Gtuss Be ta in Air Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2, Tritium in River Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . " " " "" "" " . " " " "" " " " " . 2 8 l 3.
Tri ti u m i n S u rfac e W a t e r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
- 4. Cobalt 58 in Sediment S11t...................................................................32
- 5. Cobalt 60 in Sediment S11t...................................................................33 6.
Cesium 134 in Sediment S 11t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . m . . . . . . . . . . . .
7.
Ce sium- 13 7 in Sediment S 11t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
( 8.
Ce si um- 134 in Fi sh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .:
9.
Cesi u m 137 in Fi sh . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
10.
Environmental Radiation TLDs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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- 11. U S E PA Cro s s Che c k Pro gram.. . . .. . . .. .... .. .. .. .. . . .. . . . . .... .. . . . . .. .. . . ... . .. .. . .. . . . I 1 1 t
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LIST OF TABLEE O i l
TABLE l EAfgE j B1 Conce ntration 6 of lodine 131 in Filtered A tr........................................................ 60 i
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B2 Concentrations of Gross Beta in Air Particulates. . . . . . . . . . . . . .. . . . . . . .. . . .. . . . . . . . . . . .. .
l B-3 Concentrations of Strontium and Gamma Emitters in Quanerly Air Paniculates .............. 68 B4 Concentrations of Gmss Beta, Tritium and Gamma Emitters in Precipitation .................. 71 '
B5 Concen tra tions of Gamma Emit ters in So11.......................................................... 72 B6 Concentrations of Strontium. Tritium and Gamma Emitters in Ground /Well Water........... 73 B7 Concentrations of Tritium, Strontium and Gamma Emitters in River Water.................... 74 B8 Concentrations of Tritium, Strontium and Gamma Emitters in Surface Water.................. 75 B9 Concentrations of Tritium, Strontitim and Gamma Emitters in Surface Water.................. 76 State Split '
B 10 Concentrations of Gamma Emitters in Sediment Silt............................................... 77 B-11 Concentrations of Gamma Emitters in Shoreline So11.............................................. 78 B 12 Concentrations of Gamma Emitters in Milk . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . .
B 13 Concen trations of Gamma Emitters in Fish . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
B 14 Concentrations of Gamma Emi tters in FoodNege tation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 B 15 Direct Radiation Measurements - Quanerly & Annual TLD Results ............................. 85 C B 16 Direct Radiation Measurements Sector Quanerly TLD Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 86 ili
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FORWARD This report is submitted as required by Technical Specifiestion 6.9.1.8, Annual Radiological Environmental Operating Report for North Anna Power Stations, Units 1 and 2.
( Virginia Electric and Power Company Docket Nos. 50-338 and 50-339.
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2 I. INTRODUCTION -
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION RADIOLO61 CAL ENVIRONhiENTAL OPERATING PROGRAM
- 1. INTRODUCTION The operational radiological environmental monitoring program conducted for the year 1989 for the North Anna Power Station is provided in this report. The results of measurements J
and analyses of data obtained from samples collected from January 1,1989 through December 31, 1989 is summarized.
A. The North Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles west of Fredericksburg, Virginia. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply ;
syster:ts and turbine generator fumished by Westinghouse Electric Corporation. Each unit is designed with a gross electrical output of 970 megawatts electric (MWe). Unit I achieved commercial operation on June 6,1978, and Unit 2 on December 14,1980.
g B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a)
U require that nuclear power plants be designed, constructed, and operated to keep levels of ;
radioactive material in effluents to unrestricted areas as low as reasonably achievable l (ALARA). To ensure these criteria are met, the operating license for North Anna Power I
- Station includes Technical Specifications which address the release of radioactive effluents.
l Inplant monitonng is used to ens'u re release limits are not exceeded. As a precaution against unexpected or undefined environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Technical Specifications, j C. Virginia Electric and Power Company is responsible for collecting the various indicator and i control environmental samples. Teledyne Isotopes is responsible for sample analysis and l- submitting reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with control levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural l variation to be expected. This preop: rational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation.
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dose consequence to man, the data is compared to the reporting level concentrations listed >
in the USNRC Regulatory Guide 4.8 and Table 4.12 2 of North Anna's Technical l Specifications. These concentrations are based upon the annual dose commitment i recommended by 10CFR50, Appendix I, to meet the criterion of "As Low As Is !
l Reasonably Achievable".
! E. This report documents the results of the Radiological Environmental Monitoring Program l for 1989 and satisfies the following objectives of the program:
- l. To provide measurements of radiation and of radioactive materials in those exposure '
pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation. !
- 2. To supplement the radiological effluent monitoring program by verifying that radioactive effluents att within allowable limits. .
l O 3. Te identify chan8es of ,adioactivi,y in the envi,onment. -
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- 4. To verify that the plant operations have no detrimental effect on the health and safety of the public.
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l O u. SWPUNG AND ANALYSIS PROGRAM T
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II. SAMPLING AND ANALYSIS PROGRAM O A. SAMPLING PROGRAM
- 1. Table I summarizes the sampling program for North Anna Power Station during 1989. Figure 1 indicates the locations of the environmental monitoring stations.
- 2. For routine TLD measurements, two dosimeters made of CaSO4:Dy in a tenon card are deployed at each sampling location. Several TLDs are co located with NRC and Commonwealth of Virginia direct radiation recording devices. These i are indicated as "co location" samples. -
- 3. ' In addition to the Radiological Environmental Monitoring Program required by North Anna Technical Specifications, Virginia Electric and Power Company splits samples with the Commonwealth of Virginia. All samples listed in Table 1 are collected by Vepco personnel except for those labeled state split. All samples are shipped to Teledyne Isotopes in Westwood, New Jersey,
- 4. All samples listed in Table 1 are taken at indicator locations except those labeled
" control".
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-1 B. ANALYSIS PROGRAM i F
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, 1. - Table 2 summarizes the analysis program conducted by Teledyne Isotopes for i i North Anna Power Station during 1989.
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O TABLEI (Page 1 of 5) !
Nenh Arms Pbwer Sisten - 1999 RADMXDGICALSAMPLING STATXM5 IMSTANCE AND DHtBCTION FROM UNITNO.1 i.
IHetsece Compees Cr.a6 Seenple Medle Locatlee Stettee Mlles Direceton
, is.ees Fr a _ - 1 Bemerlis Envirenamestal NAPS Sewage 01 0.20 NE 42" Queeerty On ssee.See Sg4is Therunelemsteeweist Tremenaw Plant Desimetry (TLD) & Asmusepy Fredericks HeB 02 5.30 SSW 22Y Queeerly Same Spia Meieral. Va 03 & Aa===87 7.10 WSW 243' Qumresty
& A8='a'By Weres Crossroed: 94 5.10 WNW 2ir?" Queserfy semeesyin >
Reese 752 a A8= = Ey 05 4.20 NME F Quaterly Sengen's Creek & As===sy 05A 3.20 NME 11' Qwenty Musim
& Assummty levy. VA 06 4.70 ESE I15' Queesty Samme Sylie.Cetmeneet
'& Asummmmy Bumpass VA 07 7.30 SSE 16?" Quaseerty Samme Split u
Endof Rouse 685 21 a Aa'=sy 1.00 WNW 30t* Queeerly Esclassen Besmedwy Rouse 700 & Assummsy Somme SyEit.Co-Lecames 22 IM W5W 242" Queenly Euchswei Beemdwy !
" Aspen Hi8s* & AssauBy Sasse Sylit 23 0.93 SSE 158* Quecerty Enclumene Boundary Orange VA a As== sy same syne.C.tec=or 24 22.00 MW 32 7 Quecerty Omuset ;
& Amammy Beanng Coe% Tower N.1133 0 06 N F 5 surgeon's Creet Queemly On-Sine N-2/34 3.20 N II* Quaserfy i
M Ptrtung Im "C" NME-3/35 0.25 NNE 3r Quanaty On-Sise (esite)
Good Hope Church NME-4/36 4.96 NME Phrking Lee "B" 25" Qumely sensesylis NE-5/37 0.20 NE 4F Queesty
! IAme Asums Merwee NE-6/38 1.49 N3ine
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NE 34* Quanaly Wendier Tower Fesioe BWE 7/39 0.36 ENE
- Rouse 689
'N' Queterly 0+5iec BWE-8N0 2.43 ENE 68* Quanaty
{ Near Trasung E 9NI 0.30 E 9f*
Feniwy Queserty On-Sine I
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.o O O O TABLEI (Page 2 of 5)
North Anna F- wcr Station - 19iN t
RADIOLOGICALSAMPIJNG STATIONS DISTANCE AND DIRECHON FROM UNrrNO. I Saimple Medle Distance Compass GWiectlee Locatten Statlee Miles Directlen Degrees Freguesey Renaarks Envireemental " Morn.ng Glory IT E-10/42 2.85 E 9P Querierly
, Thermolesaleescent Islexl Dike ESE-II/43 0.12 ESE 103* Querierly On-Sine Destmetry (TLD) Route 622 ESE-12/44 4.70 ESE 115' rx:enerly VEPCO Biology Lab SE-13/45 0.75 SE 13B" @ sterly On See Rouse 701(Dam Enerance) SE-14/46 5.88 SE 137' ipnerly
" Aspen Hills" SSE-15/47 0.93 SSE 158* Querierly Eachmaan Bomulary Bk Creek SSE-16/48 233 SSE 165* Quenerly i e
Warehouse CW Game S-17/49 0.22 S 17 7 . Querierly On-Siee Bk Creek Church S-18/50 1.55 S 178* Quaterly NAPS Access Road SSW-19/51 036 SSW 197* Queurly On-Siee Rouse 618 SSW-20/52 530 SSW W Quarterly NAPS Access Road SW-21/53 030 SW 211r Quenerly On-Sise Route 700 SW 22/54 ~ 436 SW 232' Quarterly 500 kv Tower WSW-23/55 0.40 WSW. -237' Quenerly On-Sise Route 700 WSW-24/56 1.00 WSW 242* Quenerly Exclusion Boundary (Exchaion Boundary)
NAPS RadioTower W-25/57 031 W 279". Quarterly . On-Siee Rouie 685 W-26/58 1 55 W .zw Queialy -
, End of Rouse 685 WNW-27/59 1.00 WNW 3Di* - Quwerly Escheson Boundary H. Purcetrs Privene Rd. WNW-28#0 - 1.52 WNW 3GP '
Queurly Co4mcaman End of #1M2 Intake NW-29MI 0.15 NW 3 21* Quanaly On-Siec Lake Amia Campgetend NW-30M2 2.54 NW . 319'_ Quarterly
- 1M2 Intake NNW-31M3 0,07 NNW
' 349' Queserly On-Sise Rouse 208 NNW-32/64 3 43 NNW' 344' Queerly Burnpass Pbs:Offkx C-1/2 730 SSE 1.67* Quanaly Commet Orange.VA C-3/4 22.00 NW 325* Qusierly Connel Mineral,VA C-SM 7.10 WSW' 24 7 Quenerly Control Lnuisa, VA C-7/8 11.54 WSW 257". Quenerly Controi
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O O O TABLEI (Page 3 of 5)
North Arma Pbwer Station - 1989 '
RADIOLOGICALSAMfUNG STATIONS a DISTANCE AND DIREC110N FROM UNIT NO. I Sample Medla Distance Comepass C ;;;.; tion Location Station Miles Directlen Degrees ,
Fregeency Rennerks Airboree Particolate NAPS Sewage 01 0.20 NE 42"
.i' and Radieledlee Weekly On-Sir. Sense Split Tn:stment Plant Fredericks Hall 02 5.30 SSW i Mineral.VA 205* Wedly 03 7.10 WSW -243" Weekly Wares Crossroads 04 5.10 WNW 237' Weekly Route 752 05 4.20 3TNE F Sturgeon's Creek Marina Weekly 05A 3.20 N Il' Weekly Levy. VA 06 4.70 ESE 115' Weeldy Burnpass, VA 07 7.30 ;
End of Rouse 685 SSE . 167* Weekly 21 1.00 WNW 301* Weddy Rome 700 22 1.00 Excheian Bowidery
. WSW 242' Wcdly Exclusion Boundary
" Aspen Hills" 23 SuneSpsit 0.93 SSE 158' Weekly Orange. VA 24 22.00 Excheion Boemidery NW 325*. Weekly Ceneral Serface Water Wasse Heat . 08 1.10 SSE 148' Momhly Semme Split Tremonent Facility
' (Second Cooling Lagoon) .
lac Anna (upseenn) 09 2.20 NW 3F
, (Route 208 Bridge)
Manhly Connot. Sense Split Civer Water Nonh Arms River 11 5.80 SE 128* Quenerly (downstream)
Gremed Water BiologyIA 01A 0.75 SE (Wen Waecr) 1385 Quenerly Samme Split Precipitation Biology Lab OIA 0.75 SE 138* Monddy Aquetic Sediment Wasse Heat 08 1.10 ;
SSE 148' Sesni-AnnuaBy Samme Split Tressment Facility (Discharge Lagoon)
Lake Anna (upmercam) -09 2.20 NW 32f Semi-Annually Nortn' Arma River Control.Senee Split 11 5.80 SSE 128' M A- *
(Downstream) ..
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TABLEI
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North Anna Ibwer Stanon - 1989 RADIOffGlCALSAMPUNGSTAllONS
- DISTANCE AND DIRBC110N FROM UNTTNO. I
_ Sample Media Disassee Comepass C eRecties '
Location Station Miles Direction Degrees Fr:gwy Remmarks Shoreline Soll take Anna (upsaream) 09 2.20 NW (Rouse 208 Bridge) 3F Semi-AnnumDy Sense Split Soll NAPS Sewage 01 0.20 NE 42' Once/3 years On-Site Treatnunt Plant LAias Hall 02 5.30 SSW 21B' Mmeral.VA :. Once/3 years 03 7.10 WSW 343' Wares Crossroads Oncv3 years 04 5.10 WNW 287*
Rouse 752 Oned3 years 05 4.20 NNE F Sewgeon's Creek Marina Once/3 years 05A 3.20 N 11' Oned3 years levy, VA 06 4.70 ESE 115'. Once/3 yees n=npass, VA 07 7.30 SSE 167' End of Rouse 685 Once/3 years 21 1.00 WNW 3 01' Rouse 700 Once/3 years Exclusion Boundary 22 ' 1.00 WSW 242' (Exclusion Boundary) Once/3 years Exclusion Boemiary w
C " Aspen HiHs" 23 0.93 SSE 158' Once/3 years Orange,VA 24 22.00 Exclusica Boundary NW 325' Once/3 years Connoi Milk Holladay Dairy 12 8.30 NW 3F Monehty (R.C. Goodwin) Sense Split TcricIrs Dairy 13 5.60 SSW 21 5
- Monthly SenseSplit (Fndericks Hall)
Fish Wasse Hear 08 1.10 SSE 148" Quenerly sense Spha Tresonese Facihty (Second Cooling lagoon) '
take Anna (upsercam) 09 2.20 NW (Route 208 Bndge) 3F Quararly Consol.Samee SpEt Food Products Rouse 713 14 1.20 (Broadleaf NE 43" Monthly ifevadsNe Vegesanon) Rouse 614 or at herwse 15 I.70 ' SE 133' Monthly if availeNe or at herwst
_ _ _ _ _ _ _ _m _ _ _ _ _ .
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3-TABLEE
-(Page 5 of 5)
North Anna Ibwer Stauan - 1999 RADIOLOGICALSAMPLJNG STATIONS DISTANCE AND DIRECTION FROM UNIT NO. I Distance Cesapess CoHution Sainple Media Location Station Miles Direction Degrees Frequency Reinerks Food Products Route 629622 16 12.60 NW (Broadleaf 314* ' hihly if available '
Vegetation) or at harvesa End of Roine 685 21 1.00 WNW 30l* hthlyif available or as harve.st -
Aspen Hills 23 0.93 SSE 158* Munehty if available or at harvest w
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i TABLE 2 9
(Page 1 of 3)
O "oara^"x^ eowen sr^i r os SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Thermoluminescent Quarterly Gamma Dose 2mRi2mR mR/std. month Dosimetry (TLD)
(84 Routine Station TLD's) 12 Station TLD's Annually Gamma Dose 2mRi2mR mR/std. month Airborne Weekly I-131 0.07 pCi/m3 Radiolodine Airborne Weekly Gross Beta 0.01 pCi/m3 Particulate Quarterly (1) Gamma Isotopic pCi/m3 ;
Cs-134 0.05 Cs 137 0.06 Annually Sr-89 0.005 pCi/m3 Sr 90 0.0002 Surface Water Monthly Gamma Isotopic pCi/l Mn-54 15 Fe-59 30 Co-58, 60 15 Zn 65 30 Zr-Nb 95 15 I131 10 Cs-134 15 Cs 137 18 Ba La 140 15 Quarterly (1) Tritium (H 3) 2000 pCi/l 2nd Quanerly' Sr-89 5 pCi/l Composite Sr-90 1 (1) Quarterly Composites of each location's samples will be used for the mquired analysis.
LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by 7
s Teledyne Isotopes may be lower than those listed.
12
fk I
TABLE 2 (Page 2 of 3) i O
v NORTH ANNA POWER STATION -
SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS River Water Quarterly Gamma Isotopic pCi/l Mn-54 15 Fe 59 30 '
Co 58,60 15 Zn 65 30 Zr Nb 95 15 1131. 10 Cs 134 15 Cs 137 18 Ba-La 140 - 15 Quarterly Tritium (H 3) 2000 pCi/l 2nd Quarterly Sr-89. 5 pCi/l Sample Sr 90 1 Ground Water Quarterly Gamma Isotopic pCi/l-(Well Water) Mn-54 15 f's Fe 59 V 30 Co 58,60 15 Zn 65 30 Zr-Nb 95 15 I-131 1 Cs 134 15 Cs-137 18 Ba La 140 15
, Quarterly - Tritium (H-3) 2000 pCi/l i
! Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry)
Sediment Cs 134 150 Cs-137 180 Annually Sr-89 200 pCi/kg (dry)
Sr90 40 .
4 Shoreline Soil Semi Annual Gamma Isotopic pCi/kg (dry)
Cs 134 150 Cs-137 180 LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Pmgram. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed.
13
ur TABLE 2 1
(Page 3 of 3)
( NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM 3
SAMPLE MEDIA FREOUENCY \
_.,)N A L Y SIS LLD* REPORT UNITS Soil Once per 3 yrs. Gamma Isotopic pCi/kg (dry) i Cs-134 150' Cs 137 180 Once per 3 yrs. Sr89 200 pCi/kg (dry)
Sr-90 40 Milk Monthly I131 1 pCi/l Monthly Gamma Isotopic pCi/l Cs 134 15 Cs 137 18 Ba La-140 15 I'
Quanerly Sr89 5 pCi/l Sr-90 1
.. Flsh Semi Annual ;
Gamma Isotopic pCi/kg (wet) i Quarterly Mn 54 130 Interim period Fe-59 260 L Co-58, 60 130 Zn 65 260 Cs-134 130 Cs 137 150 Food Products Monthly if Gamma Isotopic (Broadleaf pCi/kg (wet) -
available or Vegetation) at harvest Cs-134 60 Cs 137 80 I-131 60 . pCi/kg (wet) i Note:
This table is not a complete listing of nuclides which can be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed.
14
LEGEND FOR THE NORTE ANNA F0WER STATION ;
ENVIRONMENTAL' MONITORING STATIONS OVERVIEW MAPS (FIGURES l', 2, 3)
MAP Div1R0iGEmiAL STATION, MAP snvIRONMENTAL STATION DESIGNATION IDENTIFICATION DESIGNATION- IDENTIFICATION 1 N-1/33 23 WSW-23/55 2 N-2/34.05A 24 WSW-24/56.22 3 NNE-3/35 25 W-25/57 4 NNE-4/36 26 W-26/58 5 NE-5/37.01 27 WNW-27/59.21 6 NE-6/38.14 28 WNW-28/60-7 ENE-7/39 29 NW-29/61 8 ENE-8/40 , 30 NW-30/62.09 I 9 E-9/41 31 O 10 E-10/42 32 NNW-31/63 NNW-32/64 11 ESE-11/43 33 03. C-546 12 ESE-12/44.06 34 04 13 SE-13/45.01A 35 .05 i
14 SE-14/46 36 07. C-142 1 15 58E-15/47.23 37 08 '
16 SSE-16/48 38 11 ;
17 S-17/49 39 12 f
- 18 S-18/50 40 13
. 19 SSW-19/51 41 15 20 SSW-20/52.02 42 16
! 21 SW-21/53 43 24. C-3&4 ',
22 SW-22/54 44 C-748
! Map Designation # t 1 Road Numbers 15
F E1 O (Page.1 cf 3)
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(Page 3 of 3)
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l ENVIRONMENTAL MONITORING STATIONS OVERIEW MAP v
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III. EXCEPTIONS TO THE PROGRAM-k l,
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t III. EXCEPTIONS O
l REMP deviations for 1989 are listed in this chapter. Where possible, the causes of the deviations have been corrected to prevent recurrence.
Several air particulate / air iodine samples were not collected due to air sampler malfunctions. ,
There were six instances where there was a malfunction of the elapsed timer of a sampler and the Idr volume was estimated for a weekly period. In all cases, the gross beta analysis from the air paniculate filter and the iodine 131 analysis from the charcoal cartridge gave results which were comparable with the other stations for the weekly period and with historical data. Since the results i were in the normal ranges, the instances are not listed individually in the Exceptions Table.
Sever 6 air particulate / air iodine samples were not collected due to air sampler malfunctions. In order to assess the validity of these samples, an evaluation will be required in accordance with station procedures when the equipment does not operate properly. Factors considered in the assessment will include the condition of pumps, timer, fuses and particulate iodine ~ loading, Sample volume calculations will be performed. The equipment malfunctions will be reported on the IWL-1 form under 'Special Instructions'. Teledyne Isotopes will be requested to compare the data for the particular sample to historical data for the sample location. The evaluation will be reponedin the Annual REMPiepon.
A river water sample from station 11 for 04/01/89 was not collected. The surface water sample for 04M1/89 from stations 08 and 09 were also not collected. The State Split surface water samples from stations 27 and 33 did not meet the LLD for Ba/La-140 fmm 01/15/89 thru 12/15/89 due to the long lapse of time from collection to receipt at TI.' In addition, the LLDs for I-131 for 02/15/89 and 06/15/89 from stations 27 and 33 also were not met for the same reason.' T for the fourth quarter from station 22/54 was vandalized.
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REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND' ANALYSIS DURING 1989 NORTH. ANNA 1
- l Date of Location Description Sampling Reason (s) for Loss / Exception 24 Air Paniculate / 04/25/89 05/02/89
Equipment malfunction; no sample Airlodine collected.
07 Air Particulate / 06/06/89-06/13/89 Equipment malfunction; no sample -
Air Iodine . collected.
01 Air Particulate / 06/27/89 07/04/89 Equipment malfunction; no sample Air Iodine collected.
04 Air Particulate / 12/21/89 12/27/89 Equipment malfunction; no sample Air lodine collected.
1I River Water 04/01/89 Sample not obtained.
08/09 Surface Water 04/01/89 Sample not collected.
O 27/33 Surface Water 01/15/89 thru 12/15/89 LLD could not be met for Ba/La 140 due to long lapse of time from collection to receipt at TI.
5 27/33 Surface Water 02/15/89/ LLD could not be met for I 131 due 06/15/89 to long lapse of time from collection to receipt at TI.
22/54 Direct Radiation Fourth Quarter TLD Vandalized l
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AND DISCUSSION OF 1989: ANALYTICAL RESULTS f
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SUMMARY
AND DISCUSSION OF 1989 ANALYTICAL RESULTS ,
Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as required in the Teledyne isotopes Quality Assurance Manual ,
and are explained in the Teledyne Isotopes Analytical Procedures. 'A synopsis of analytical
. procedures used for the environmental samples is provided in Appendix D. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures that independen: checks on the precision and accuracy of the measurements of <
radioactive material in environmental samples are performed. The results of the EPA Interlaboratory Comparison are provided in Appendix E.
Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of the art measurement methods. Teledyne Isotopes analytical' methods meet the Lower Limit of Detection (LLD) requirements given in Table 2 of the USNRC Branch Tcchnical Position of Radiological Monitoring (November 1979, Revision 1) and -
Technical Specifications.
The following is a discussion and summary of the results of the environmental measurements taken during the 1989 reporting period.
A. Airborne Exposure Pathway
! 1. AirIodine/Particulates l
l Charcoal cartridges used to collect airborne iodine were collected weekly and
! analyzed by a radiochemical separation procedure for iodine-131. The results are presented in Table B 1. Of the 607 filters analyzed iodine 131 was measured in three samples with an average activity of 0.026 pCi/m3 and a range of 0.009 to 0.049 pCi/m3. All three positive results were below the required lower limit of detection and all were confirmed by i additional counting. Gross beta activity was observed in all fifty control samples with an average concentration of 0.020 pCi/m3 and a range of 0.006 to 0.045 pCi/m3. The -
average measurement for the indicator locations was 0.026 pCi/m3 with a range of 0.006 to l 0.081 pCi/m3. The results of the gross beta activities are presented in Table B 2. The l
l Q monthly averages of the gross beta concentrations for the eleven indicator locations and the controllocation are plotted from 1977 through 1989. With the exception of the five week J
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GROSS BETA IN AIR PARTICULATES 1
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h period in 1986 influenced by the Chernobyl accident, the gross beta activities were comparable to levels in the 1982 1988 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear vceapons testing by other countries. I Air particulate filters were composited by locations on a quarterly basis and were '
analyzed by gamma ray spectroscopy. The results are listed in Table B 3, Cosmogenically :
produced beryllium 7 was measured in all 48 composite samples. The average measurement for the control location was 0.041 pCi/m3 with a range of 0.027 to 0.053 pCi/m3. The indicator locations had an average concentration of 0.046 pCi/m3 and a range of 0.014 to 0.069 pCi/m3 Naturally occurring potassium-40 was detected in one control 4 sample with an activi:y of 0.029 pCi/m3 and in twelve indicator samples with an average measurement of 0.021 pCi/m3 and a range of 0.010 to 0.050 pCi/m3. All other gamma emitters were below the detection limits.
5 The second quarter composites of air particulate filters fmm all twelve stations were anc.lyzed for strontium 89 and 90. There were no detection of these fission products at any -
of the eleven indicator stations nor at the control stations.
- 2. . Precipitation A sample of rain water was collected monthly at station 01 A, on site,0.75 miles, 138 degrees SE and analyzed for gross beta activity. The results are presented in Table B-
- 4. The average gross beta activity for eleven months was 5.5 pCi/ liter with a range from 1.8 to 14 pCi/ liter. A semi annual composite was prepared and analyzed for gamma l emitting isotopes and tritium. All gamma emitters were below their detection limits.
Tritiam was measured in both samples with an average concentration of 265 pCi/ liter and a range from 210 to 320 pCi/ liter. These results were comparable to those measured in 1986 thru 1988.
l
- 3. Soil t j Soil samples which are collected every three years from twelve stations, were collected in July and analyzed by gamma ray spectroscopy. The results are presented in Table B 5. Naturally occurring potassium-40 was detecte.d in all twelve samples with an l
average activity of 10062 pCi/kg dry weight. The terrestrial nuclide radium-226 was monitored in all twelve samples with an average activity of 1868 pCi/kg dry weight and a O r #8 orto9ote 373oaci/*8 arr i 8at. Theri m.228, aise natura>ix occurring was detected in all samples with an aserage activity of 1318 pCi/kg dry weight and a range of 26
-t 447 to 3020 pCi/kg dry weight. The fission product cesium 137 was detected in eleven of O the iweive sampics ai an avera8. activitx of 453 vCi/k dry wei.hi and a ranse of 90.3 e 984 pCi/kg dry weight. The cesium-137 is attributed to past atmospheric nuclear weapons . .
testing. Cesium 137 was not detected in the sample from station 24, the control station.-
The twelve soil samples were analyzed for strontium 89 and strentium-90. There were no detections of strontium-89. Strontium 90 was detected in ten of the twelve i
samples whh an average activity of 82.7 pCi/kg dry weight and a range of 46 to 170 pCi/kg dry weight. These fission products occurred in previous years and are believed to be from
[
atmospheric nuclear weapons testing in previous years.
- F B. Waterborne Exposure Pathway
- 1. Ground /Well Water Water was sampled quarterly from the on site well at the biology laboratory. These samples were analyzed by gamma ray spectroscopy and for tritium ; The results are presented in Table B 6. No gamma emitting isotopes were detected. Tritium was detected
,] in the third quarter sample with an activity of 210 pCi/ liter This is a normal environmental level. The second quarter sample was analyzed for strontium 89 and strontium-90. There we e no detections of these isotopes above th: detection le*cel ' -
- 2. River Water A sample of water from the North Anna River was collected monthly except for April 1989 at station 11,5.8 miles downstream from the discharge lagoon,= 128 degrees SSE. The results are presented in Table B 7. The samples were analyzed by gamma-spectroscopy, and for tritium. The second quarter samples were analyzed in addition for strontium-89 and strontium-90.
Naturally occurring potassium 40 was observed in one sample with an activity of 67.3 pCi/ liter. All other gamma emitters were below the detection level. No detections of i strontium-89 or strontium-90 occurred. Tritium was measured with an average level of l
3749 pCi/ liter and a range of 1500 to 5840 pCi/ liter. This compares favorably with the average tritium activity for 1988 of 3925 pCi/ liter and a range of 3300 to 5350. The I average tritium activity in 1987 was 3680 pCi/ liter and a range of 2600 to 5170 pCi/ liter.
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- ) 3. Surface Water Samples of surface water were collected monthly from two stations. Station 08 is -
at the discharge lagoon,1.1 miles,148 degrees SSE on Lake Anna. Station 09 is 2.2 miles l
upstream on Lake Anna,320 degrees NW. .The samples were analyzed for iodine-131 by.
cradiochemical separation. No iodine was detected in the 22 samples analyzed. The results are presented in Table B 8. The samples were also analyzed by gamma ray spectrometry.
All gamma emitters were below the detection levels at either station.
A quarterly composite from each station was prepared and analyzed for tritium.
The tritium activity at station 08 was at an average level of 3725 pCi/ liter with a range of 2700 to 5200 pCi/ liter. The trend of the tritium activity at station 08 has been plotted. The tritium level had been increasing since the middle of 1978 when the average level was .g below 300 pCi/ liter. However, during 1989 the results were within the same range as those measured in 1986,1987 and 1988.
1 The tritium activity in the four quarterly composites from station 09 was at a level of 2850 pCi/ liter with a range of 1800 to 4300 pCi/ liter. The level of tritium for 1989 for L V station 09 is also within the same range as those measured in 1986,1987 and 1988, l
[-
L Samples of surface water were collected by the Commonwealth of Virginia from two stations. Station W-33 is located at the discharge lagoon while station W-27 is located .]
on the North Anna River at the RT. 208 Bridge, which is upstream of the site. Twenty-four samples were collected and analyzed by gamma ray spectroscopy and for tritium. The results are presented in Table B 9. ~All gamma emitters were below their detection levels.
i l One sample from each station was analyzed for tritium. The activity level at station W-33 was 4500 pCi/ liter. This compares favorably with the average activity of 4333 pCi/ liter during 1988 at this statioa.. The activity level at stat: in W-27 was 150 pCi/ liter.
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y C.- Aquatic Exposure Pathway i
- 1. Sediment / Silt Sediment samples were collected during April and September from each of three locations and were analyzed by gamma spectrometry. The results are presented in Table -
B-10. A number of man made and naturally occurring radioisotopes were detected in-these samples. Cesium 137 was detected in four of the six samples.with an average activity of 284 pCi/kg (dry weight) and a range from 98.4 to 756 pCi/kg (dry weight).
Cesium 134 was measured in two samples, one each from station 08 and 09. 7he average
[
activity was 106 pCi/kg (dry weight) and a range of 103 to 108 pCi/kg (dry weight). The -
highest readings for cesium-134 and cesium-137 were obtained from station 08 located 1.10 miles downstream in the North Anna River,148' SSE. >
Naturally occurring potassium-40 was observed in all samples with an average activity of 9865 pCi/kg (dry weight) and a range from 4760 to 18100 pCi/kg (dry weight).
Radium-226 was measured in all six samples with an average concentration of 1953 pCi/kg (dry weight) and a range of 1050 to 3830 pCi/kg (dry weight). Also naturally occurring, '
thorium-228 was observed in all six samples with an average concentration of 1134 pCi/kg O < dry weishi) and a -se < 416 m n20 gCuk (drx weight). Ca*58 -d 60 was
~
observed in one sample each with concentrations of 262 and 70.9 pCi/kg (dry weight) i respectively. The September samples were analyzed for strontium-89 and strontium 90.
There were no detections of strontium 89 in aquatic sediment / silt. Strontium 90 was measured in the control samples with an activity of 76 pCi/kg (dry weight).- Strontium 90 -
I was detected in the indicator samples with an average concentration of 101 pCi/kg (dry-
' weight) and a range of 52 to 150 pci/kg (dry weight). In the accompanying figures the 3
isotopes cobalt-58, cobalt-60, cesium 134 and cesium-137 are plotted for the sediment samples collected during 1989 at stations 08,09, and 11. All results are consistent with previous years.
- 2. Shortline Soil A sample of shoreline sediment was collected in April and September from station 09,2.2 miles upstream of the North Anna Power Station. The samples were analyzed by-gamma ray spectrometry. The results are presented in Table B-11.' The naturally occurring nuclide potassium 40 was measured in both samples at an average of 5910 pCi/kg (dry
!h t
weight) and a range of 4940 to 6880 pCi/kg (dry weight). Thorium-228 was measured at an average of 1125 pCi/kg (dry weight) and a range of 1040 to 1210 pCi/kg (dry weight).
i
. 31
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j O andi- 226 was ais-a-d in - -gies e mverage re g a ius ,Cag !
(dry weigM and a range of 1420 to 2070 pCWg (dry weight). Cesium 137, also a fission product was monitored in both samples with an average reading of 378 pCi/kg (dry weight) and a range of 218 to 537 pCWg (dry weight).
The two quarterly samples are usually composited and analyzed for strontium, ,
however the April samples were inadvertently disposed of. The September sampler were i ['
analyzed for strontium and there were no detections of strontium 89 or strontiuic.90 in
, shoreline soil.
D. Ingestion Exposure Pathway
- 1. Milk ,
4 The results of the iodine 131 analysis of milk samples are presented in Table B 12.
A sampie vas collected monthly from two stations. A total of 24 samples were analyzed. -
There were no measurements ofiodine 131 above the detection limits.
1
' The milk samples were also analyzed by gamma ray spectroscopy and the results
\
are also presented in Table B 12. A total of 24 samples were analyzed. Naturally occurring potassium 40 was measured in all of the samples with an average of 1320 l pCi/ liter and a range of 1110 to 1570 pCi/ liter. The fission product cesium 137 has been detected sporadically in recent years and the activity has been attributed to global fellom from past atmospheric weapons testing. However, cesium 137 was not 6teced in any l
milk samples. All other gamma emitters were below their detection levels. A quarterly composite was prepared from each of the two collection stations and analyzed for l strontium 89 and strontium 90. Strontium 89 was not detected in any of the samples i
monitored. Strontium 90 was detected in the eight samples monitored with an average -
level of 1.6 pCi/ liter and a range of 0.93 to 3.1 pCi/ liter. This is similar to activities determined in previous years and lower than the preoperational levels of 2.2 to 5.4 pCi/ liter.
2, Fish Aquatic blota can be sensitive indicators of radionuclide accumulation in the environment because of their ability to concentrate certain chemical elements which have radioactive isotopes. ~lhe results are presented in Table B 13. four samples of fish were collected from station 08, the discharge lagoon. These samples were analyzed by gamma 36
i i
< I l
i O rar srectroscoex and the natura>>x occurrin iseiore retassium-40 was reund in aii four !
samples at an average of 2065 pCi/kg (wet weight) with a range of 1760 to 2560 pCl/kg (wet weight). Cesium.134, a fission product, was observed at an average of 30.5 pCi/kg j (wet weight) and a range of 22.0 to 35.8 pCi/kg (wet weight). The fission product cesium-137 was measured at an average of 187 pCi/kg (wet weight)in all four samples with a range of 166 to 199 pCl/kg (wet weight).
i Four samples were also collected from station 09, se control location 2.2 miles j
upstream on Lake Anna. The same nuclides were detected by gamma ray spectroscopy. ;
Naturally occurring potassium 40 was monitored in all four samples at an average of 2115 l
pCi/kg (wet weight) with a range of 1660 to 2920 pCi/kg (wet weight). Cesium 134 was 4
measured in three of the four samples at an average of 33.8 pCi/kg (wet weight) and a range of 15.1 to 54.4 pCi/kg (wet weight). Cesium 137 was measured in all four samples at an average of 213 pCi/kg (wet weigh 0 with a range of 99 to 384 pCi/kg (wet weight). '
In the accompanying figures the fission products cesium 134 and cesium 137 are plotted for the fish samples collected at stations 08 and 09 from 1981 to the present. The ,
increase seen in 1985 was due to substantial primary to secondary steam generator problems experienced at North Anna. The subsequent decreasing cesium activities are due to repairs made to the steam generators and better liquid waste processing, thus reducing the effluent activities released to the environment.
k
- 3. Food / Vegetation Thirty five food samples were collected from five locations and analyzed by gamma spectrometry. The samples consisted of green leafy vegetables such as cabbage and t lettuce. The results are presented in Table B 14. Naturally occurring potassium 40 was monitored in all of the samples with an average activity level of 8768 pCi/kg (wet weight) and a range of 1790 to 21800 pCi/kg (wet weight). Cosmogenic betyllium-7 was detected '
in all samples with an average concentration of 1743 pCi/kg (wet weight) and a range of 278 to 5150 pCi/kg (wet weight). The terrestrial nuclide thorium 228 occurred in three of '
the samples at an average activity of 213 pCi/kg (wet weight) and a range of 160 to 283 - ,
pCi/kg (wet weight). Radium 226 was detected in three samples with an average activity of 907 pCi/kg and a range of 712 to 1260 pCi/kg (wet weight).
O
, 37
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O T8e iissien greduci cesium 132 was detected in ten ef the thirtx five samgies with an average activity of 110 pCi/kg (wet weight) and a range of 21.5 to 300 pCi/kg (wet l
l weight). In recent years cesium 137 has been detected sporadically and has been attributed '
to global fallout from past atmospheric weapons testing. These results are consistent with
{
those measured in previous years. '
\
i E. Direct Radiation Exposure Pathway
- 1. TLD Dosimeters '
Thermoluminescent dosimeters (TLDs) determined environmental radiation dose !
t rates and the results are presented in Table B 15. A TLD badge of four readout areas each i was deployed quarterly at 12 locations around the periphery of the plant. %e mean values of four readings (calibrated individually for response to a known dose and for intransit dose) are reported in this table. Individual measurements of external radiation levels in the '
environs of the North Anna site had an average dose of 5.8 mR/ standard month with a range of 4.0 to 8.4 mR/ standard month. The control station, No 24 had an average reading of 4.4 mR/ standard month with a range of 4.0 to 4.8 mR/ standard month. The highest dose was at station 01, NAPS Sewage Treatment Plant. 0.2 miles,42 degrees NE, with a reading of 7.8 mR/ standard month and a range of 7.5 to 8.4 mR/ standard month. '.
L Sector TLDs are deployed quarterly at thirty two locations in the environs of the North Anna site. Two badges are placed at each location. The results are presented in Table B 16. The average level of the 32 locations (two badges at each location) was 6.1 mR/ standard month with a range of 3.1 to 9.7 mR/ standard month. The thirty two control TLDs from eight locations showed an average reading of 5.3 mR/ standard month with a range of 3.8 to 7.1 mR/ standard month. Two of the badges were vandalized during the fourth quarter. Although a thorough search was made of the area the TLD's could not be located. The highest dose levels were at station SW 53 with an average level of 8.9 mR/ standard month and a range of 8.4 to 9.4 mR/ standard month. On one figure the
- results of the environmental TLDs are plotted from 1977 through 1985 in mR/ day. For 1986,1987,1988 and 1989 the results were plotted in mR/ standard month on a second
~
figure. For the period 1985 th'ough 1989, the external radiation levels have remained constant at approximately 0.2 mR/ day (or 6 mR/ standard month). He sector TLDs have been in use since 1984 and the results for 1984 through 1986 are plotted on the same two O ii Sures discussed above. He resuits of the secter TLDs are co garabie io the resuits or the environmental R.Ds.
40
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41
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E V. CONCLUSIONS 1 i
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1 l
V. CONCLUEIONS O The results of the 1989 Radiological Environmental Monitoring Program for the North -
Anna Nuclear Power Station have been presented. De following sections discuss each pathway individually followed by a program summary, t
Airborne Exnosure Pathway r
Air particulate gross beta concentrations of all the indicator locations for 1989 followed the 4
gross beta concentrations at the control location. The gross beta concentmtions were comparable to levels observed since 1982 except for a five week period in 1986 which was influenced by the Chernobyl accident. Gamma isotopic analysis of the particulate samples identified the gamma ,
emitting isotopes as natural products (beryllium 7 and potassium 40). There viere no measurements of fission products nor other man made isotopes in the particulate media during 1989 lodine 131 was detected at activity levels below the required lower limit of detection in three of the 607 charcoal filters analyzed during 1989.
A precipitation sample was collected eleven months during 1989 and analyzed for gross beta activity. All the gross beta activities were comparable to those measured in previous years.
O semi ###ico nosit - r ix ators == -i'ti# ie'en =#a'riti# - ^ii s - -
emitters were below their detection limits. Tritium was observed in two samples at an average level of 265 pCi/ liter.
Waterbome Exoosure Pathway No man made or natural isotopes were monitored in the surface water of Lake Anna except 1 tritium. The average tritium activity in 1989 at the waste heat treatment facility was 3725 pCi/ liter :
which is 18.6% of the reporting level for a water sample. In 1988 the tritium level was 3915 .
pCi/ liter, ne preoperational level was 150 pCi/ liter and has been rising since 1977. The tritium i level upstream of the site was 2850 pCi/ liter as compared with 3010 pCi/ liter in 1988, i The samples of stuface water collected by the Commonwealth of Virginia at the waste heat treatment facility had similar tritium results with a measurement of 4500 pCi/ liter. The upstream location had a lower activity of 150 pCi/ liter. No gamma emitting isotopes wce detected.
O 43
River water collected from the North Anna River,5.8 miles downstream of the site had an 0 average tritium level of 3749 pCi/ liter. The average tritium in 1988 had been 3925 pCi/ liter No gamma emitters were detected. -
Ground water from the environmental well on site contained no gamma emitters. There
'l was only one detection of tritium in ground /well water at 210 pCi/ liter which is a low crwironmentallevel, i t
Aountic PathwaX Sediment / silt samples provide a sensitive indicator of discharges from nuclear power i stations. The sediment from North Anna environmental samples indicated that two man made ,
isotopes were present. Cesium 137 was detected in four of the six samples at three locations.
During the preoperational period, cesium 137 was measured in samples of aquatic sedimentt however, additional man made isotopes appear to have accumulated. Cesium 134 was monitored in two samples. Sediment contamination does not provide a direct dose pathway to man.
The samples of shoreline soil monitored downstream of the site contained no cesium 134.
Cesium 137 was measured at an average of 378 pCi/ liter which is comparable to cesium 137 in :
sediment samples.
f]
Ingestion Pathway lodine 131 was not measured in any of the twenty four milk samples using the radlochemical separation method. Although cesium 137 has been detected occasionally in previous years and attributed to past atmospheric nuclear weapons testing there were no detections during l 1989. Strontium 90 was measured in all of the milk samples. The values wcre companible to the l levels in 1988 arid somewhat lower than preoperational years. Strontium 90 from those years is l attributed to past atmospheric nuclear weapons testing. No strontium 89 was detected in any of the milk samples. Naturally occutting potassium 40 was measured in all the milk samples at normal
-l environmentallevels. .
Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples in 1989 showed the presence of the man made isotopes cesium 134 and '
cesium 137. These isotopes were at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1987 and 1988. Only cesium 137 was measured in
! g preoperational environmental fish samples. Due to primary and secondary steam generator LJ 44
3 i
l l
problems experienced at North Anna during 1984/1985, a build up in activity levels both in O
enucets and nsh did . Renaim m the sicam gen-ame and ben-en uid wasic p-eseg l have reduced these activity levels in effluents and thus decreased activity levels are now being )
observed in the fish. The average level of activity in 1989 of cesium 134 was 3.2% of the }
reporting level and cesium 137 was 10.0% of the reporting level. l Vegetation samples contained the man made isotope cesium 137. The cesium 137 activity I levels in 1988 and in preoperational samples were statistically shnitar to the 1989 level. j Direct Exnosure Pathway The direct exposure pathway as measured in the environment of the North Anna site by ;
i thermoluminescent dosimetry has remained essentially the same since the preoperational period in 1977 at 6 milliroentgens per month or 0.2 milliroentgens per day. The average dose levels monitored have shown a normal fluctuation about these levels which are less than the estimated
(
whole body does due to natural terrestrial and cosmic radiation and the intemal dosage from natural ,
radionuclides. ,
Pmuram Conclusions The results were as expected for normal environmental samples. Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant ,
dose consequence.
As a method of referencing the measured radionuclide concentrations in sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in Technical Specifications. These concentrations are based upon 25% of the annual dose ,
commitment recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is Reasonably Achievable." Based upon the evidence of the environmental monitoring program the station is operating within regulatory limits. Thus, no unusual radiological characteristics were observed in the environs of the North Anna Nuclear Power Station in 1989. :
p O
45
-s- _ , y a a. -m-m-,,---. o.ua2mLs--.m& 4AAnou--4-= A-as..Ms n.6*aM.ss-n---. a nsa- , , , a- - +.
- sea 4. RHA --a-heo 4 , 'e--+
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VI. REFERENCES '-
1 ,
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-n, - .e~r.,--. - --+., -e ,
VI. REFERENCES O
- 1. !
United States Nuclear Regulatory Commission, Regulatory Guide 4.8
" Environmental Technical Specifications for Nuclear Power Plants". December, i 1975. !
- 2. Virginia Electric and Power Company, North Anna Power Station Technical '
Specifications, Units 1 and 2. L I
- 3. NUREG 0472, " Radiological Effluent Technical Specifications for PWRs", Rev. 3. ,
l March 1982.
- 4. United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1, l
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for i
- the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October,1977. ,
- 5. USNRC Branch Technical Position, " Acceptable Radiological Environmental i Monitoritig Program", Rey,1. November 1979. 7 1
1 l
O 47
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O APPENDIX A i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
.1989 1
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O O O
\ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
NORTH ANNA POWER STATION DOCKETNO.50-338/339 IDUISA COUN'lY.VIRGINTA JANUARY I to DECEMBER 31.1999 ANALYSIS AND IDWBt IJMrr DE!DIUM OR PATHWAY TUTALNUtest OF A11MDK'AlI]EIDCATX]h5 1DCATMJN WIIIIBIGIE3T hEAN NURGBHL OF SAwtID OF ANALYSE 5 DETTff10N CONDtOL LOCATION NONROUTHE DE!AN NAW WAN (UNTTOF WA$t4tBENT) PUtR)stDED GJDMI) RANGE WAN Rf70RTED DESTANG AND DetR' TION MANGE RAWE WA300tFnGNTS Preciphattes Menshly (ICa/her)
Gmes Beta 11 4 1 5(11/11) 01A 0.2mi NE 5.5(11/11) NONE O (1.8-14) (1.814)
Gamma 2 '
(Semi-Annismily)
Be-7 2 70 -(Of2) NA NA NONE O y Tnamen 2 2000 265(2/2) 01 A 0.2 mi NE 265(2/2) NONE O (240-320) (210-320)
(I) LLD is luwa lumeI.ofNovember descamm as def med ar=1 sequeral m USNRC Branch Techcal thiamm on an Acceptable RadWtJ Enveswunental Mometweig INogram. Mcwsiim 1979 I
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ ~ . . . _ . . . . - - , . . , _ . . _ _ . _ . . _ . . . . . . , _ , , . . . . .
O O O RADIOLOGICAL, ENVIRONMENTAL, MONITORING PROGRAM
SUMMARY
NORTH ANNA POWER STAT 10N DOCKET NO. 50-33R/339 LDUISA COUhrTY. VIRGINIA JANUARY I no DECEMBER 31.19r7 ANALYSIS AND IDWER LIMfT EDIUM Oct PATHWAY TUTAL NUMBBt OF AlllNDICATDSt IDCATIONS NUM90t (W SA 6 LDCATION wtTM umM SEA *4 CONTROL LOCAllON OFANALYSES DETECi1ON MFAN NONROUT1PE:
(UNTT OF EASURIMhrr) NAME MFAN MF4N PGtRIItED GJD)D) RANGE DITTAMT A NO DetFCT10N Itf700tTfD RANGF RANaE EAstatFwn Soli Gamma 12 (pCiAg (dry)
K-40 12 100 197I80 1/13) 23 0.93mi SSE 25000(13) 2840(18)
(3370-25000) -
0 Cs-137 12 ISO 453(11/11) 05 4_20mi NNE 9.84(1H)
(90.3-984) -
-(On) 0 Ra-226 12 100 193501n1) 22 1.00 mi WSW 3730(13)
(1090-3730) -
1130(18) 0 Th-228 12 30 1391(11/11) 22 1.00 mi WSW 3020(13) Sl4(In)
(447-3020) -
0 Sr-P9 12 200 40(11) NA (Ammmmp y) -
NA -(OH) 0 St-90 12 40 82.7(10/11) 05 4.20mi NNE 170(Ill) -(OH) 0 (Annually) (46-170) -
(1) 11D is hmer I'rogram. twmt Revn=e of eleiccine I. Novemtxx 19FAas ekfmed and requwal in USNRC Brarah Tcchical thinum <m an Accxptable RadmApcal Erwmmmemal 14mseivmg
o O O RAIMOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
NORTH ANNA M)%T.R STAllON DOCKETNo. 50-338/339 1DUISACOUNTY VIRGINIA JANUARY I ete DECEMBER 31.1999 ANALYSIS AND IDWBt LIMfr EDetJM OR PATHWAY TUI'AL NUMMR OF AIL INDICATOR IDCAllONS Mmeest CS 5AhrIED IDCATX23 Wml HEIE3T MAN CtWilt0L LOCAT3ON N OF ANALYSE 5 DETIC110N WAN NAME (tJNTTOF EASURDENT) PUtf0RDED EM WAN REPOftTID GlD)(t) RAteGE DtSTA* ICE A*8DN RANGE RAW WASURE1herTS Gremed/Well Water Gamma 4 (pcaser)
K-40 4 60 -(W4) N/A N/A NONE O Tntman 4 2000 210(I/4) 01A 210(IM) NONE O U River Water Gamma Il
<,caser)
K-40 11 200 673(t/8) 11 SJmi SSE 673(1/s) NOME O Trisimi II 2000 3750(11/11) 11 5A mi SSE 3~50(11/1I) NOME e (150s-4ees) (15epaeoo) 1 (1) w 11D is lowcr liogram. Revisam Iwnn (4 docctism I. November as def ied aruf sequered m USNRC Hranch Tcctwncal Ibsitum (m an h,4 Raindnga:al Envwtwnerwal Mimierweg 1979.
. - _ _ . , . - - . ~ ,_ _ _. .. _. , . _ ...._,_ . _ _ . . , _ _ _ . . _ . _ _ . _ .
's C (G
RAIMotAM;lCAL ENVIRONMENTAL MONITORING PR(M;MAM
SUMMARY
NORTH ANNA POWER STATION DOCKET NO.50-338/37)
IJOUISA COUNTY.VIRGINTA 3ANUARY I to DECEMBER 31,1999 ANALYSB AND IEWUtIE4rr 6M OR PATHWAY TUTALN OF A!1NDICATOR IMAT10N3 Mt, M OF SA!@ TID OFANALYSES f.DCATION WTTH nN MV NI_UCATR)as N TETBCTION WAN NAE EAN (tJNTTOFWASURFE.V D PBtR)R E D GlDH1) RANGE MFAN Rf708tTID DESTAMT AND OWtFCTKW PAMCE W AW WAstM6 Serface Weetr I-131 22 0.5 (pChimer) -(0(II) N/A N/A -(0(II)
- 0 Res=in Mumhbes -
Gemne 22 K-40 22 200 -(0(11) N/A N/A -(0(II) O Tnemen 8 2000 3725(4M) 8 1.1 mi SSE 3725(4M) 2850H/4) 0 (2700-5200) (2700-5200) (19804 300) s.n u
Serface Weser Genma 24 (pCWheer) suse sp6=
K4 24 200 g4) N/A N/A NONE O Tnemen 2 2000 2325(2/2) W33 (150450ny 4500(t/1) NOME O (I) t LD slower inna I.ofNewmber desetskm as definal arut rapani m USNRC Itranch TcAtuwal 5%nkm um an Accrptatde Maladogical Enwmmmereal Momerug th.grarn. Resiskm 1979
,- - , , - . , , , _ ._ . . ~ , , .. . ._ . - . - _ ._ ._ . _ _ - _. _. .. _ . .
O O O RADIGIAM;ICAL ENVIRONMENTAL MONITORING PROGRAM SSMMARY NORTH ANNA M)%ER STATION DOCKET No.50-33U3N EDUISA COUNTY. VIRGINIA JANUARY I so DECEMBER 31.1999 ANALYSIS AND IMMR IJMIT MEDIUM OR rATMWAY TMAL NUM OF All INDICATUdt LOCAT10NS LDCATION WfTH urusTT BE:AM NL%mIR OF SAD @ LED OFAMALYSES DETECTION MEAN OWIROL LOCATR)N MPeet,M (UNfT OF WASURFW P9tRJR W D NAME WAN MFAN Rt708tTT-D 01D)(1) RANGE UtSTANG ANDDIRRTwr4 RANGF R ANrF WAST tpFnsFW sed 6 ment Sees Gamma 6 (pCiAg (dry)
Be-7 6 200 -(0/4) 9 2.2 mi NW 398(IR) 394(1/2) 0 K-40 6 200 Il282(4M) 11 5.8 mi SSE 16150(7/2) 7030(2/2) 0 (5320-18100) '14200-18100) (4760-9300)
Co-58 6 150 262(1/4) 11 5.8 mi SSE 262(IR) -(Gr2) O Co 60 6 150 a
70.9(1/4) 8 1.1 mi SSE 7051/2)
W) -
0 Cs-134 6 150 108(1/4) 8 1.1 mi SSE 108(IR) 103(1/2) O Cs-137 6 18G 322(3/4) 8 1.1 mi SSE 427(2R) 170(1/2) 0 (98.4-756) (M.4-756) -
Ra-226 6 100 2048(4M) II 5.8 mi SSE 2985(2/2) 1765(2/2) 0 (1950-3830) (2140-3830) (13 4 2160)
Th-228 6 30 1098(4M) II 5.8 mi SSE 1600(2/2) 1207(2/2) 0 (416-1723) (1480-1720) (893-1520)
Sr-89 3 4.0 -(0(2) NA (AneseDy) -
NA -(fVI) 0 Sr-90 3 0.8 101(2/2) NA (Annually) NA 76(1/1) 0 (52-150) -
(I)
LID is lower imme l'hyram.Revesam of desectum I,Novemta 1979. as defmed and regenred m USNRC Brarah Tedmscal ihnam m sui AccqtsNe Raholig. cal Ew mmmersal lemenrmg
. . . . . _ . . . . . _ ._ ._ . . _ _ . - . _ _ _ . - ~ , , . _ . _ . _ . _ _ _ _ . _ - ,
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,- s O O U RAIMOLOGICAL INVIRONMENTAL MONITORING PROGRAM
SUMMARY
NORTH ANNAIUWERSTATION DOCKET NO. 50-338/339 LOUISACOUNTY VIRGINIA JANUARY I so DECEJWER 31.1989 ANALYSIS AND IEWER I.J!befT hEDRIM OR PATHWAY TUTAL PRJhEst OF NUMagtOF AI.1LNDICAT(X ll) CATIONS 1.IX'AT10N ETT1R N W_AN CONTWot.LOCAT10N SAbetID OF ANALYSE 3 DETFCTION MAM NONetolfitNF MADEs >EEAN MAN (UNfTOF hEASUREWNT) PERR)sthdCD (IlDMO RANGE R570RTED Dt3 TANG AND DWtR*nO4 RANrm mAgry ggFAStWWFT3 Mek I-131 24 0.5 -(0/24) N/A (pCinner) -
NA NOPvE O Comune 24 K-40 24 100 1320(24/24) 12 8.3 mi NW 1418(12/12) NOME O (1110-1570) (1320-1570)
Sr-89 8 5 -(Of8) N/A (Qumreerly) -
N/A NOME O Sr-90 3 0.8 1.60(8/8) 13 5.60mi SSW (Qumrectly) 2.0(4/4) NONE O (0.93-3.1) (1.3-3.1)
Fish Gamune 8 FCE4g(wen)
K 8 200 2065(4M) 09 2.2mi NW 2115(4M) 2115(4/4) 0 (1760-2560) (1640-2920)
(1640-2920)
Cs-134 8 40 30.5(4/4) 09 2.2 sui NW 33.8(3M) 33.8(3/4) 0 (22.0-35.8) (15.1 54.4) (15.1-54.4)
Cs-137 8 40 187(4M) 09 2.2sni NW 213(4M) 233(4/4) 0 (166-199)) (99 384) (99-384)
(I) L1D is lower Imme of desertum I% gram. Revisam 1. November 1979.as defecd and regiared in USNRC Hearx.h Tectancal Ibsnam em an AcapenNe Rain &sical Emstwwwemas Mienenrog
( _ . _ _ . ., -- . . - - - - - - - - - - ' ~~ ~~ ~~ '~ ~ '~~
L.
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M E CE A 'A 37 4 0 3( p ER M2 31 6 o A CK D 92 1
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O i RADIOLOGICAL ENVIRf)NMENTAL MONITORING PROGRAM
SUMMARY
NORTH ANNA POWER STATION DOCKETNO.50 33tV339 IDUISA COUNTY. VIRGINIA JANUARY I se DECEheER 31.1989
{ ANALY3tB AND LOUBtIJMrr DEDIUM OR PATWWAY TUTALN OF A11BIDEATIM IDCATIONS IDEAIEN( WITE MEME3TREAN nut 0 DER OF SAletED OF ANALY3E5 C04T110E,t OCAT10N NOMm0UTWEE OETECTION R4 NAW_ DEMN (UMfT OF RG!A.RIREhENT) PERRRtED GIDHT) DEiAM mgestT1-D RANGE DtTTA88CE AND DRFCTWW RANGE RANGE 9E%SUqtEnC14TT Direct R e h Gamme Dese 48 9.2 5 3(44/44) 61 0.2 mi NE 7.8(4/4) 4.4(4/4)
(mR/ sed.mondi) (4.0-8.4) 0 (RegularTIDs) (7.5-8.4) (4.04.8)
Direct Radlettes Gemme Dese 12 0.2 6.0(11n I) 01 0.2 mi NE (mR/ sed.Dennah) 8 3(111 ) 4.3(111 ) 0 (4.5-8.7) -
(AsummelTIDs)
Direct Ramatise Gamwee Desc 286 0.2 6.1(254/254) 21153 030mi SW m (mR/ sed Mesuh) 8.85(W8) 5.3(37/32) 0 on (3.1-9.7) (8.4-9.4)
(h*= TIDs) (3.8-7.1) 4 (1)
L1D is h=cr Program. Revnemlame1.ofNovember deacctxm 1979. as dermed and requad in USNRC Brarwh Tecitrwcal Ihwam em an AccepesNe Rabice,ical R._aet fi_._,
s-.."- u4 4.-&N-wAon4-a ,A Ae <--+e-emam ,s am 4--m'-a= = = -w - -,n =
ea-A"w-== =w-+-- w "a s a kwnv~~ > w e.,mann-w-w so4--M-aa w w s-.4 a'- s- ' =
m a A 1
1
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1, i l i
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i I
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1
)
i
-l !
4
't APPENDIX B DATA TABLES 98 59
.O
- ! "U IiN
~
t H!! -
Hl! !5H g HH Hi !sH
,l =
HH HH 9H !
q i l
O jill: 5H5 Hh hH !
et s a l l H55 HIS 5HI Y
i p .
?m IRB hH jd 11 l
HH HH' hH i 111 o i l := mi i ul t i
o sing e is
. I ass 60
O O O TABLE B.1 (Page 2 of 4)
NORTH ANNA-1989 CONCEN IRATIONS OF IODINE-131 IN FILTc2 RED AIR '
pCi/m312 Sigma 1989 COLLECTION DATE SI 02 03 04 05 OSA 06 07 21 22 23 24 APRIL 04/04-04/11 <.01 <.009 <Al <.01 <.009 < 01 <.008 <.01 < 02 <.01 <.006 <.006 04/11 04/18 <.006 <.007 <.007 <.007 <.005 <.008 <.006 <.009 <.007 <.006 <.006 <.005 04/18 04/25 <.01 <.02 <.01 <.02 <.02 <.02 <.02 <.006 < 007 <.01 <.006 <.00s 04/25-05N2 <.007 <.006 <.02 <.007 <.006 <.008 <.007 < 005 <.006 <.005 <.006 (a)
MAY 05M2 05/09 <.01 <.01 <.02 <.01 <.01 <.01 <.01 05/09 45/17 <.01 <.02 <.01 <.GI <.01
<.01 <.007 <.006 <.007 <.006 <.009 <.009 < 01 e 05/17 05/23 <.0 % <.006 <.01 <.01 <.01 <.01
" <.004 <.01 <.01 <.006 <.005 <.01 I 05/23-05/30 <.007 <.006 <.005 <.009 <.006 <.006
<.007 < 02 <.005 <.01 <.004 <.005 <.005 <.005 <.007 <.005 i
- it1NE 05/30-06dO6 <.02 <.01 <.01 <.01 <,01 <.01 <.006
<.02 <.01 <.01 <.01 <.01 <.01 06dOH16/13 <.008 <.01 <.01 <.009 <.01 <.01 06/13-06/20 <.007 <.006 (b) - <.009 <.007 <.01 <.01
<2'38 <:.005 <.006 <.005 <.004 <.006 <.007 06/20 06/27 <.007 <.006 ' <.007 <.009 <.01 <.000
<.006 <.005 <.006 <.006 <.006 <.005 <.007 <.008 <.009 (b) r.. % == sample h 4
. . _. . . . . . . - _ ~ , _ ._. , . _ . . . . . _. _ .._ _ . . . . . . . _ _ _ . _ _ _ , . _
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63
~. . - . - .-. . - . _- -
O O O TABLE 8-2 (Page 1 of 4)
NOR7M ANNA - 1989 CONCENTRAllONS OF GROSS BETA IN AIP. PAR'llCULATES 1o 3pcir.33 t 2 sisen COLLECTION 1989 ,
DATE 01 02 03 04 e5 AVERAGE GSA e6 47 21 22 23 24 1 2 Ed. !
JANUARY OIA)341/10 4817 4717 4916 3916 451 6 4016 3716 4315 441 6 3016 4516 2915 2614 40116 01/10 41/17 2715 3015 42 i 6 4718 3316 331 6 3516 3115 01/17 41/24 Mi6 3215 4216 3816 4216 3115 2014 35115 5118 3516 3516 3716 %16 4116 2415 I
01/24 41/31 '4016 4516 4116 47i6 3916 5410 42 16 1814 Mi l7 4916 39t 6 4716 3316 3916 431 11 FEBRUARY 01/31 42/07 4316 4416 3416 3015 3817 3916 e 250140(a) 4316 2615 4216 32.1 5 d i; 02/07 42/14 .3916 4316 2516 4317 140120 (a) 291 6 3516
- 1 :*
3416 4016 1915 3916 2415 2214 33118 02/14 42/21 341 6 2816 4016 3617 39 17 3316 3916 2315- 4216 221 5 221 4 33115 02/21-02/28 X16 331 6 2416 3716 66i13 5919 3816 391 6 1915 3316 331 6 2214 ~37128 MARCH 02/2843/14 (b) 2212 2513 3214 1812 7718 (c) 2814 2813 2513 14 12 03/14 4 3/22 331 6 2615 2815 361 6 2913 1513 131 2 27134 361 6 3017 331 6 2515 16 i 5 3516 03/22 4 3/28 4417 2626 67 111 331 6 3116 3416 2615 22 5 1213 28117-3316 2315 371 6 3316 2014 34 125 Average 38 i 14 35 i 17 33 i 16 i 2 s.d.
37 i 16 48 i 36 39 i 19. 35 i 9 37 i 15 25 i le 39 i 11 27 i 12 21 i 14 37 i 26 ,
(a) Elevated result due no low sample volume; ruis included in averages.
(b) Several collecake dates 02/27 03/14.'
(c) Wilied by a second count.
. _ . . - . . - m. , _ , ,. __ _ . . . . ~ , .,,_ , . , . _ . , . cun
O O O TABLE B-2 (Page 2 el4)
NOR711 ANNA - 1989 CONCENTRA"IlONS OF GROSS BETA IN AIR PAR 71CULATES 10 3pciAn3 2 s.sm.
COLLECTION 1989 DATE SI 82 93 84 SS AVERAGE
'95A 46 07 21 22 23 24- i 2 s d.
APRIL 03/pt44A)4 321 6 2815 3716 181 3 31 i 6 3016 24 t 5 3015 2115 35 6 2515 04S444/II 4016 2515 3917 2015 2816 261 6 1514 20 14 28 112 sei/Il-04/18 401 6 2715 2815- 2215 2615 21 5 1914 26115 4417 351 6 351 6 3416 1815 381 6 2015 04/18-04/25 (a) 3116 72 112 3517 65 111 76 114 52 111 4016 3616 2014 32118 2115 2315 51 110 2215 381 6 41 tic 3416- 2414 45136 04/25 45/02 2718 271 5 2315 1515 1714 2315 1114 2215 1815 (b)- 21110 MAX 05#2-05/09 121 4 1915 1815 1615 1915 1515 1114 m 05)D945/17 1014 1514 1515 1915 1215 1914 714 1815 1518
- 1614 1414 20i5 2214 151 4 1114 05/17-05/23 1716 20i6 2017 43 113 2718 714 1414 1414 1418 251 7 2416 -34 112 1016 1115 05/23 45/30 1814 2615 2115 67 119 2114 3116 2815 191 4 1416 2116 22119 1314 2214 2214 2415 26127 kilNE, 05/304646 44 112 1615 1515 2515 231 5 2915 1714 06/05 46/13 30 111 1415 191 6 1615 1415 .2015 814 2015 21118 191 6 12 15 211 6 1715 lb) 1115 06/1346/20 1815 2015 3917 321 6- 2015 1315 191 6 131 5 17 i ll 2816 221 5 261 6 2015 1915 06/20 46/27 1015 1215 2217 2116 201 6 13 i 5 1615 251 6 2015 24113
^2016 131 5 1916 1415 1616 1618 Average '25 124 24 136 27 121 31 135 27 132 26 121
' i 2 s.d. 22 120 24.114- 17 116 22 122 29 118 1917 24 i s
- (c) Several stations results elevated due to low air volume.
(b) Sampler malfunctum; no sampic available.
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l > ' ; .
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57 G 1 2 . 5 831 .3 G m
11719 1791 11181 AJ R s 11111 1111 11111 i E 54490 2575 35730 R 22112 2123 V 2 22112 2 _
A i O 4 58555 6544 44443 6
1 2 1 111 1111 11111 1~ _
15701 1 141 69295 0 24122 2122 1 1211 2 r.
3 3
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2 i11i1 1111 11111 i _
36092 8164 80239 9 _
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6 1
2 56675 6666 . 66555 2 11111 i111 11111 1 52189 0441 241 16 3 23221 2133 32111 2 1
S 1 E 1 64555 6)65 b 56556 7 2 11111 1(1i 9 _ 11111 i A 73123 40 L
U 21111 0<21 1 29842 11112 6
1 ,
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9 A 1 8
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) T s 65565 6656 1 e
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E 3 o N B 32 9 15875 11111 L e g AN S Sm 32122 7568 2122 59559 23212 5
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75249 5853 96532 6 22122 3133 22123 2 7 r 15 3
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0 11111 i111 11111 i
, 96580 6599 71202 1 3 12112 2122 33111 e 2 l p b .
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TA;LE C-3
&aec 3 of 3)
NORTH ANNA-IM9 CONCE!GRAT10NS OF STRONI1UM 89S0 AND GAMMA EMITTERS
- IN AIR PARTICULATES 0 3pcihn3 2 2 siyne FIRST QUARTER SECOND QUARTER . THIRD 4)UARTER STATION NUCLIDE 01/03 44/04 FOURTH QUARTER AVERAGE 04/04-07S4 (b) 07/04-10 S3 100441S3 + 2 s.d.
STA 21 Sr-89 (a) <2 Sr-90 (a) (a) -
(a) <04 (a)
' Be-7 I3.8 i 7.6 31.6 i 10.6 (a) -
K 40 40.1 i 15.2 44.6 i 9.9 32.5127.2 23.6111.9 < 40 < 50 Co40 <1 <1 13A i 6.2 18.5 i I4.4
<1 < 0.8 Ru-103 <1 <1 <2 Cs.134 - <1 <1 -
<1 <1 < 0.7 Cs-137 <1 <1 -
<1 < 0.7 n-228 <2 <1 <2
<1 -
STA-22 Sr-89 (a) <2 St-90 (a) (a) '
(a) <0A (a)
Be-7 48.219.0 44A i 11.4 (a) -
K-40 293 i 5.9 393 i 13.0 403 i16A 21.8 i 9.5 < 20 . < 70 Co40 <1 < 40 21.8 i 9.5 '
<1 <4 <1 Ru-103 <1 <1 -.
y Cs-134
<7 <2
<I <1 <4 o Cs 137 <1 <I'
<1 <5 <1 n-228 <1 <2 < 10
<2 -
STA-23 Sr.89 (a) <2 Sr-90 (a) (a)
(a) < 03 . (a)
Be-7 25.918.6 48A 19.1 (a) -
K-40 < 20 34.9 i 9.1 36.0 1 103 363 i I8.5
< 20 < 10 < 20
~
Co-60 <1 < 0.8
< 0.9 <1 Ru-103 <1 . <1 < 0.9 Cs-134 < 0.8 <1 .
< 0.8 < 0.7 Cs-137 < 0.9 < 0.8 < 0.9 -
n-228 < 0.6 <1
<I <1 <1 1 <1 -
STA-24 Sr-89 (a) <2 Sr-90 ' (a) (a) '
(a) < 0.2 (a)
Be-7 26.5 i 63 46.2 i 9A (a) -
K-40 < 20 53.2114.9 37.2 i lI.6 40.8 i 23.1
< 20 293 i 16.2 Co40 < 0.7 < 20 293 i 16.2
<1 <1 <2 Ru-103 < 0.8 <1 .-
Cs 134 < 0.7
<2 <2 -
<1 <1 <1 Cs 137 < 0.6 .<1 .
n-228 < 0.8
<1 <1
<2 <2 <2 i All othergamma eminen were < LLD.
(a) Strontium 89S0 performed annually.
(b) Several stations had varied colketion dates.
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O O. O-TABLE N-5 NORTil ANNA - 1989 CONCENTRATIONS OF GAMMA EMITTERS
- IN SOIL .
pCiAg 12 Sigma COLL STATION DATES Sr-89 Sr-90 Be-7 K-46 Cs-134 Cs-137 Ra-226- Th-228 ;
O! 07/19/89 < 300 < 60
- i
< 500 15100 1 1500 < 50 90.31 43.8 2590 1 560 17601 180 02 07/19/89 < 200 52125 < 300 88701 890 < 30 784 78 10901440 447 1 45 03 07/19/89 < 100 % i19 < 400 5030i 500 < 40 4561 46 1310 i480 579 i 58 04 07/19/89 <100 91124 < 400 3600 1: 370 < 40 8061 81 13501580 6161 62 05 07/19/89 < 200 170140 <500 13700i 1400 < 50 9841 98 18001590 1180i 120 OSA 07/19/89 < 200 78i46 <500 9170i 920 < 40 618i 62 16901490 1930i 100 06 07/19/89 < 100 46i24 <500 91801 920 < 50 3231 50 2350i580 23601 240 07 07/19/89 < 100 68123 < 300 - 33701 340 < 30 125 i 14 1440 1350 -1420 1 140 21 07/19/89 < 200 - 631 27 < 300 10700i 1100 < 30 375 i 38 I3401380 599 i 60 22 07/19/89 < 200 921 35 < 400 141001-1400 < 40 1511 39 3730 1 540 30201 300 23 07/1949 < 200 711 27 < 400 250001 2500 < 40 2761 34 25901460 22901 230 24 07/19/89 - < 200 . < 40 < 400 28401 310 < 30 < 30
. 1130 1 480 Sidi Sti +
Average '82.7 i 69.9 i 2 s.d. 19962 i 12713 453 1 699 1868 i 1592 1388 i3726 All wher gamma enntters werc < LLD.
4y ~. m - - - , 4 . he.-, ,. .- ,. . ,3%.,, , . * . w -. E--ww
O O O TABLE B4 NORTH ANNA - 1989 CONCENTRATIONS OF 57RONTIUM, TRIT 1UM AND GAMMA EMrITERS' IN GROUND (WEIL WATER pCillieeri2 Sigma COLLECTION DATES H -3' Sr-89 S r-94 se 7 K.4e 3 333 Be-I4e Th-228 STATION elA 03/28189 < 120 (a) (a) < 30 < 60 < 0.2 <5 <7 07/04/89 < 100 <2 < 0.6 < 30 < 50 <03 <7' <5 10m5/89 210280 (a) (a) < 30 < 40 < 0.2 <10 <5 01/03/90 < 100 (a) (a) < 40 < 100 <0.2 <7 <g u Average 21e i 80 w t 2 s A.
! l 1
4 All other gamma emitters were < L1D.
(a) Strontium-89hd analyses performed only on second quarter sample.
..uim. , .y--w y - * . , - , = , - , ,. , ,A. . .,y... g e 4 +r-- .g .=3m..g e y- i-,.gg., ,p., q.,w ,
TABLE B-7 NORT11 ANNA - 1989 CONCENTRATIONS OFTRTITUM.STROffilUM AND GAMMA EMITTERS
- IN RIVER WATER pCD112 Sigma COLLECTION DATES S r-89 Sr-9e H-3 Be-7 K-44 I-131 Cs-137 Ba-144 Ra-226 Th-228 STATION - 11 01/13/89 (a) (a) 54001 100 < 30 < 60 < 03 <4 <6 < 70 <6 02/16/89 5840i100 < 30 < 70 < 0.4 <4 <6 < 80 <6 03/21/89 4100i100 < 30 < 60 < 0.2 ' <4 <7 < 80 <7 04/01/89(b)
. 05/11/89 <2 < 0.5 4000i 100 < 40 < 200 < 10 .<5 <8 < 90 ' <7 06/15/89 <2 < 0.5 33001100 <40 < 60 < 03 <4 < 10 < 90 -<7 07/21/89 1500i100 < 40 < 60 < 03 <4 < 10 < 90 <7 08/17/89 29001100 < 20 <50 < 03 <3 <6 < 90 <5 09/12/89 25001200 < 30 < 50 < 10 <3 <9 < 70 <5 10/11/89 35001100 < 40 < 100 . < 30 ' <5 < 15 < 70 <7 11/16/89 3600i200 < 30 67.3126.6 < 03 <3 < 10 < 60 <5 12/07/89 46001200 < 30 < 60 < 03 <3 <8 < 80 <6 Average 3749 i 2591 67.3126.6 12s4. -
1
- ' All other gamma cminers were < LLD.
(a) Sr 89/90 analyses performed on secorut quaner sampics.
(b) Sample not collected.
_ . . . . . _ - - - - - - - .. . - : . :-. _ -- .=: .
O O O TABLE B-8 NORTH ANNA - 1989 CONCENTRAllONS OFTRfrIUM STRON11UM AND GAMMA EMITTERS
- IN SURFACE WATER pCilliteri 2 Sigma COLLECTION H -3 I-131(a) Sr-89 Sr-94 Be-7 DATES K-40 ~ Cs-137 Ba-14e Ra-226 Tb-228 !
-~ ~
STATION - es 01/13/89 (b) < 03 (c) (c) < 30 < 60 <4 <7 02/16/89 < 03 < 90 <7
< 30 < 60 <4 <7 OV21/89 52001200 < 03 < 40 < 200 .< 90 <7 i
04SI/89 <6 <8 '< 90 <8 (d) 05/11/89 < 0.2 < 40 < 200 <5 <7 06/15/89 3100i100 < 03 < 30 < 60 <4
< 90 <7 07/21/89 < 03 < 10 < 100 <6.
< 40 < 90 <4 < 10 08/17/89 < 0.2 < 30 < 100 - <7
< 50 <3 <5 09/12/89 2700i100 < 0.4 < 30 < 50
< 70 <6 10(11/89 < 0.5 <3 <8 < 70 .<5
< 30 < 50 <3 < 10 11/16/89 < 03 < 30 < 70 <6
< 60 <3 < 10 12A7/89 3900i100 < 0.4 < 30 < 60
< 70 '<5
<3 <8 < 80 <7 M Average 3725 1 2245
- 12. s.d.
STATION - 49 01/13/89 (b) < 03 (c) (c) < 50
' . < 100 <5 < 10 02/1489 < 03 < 50 < 100 < 10 --
< 200 <6 < 10 < 90 03/21/89 43001200 < 0.2 < 30 < 70 <8 0401/89 <4 <6 < 80 '<6 (d) 05/11/89 < 0.2 < 30
< 60 <4 <8 < 90 06/15/89 1800 i 100 < 03 - < 40 <7
< 50 <4 < 10 . < 70 -
07/21/89 < 03 < 30 < 60 <4
<6' 08/17/89 < 03 - < 10 < 80 <7-
< 30 ' < 50 <4 <6 09/12/89 2500i100 < 03 < 30 < 50
< 80 <7 10f11/89 < 03 <3 < 10 < 70 <6
< 30 < 60 . <3 < 10 11/16/89 < 0.4 < 30 ' < 70 <7
< 50 <3 < 10 < 70 12/07/89 2800i100 < 0.4 < 30 < 50
<6
<3 <9 < 70 <6 Average 2854 i 2107 12s4.
Allother gamma emmers were < LLD. M, (a) 1-131 by radiochemistry
' (b) Analysis performed quarterly.
4:
(c) Analysis performed only with second quarter. ,
(d) Sampic rue collected.
- a t'" 8 '# ~
o o O TABLE B-9 NOR111 ANNA - 1989 CONCENTRA'llONS OF1RITIUM, STROrfi1UM AND GAMMA EMfITERS* IN SURFACE WATER pCi/literi2 Sigma - STATE SPLIT i
COLLECTION DATES H-3 Be-7 K-44 1-131 Cs-137 Ba-144 Ma-226 Th-228 STATION - W-27 01/15/89 < 40 < 60 ;
<2 <4 02/15/89 < 40 < 60 < 80(a) <4
< 20 (a) < 90 <7 03/15189 < 60 < 80 <4 < 30 - (a) < 80 <7 04/15/89 < 40
<5 < 50 - (a) < 90
< 50 <2 <3 < 10 05/15/89 < 40 < 60 <2 <3
< 30 (a) < 80 <6 06/15/89 < 80 < 90 < 500(a) <5
< 40 (a) < 100 <7 07/15/89 < 60 < 70 <4 <4
< 100 (a) < 100 < 10 06/15/89 < 50 < 50 <9 <3
< 40 (a) < 90 < 10 09/15/89 < S0 < 60 . (a) < 80 <6
< 90 <3 <6 . < 70 (a)
~
IW15/89 < SG < 50 < 100 < 10 .
<5 <4 11/15/89 < 50 < 60 < 03 <3
< 60 (a) < 70 <7 12/15/89 150180 < 70 < 100 < <5
< 30 (a) < 80 <7
< 30 (a) < 90 <8 STATION - W-33 01/15/89 < 60 < 100 <2 <5 02/15/89 . < 40 < $0 < 80 (a) <4
< 30 (a) < 90 <8 03/15!89 < 50 < 80 <4 <4
< 30 (a) < 80 <7 04/15/89 < 40 < 60 <4 < 50 '(a) < 80 <6 05/15/89 < 60 <3 < 40 _ (a) < 90 <6
< 200 <2 <5 06/15/89 < 90 < 200 < 600(a) <6
< 40 (a) < 90 <8 07/15/89 < 50 . < 80 .<4 < 100 (a) .. < 100 <9 08/15/89 < 50
<4 < 40 (a) < 80
< 50 <8 <3 <6 09/15/89 < 60 . < 90 <6 <5
< 60 (a) < 80 <7 IW15/89 < 100 . < 200 <8 <7
< 60 (a) <100 <7 11/15/89 < 40 < 50 < 0.4 < 100 (a) < 200 < 10 12/15/89 45001200 < 50
<4 < 40 (a) < 70
< 50 < <4 <6
< 40 (a) < 70 <6 Average 2325 i 6152 12 s.d.
All o!her gamma emitters werc < LLD.
(a) . LLD could not le met due so delay in reccipe of saniple inun the State of Vsginia.
~ .c. - - - . - . . ,-.. _- . _ _ _ - _ . - _ - - _ - _ _ -
O O O TABLE B-le VIRGINIA FOWER - NORT11 ANNA - 1989 CONCENTRATIONS OF GAMMA EMITIERS* IN SEDIMENTSILT pCdgi 2 Sigma STA 08 STA-99 STA-II STA-SS STA-99 STA-Il Average NUCLIDE e4/03/89 84/03/89 94/03/89 #9/12/89 99/12/89 09/12/89 12 Signia Sr-89 (a) (a) (a) < 300 < 600 < 500 -
Sr-90 (a) (a) (a) 52128 76i41 150140 92.7 1 102 Be-7 < 200 394i204 < 400 < 300 < 400 <500 3941 204 K 40 53201 530 4760 1 480 18100i 1800 75101750 9300i930 14200t140 9865i10552 Mn-54 < 20 < 20 < 40 < 30 < 40 < 40 -
Co-58 < 20 < 30 262 1 45 < 30 < 40 < 50 262145 Co-60 70.9 i ' I8.3 < 30 < 40 < 30 < 30 < 40 709118.3 Cs-134 1081 20 1031 25 < 50 < 30 < 50 < 60 1061 7.1 Cs-137 756 i 76 170i~25 11Ii 43 98.4127.0 < 40 < 50 284i 633 Ra-226 1170 1 370 13701 370 38301 600 1050 1 460 21601520 21401 650 -19531 2073 Th-228 416 1 42 893i 89 1400 2 150 776i78 1520i150 1720 i170 I13411025
- All other gamma emitters were < LLD.
(a) Strontium 89B0 analyses performed annually.
~
^ ^ ~
- ~
.- -- . ~ ~ -
O O O.
l l
l TABLE B-Il NORTH ANNA-1989 CONCENTRATIONS OF GAMMA EMITTERS
- IN SHOREllNE SOIL pCiAg i 2 Sigma i
STATION 4P STAT 10N419 AVERAGE NUClJDE 04M3/89 09n2/89 2 Sigma Sr-89 (a) < 400 St-90 (a) < 40 -
Be-7 < 300 < 300 -
K 4940 i 490 6880 1 690 5910 1 2744 Mn-54 < 30 < 20 -
y Co-58 < 30 < 30 -
Co-60 < 30 < 20 -
Cs-134 < 30 < 20 -
Cs-137 5372 54 218 123 378 i 451 Ra-226 ~ 20701 450 14201 300 17451 919 Th-228 1940 1 100 1210 i 120 '
1125 1 240 4
L All other gamma emitters werc < LLD.
(a) Strontium 89f30 analyses performed annually.
O O O l
TABLE B-12 (Page I of 3)
NORTH ANNA' 1989 -
CONCENTRAllONS OFGAMMA EMITIERS* MILK pCi/Ii 2 Sigma MONTH NUCLIDE STATION-12 STATION-13 l JANUARY Sr-89 <5 <5 Sr-90 0.93 i 034 1.3 + 0.9 K-40 13801 140 11201 110 i Cs-137 <4 <4 ;'
I-131 < 03 < 03 FEBRUARY Sr-89 (a) (a)
Sr-90 (a) ,.*
(a)
K-40 1360 i 140 d Cs-137 <4 1290t 130
<5 I-131 <02 < 0.2
-t MARCH Sr-89 (a) (a)
St-90 ' (a) (a)
K-40 1370 i 140 1I10i i10 Cs-137 <4~ <4 I-131 < 03 < 0.2 APRIL Sr-89 <5 <4 Sr-90 1.2 1 0.6 1.7 i 0.6 K-40 13701 140 13401 130 Cs-137 <4 ' <5. +
1-131 < 0.2 - < 03 A11 sahcr g.unma crmiscrs werc <LLD.
(4) Strimnaten 89fAl wulyscs grriormed qusictly.
.. _.2_.- _ _ . ____..1_ -
. .;-. , . _- . . -a ...-.. - _ _ _ . _ . _ _ _ _ _ . _ m.. _ _ . _ _ _ _ _ . _ _ _ _ _ . , _ _ _ _
- - - - - - - j TABLE B-12 (Page 2 of 3)
NORTH ANNA-1989 CONCENTRATIONS OFGAMMA EMrITERS* MILK pCilli2 Sigma MONTH NUCLIDE STATION-12 STATION-13 MAY Sr-89 (a) (a)
St-90 (a) (a)
K-40 14501 140 1230 1 120 Cs-137 <4 <5 I-131 < 01 < 03 JUNE Sr-89 (a) (a)
Sr-90 (a) (a) g K-40 14701 150 1170 1 120 Cs-137 <3 <4 I-131 < 0.2 ' <02 JULY Sr-89 <5 <5 Sr-90 1.6 i 0.8 1.9 1 0.9 K-40 , 14201 140 1150 1 120 Cs-137 <4 <3 1-131 < 03 < 0.3 AUGUST Sr-89 .- (a) (,)
Sr-90 (a) (a)
K-40 13201 130 13601 140 Cs-137 <5 <5-I-131. < 0.4 < 0.4
- All other gamma emitters were <LLD. ..
(a) Sanmtium 89f)0 analyses paformcd quarterly.
L- ~ --'~ -- ~- ~~ ^ - '^ ~ ~ ~ ~ ^ -
O O 0:
TABLE B-12 (Page 3 of 3)
NORTH ANNA - 1989 CONCENTRA110NS OF GAMMA EMITTERS
- MILK pCilli 2 Sisma i
MONTH NUCLIDE STATION-12 STATION-13 SEPTEMBER Sr-89 (a)
Sr-90 (a)
(a) (a)
K-40 15601 160 11401 110 Cs-137 .<4 <4 I-131 < 03 < 03 i OCTOBER Sr-89 . <2 <4 Sr-90 1.1 1 0.7 3.1 i13 K-40 15701 160 12701 130 co
- Cs-137 <4 <4 I 131 < 03 < 0.3 -
1 4
NOVEMBER Sr-89 (a).
St-90 (a)
(a) (a)
K-40 13401 130 1260 1 130 Cs-137 <5 <4 I 131 ' < 03 < 03 DECEMBER St-89 (a) '
Sr-90 (a)
(a) - (a)
K-40 1400i 140 1230i 120 Cs-137 <4 .<4 I-131 < 0.5 < 0.5 t
All other gamma emitters were <LLD.
(a) Strontium 89f>0 analyses perforr.cd quaractly.
, . . . . . . - . . . .: - - . . . - -a_ . - . _ _ _ - . , - _ _ - - _ ._ _,_ - . __-. - .:..
O O O TABLE B-13 NORTH ANNA - 1989 ,
CONCENTRATIONS OF GAMMA EMITIERS* IN FISH pCdg (wet)i 2 Sigram COLLECTION DATE STATION SAMPLE TYPE K-44 Co-58 Cs-134 Cs-137 01/19/89 08 25601 260 <7 22.01 7.3 190 i 19 04/13/89 08 21201 210 < 10 30.8 i 9.6 199 1 20 07/27/89 08 18201 200 < 10 35.8 i 14.7 194i 19 10 @ 8/89 08 1760 i 180 < 10. 33.5 i 9.2 166i 17 0
01/19/89 - 09 29201 290 - <6 54.41 5.7 3841 38 04/13/89 09 21401 210 <7 < 10 1281 13 07/27/89 09 1660i 170 < 10 31.8 i 9.7 2421 24 IIK9/89 09 1740i 170 < 10 15.1 i 7.8 99 i II Average 2998 i 895 12 s.d. 31.9124.6 20e .i 173
- ' All other gamma cmitters were <LLD.
- ^ * * . - - ~ - - - - - - - - - - - - - -
-a -----M-m.. .-- --s--
- 4.--i- *Ma.m.-.a -----m-e.ia12..
---.2--mw
TABLE B-14 (Page 1 of 2)
NORTH ANNA - 1989 CONCENTRATIONS OF GAMMA EMITTERS
- IN FOOD / VEGETATION pCi/kg(wet)i 2 Sigma COLLECTION DATE Be-7 K-44 1-131 Re-183 Cs-134 Cs-137 Th-228 Re-226 STATION 14 05/23/89 893i I85 64101 640 < 2G < 30 < 20 58.7 i 19.0 06/20/89 476i 143 5170 1 520 < 10 < 20 < 20
< 40 < 400 07/26/89 18601 340 113001 1100 < 20 < 30 < 400
< 40 < 50 < 20 08/l6/89 818i 173 11600 i 1200 < 30 < 40 < 400 '
< 10 < 20 < 20 09/20/89 34501 390 7850 i 790 <8 26.5 i I3.1 < 30 < 300 -
< 50 < 40 80.1130.2 ItV25/89 23801 280 1690i 370 < 20 < 40 < 60 < 700 1t/15/89 24401 330 < 20 70.3 i 20.6 < 30 9050 1 910- < 50 < 40 < 600
< 30 < 30 < 50 < 600 STATION 15
' 05/24/89 9911 195 6850 1 680 < 30 < 30 06/20/89 783i 197 < 20 < 20 ' < 40 4200 1 420 < 20 < 30 < 20
<$00' 07/26/89 12001 450 21800 1 2200 < 20 < 50 < 400
< 70 (a) < 80 < 40 < 40 08/16/89 1610i 360 19000i 1900 < 10 - < 50 < 40
< 70 < 800 09/20/89 19801 340 8420i 840 < 40 < 70 < 900
. <7 .< 50 < 30 < 40 10(25/89 20201 260 4420 1 440 < 10 < 30 283i33 12ile i 670 14001 270 < 20 < 20 . < 50 11/15/89 5130 1 510 < 60 < 40 < 20
<500
< 30 - < 30 < 600 STATION 16 05/24/89 618i 122 6890 i 690 < 40 < 29 < 20 06/20/89 883i 150 2730 1 270 ' < 20 < 30 < 300
< 10 < 20 . < 20 -
07/26/89 917i 493 11500 i'1100 < 20 < 30 < 400
< 50 < 90 < 40 08/16/89 41601 610 17700 i 1800 < 40 < 90 < 800
< 20 < 80 - < 60 09/20/89 27101 310 5460 1 550 < 70 < 100 < 10ile
<9 < 40 < 30 < 30 10(25/89 I170i ISO 3190 1 320 <8 '
< .10 < 20
< 70 < 600 11/15/89 2300 1 410 12700i 1300 < 20 < 30 - < 300
< 60 < 60 < 40 < 40 < 80 .< 800 All other gamma cmincts were < LLD.
i
_ , ~ . -
, 3 7 3 .,, r'-' - - - - - - -
-wv * ~w w-w r m-- * * ' ' - - - ~ ' - --w*- < =,*
o o O TABLE B-14 (Page 2 of 2)
NOR7H ANNA - 1989 CONCENTRA'I1ONS OF GAMMA EMITIERS* IN FOOD /VEGETA110N pCi/L g (wet)i 2 Sigma COLLECTION DATE Be-7 K-44 1-131 Re-le3 Cs-134 Cs-137 Tle-228 Re-226 STATION 21 05/23/89 278 i 56 1790i I80 < 20 <6 <6 21.515.4 < 10 < 100 06/20/89 999 i 100 89401 890 < 10 <9 <9 <8 < 10 < 200 07/26/89 12501 420 12400 i 1200 < 40 < 70 < 40 < 30 < 60 < 700 08n6/89 33701 550 9020 1 900 < 30 < 80 < 60 257i50 < 100 < 1000 09/20/89 21201 510 6620 i 680 < 20 < 80 < 60 < 60 <100 <1000 10/25/89 . 5150 t 510 74701 750 < 10 < 50 < 30 300133 1 % i 52 < 700 11/15/89 17601 210 200001 2000 < 50 < 30 < 20 < 20 < 30 <400
, STATION 23 s
05/24/89 497i 140 46401 460 < 20 < 20 < 20 106i19 < 30 < 400 06/20/89 886i 404 6360 1 660 < 10 < 60 < 60 <50 < 100 < 1000 07/26/89 I150i 350 9760i.980 < 20 < 50 < 30 < 20 < 40 7121348 08/16/89 1990i 240 73001 730 < 20 < 30 < 30 < 30 - 160139 7501402 09/20/89 - 1380 A 190 5410 i 540 <6 < 20 < 20 42.6 i 13.8 < 30 < 400 -
IW25/89 43001 470 74201 740 .<8 < 60 < 50 128 i40 . < 90 < 1000 -
I1/15/89 17201 210 14700i 1500 < 50 < 20 < 20 < 20 < 30 < 400 Average 1743 1 2332 8768 i 9967 110 i 191 213 i 126 907 1 682 12sd.
All mfict gamnia cmincts acre < l.l.D
_ _ . - ~ :------~--- " ~ ' - ' ~ - ' ~ ~ ~ ~ ~ ~
0 O O TABLE B.15 NORIH ANNA - 1989 DIRECT RADIAT.ON MEASUREMENTS- QUARTERLY & ANNUALTID RESUL'13 mR/ standard month 12 Sigma '
l
' STATION IST QTR 2ND QTR NUMBER 3RD QTR 4th QTR QUARTERLY 01/03/8941A)1/89 04/01/8946f29/89 06f29/8949/28/89(a) 09/29/89-12/29/89 ANNUAL TLD '
AVERAGE 07M148-07/04/89 01 7.610.8 7.5 i 0.4 7.5105 8.410.8 7.810.9 8.7103 02 4.6103 4310.1 4.2 1 0.2 5.2 i 03 4.6109 4.7 i03 03 4.1 1 0.2 4.210.2 4.1103 5.110.6 4.4 i 1.0 4.510.1 04 4.8103 5.010.2 4310.1 4.110.2 4.6 0.8 49109 05 5310.2 5.110.2 5.0 1 0.6 6.010.1 5.4109 5310.8 05A 5310.2 5310.6 5.0 1 0.2 4.8 i 0.1 oo
- 5.1103 5.6103 06 6.5 1 0 3 . 6.6103 7.410.9 7.710.7 7.1 i 1.2 6.9103 07 4.910.4 5.410.7 4.8103 6.1103 53 i1.2 '
53 i03, 21 5.810.1 5.4 i 1.0 5.810.4 5.010.1 5.510.8 5310.2 -
22 63 i 1.2 7.0103 6.9 i 0.4 6.I i 03 6.610.9 6.4 i 0.6 23 8.4 i 1.4 6310.2 6.0103 63103 6.812.2 7.410.1 24 4.8 i 0.4 4.710.2 4.0 1 0.2 4.2 1 0.2 4.410.8 43 i P.2 !
A verage 5.712.6 5.6 1 2.1 S A i 2.6 5.8 1 2.6 5.6 1 43 i 2 s.d. 5.8 1 2.6 1
Standard month = 30 4 days.
- 4) Several collecthsi daies were 06f29/89 U)/27/M9.
y g . ~ . . . =
g w ,- <e. .w; ,r-,.e-_
,, mm%__-,_ .
O O O TABLE B-I6 (Page I of 2)
NORTH ANNA - 1989 DIREf.T.RADIA'llON MEASUREMENTS - SECTOR QUARTERLY T1.D RESULTS -
mR/ standard month i2 Sigma STATION FIRST QUARTER SECOND QUARTER NUMBER eI/03-64/01 THIRD QUARTER FOURTH QUARTER AVERAGE 94/41-96/29 06/29-99/28 99/29-12/29 i 2 S.d.
N.1 7.2 i 1.0 5.2i 03 N-2 4S i 0.2 6.7 i 1.2 6.012.2 5.9 i 0.1 5.0 i 0.2 5.610.5 NNE-3 7.5 i A.4 5.0 i 0.2 5 A i 0.9 6.7 i 03 63103 73203 NNE-4 6.210.1 5.1 1 0.2 53 i OA 7.1 i13 NE-5 8.5103 4.610.1 53 i13 7.2103 7.510.9 8.010.4 NE-6 3 9 i 0.1 3.410.2 4.210.8 7.8 i 1.1 ENE.7 69103 4.8 i 1.0 4.1 i12 5A i 0.2 6.8 i 0.2 5.9 i 0.6 ENE.8 5A i 0.2 4.810.2 63 i1A E-9 4.8 i 0.2 4.810.1 5.010.6 83103 7.010.4 7.0103 6 9 1 0.1 E-10 5.6 1 0.2 5.510.2 5 A i 0.4 7.4i15 ESE.ll 6310.4 4.8 i 0.2 53103 6.010.4 6 3 1 0.9 '5.510.1 ESE-12 7.8103 6310.2. 6.1 0.9
' SE-13 63103 6.9 i03 6.9i13 6.910.2 5.210.9 5A iOA 5.1 i 1.0 SE.14 8A i 0.1 7.5103 7.5 i OA 53113 SSE-15 7.5 i 0.8 7.8103 7 9 i 1.2 SSE-16 6.2103 73 i 03 7.0103 7.0 i 1.1 5.210.1 4.6 i 0.2 53 i 0.4
, g S.17 8310.6 7.8 i 0.6 7 3 1 0.2 5.1103 5.1 1 0.6 S.18 4.6 i 03 3.110.6 8.110.2 7.9 i 0.7 SSW.19 3A i 0.2 4.110.0 3.8 i I A 8.5 i 0.2 73 i OA '8.110.2 SSW-20 5310.1 4310.2 7.610.6' 8.0 i 0.8 3.9 i 0.2 4.2 i 0.2 4 A i 1.2 SW-21 .9.110.5 83 i 1.0 9A i 0.4 SW-22 5.610.2 5.6103 8.4103 8.910.9 SW-23 6.4103 (a) 5.9 i 0.9 5.6 i 03 43103 5.1 i 0.2 SW.24 6.110.3 6.010.1 63103 5.5 i 1.2 6.1 1 0.2 .5.810.2 SW-25 69103 6.6 i 0.2 7.0 i IS 6.0103 SW-26 4S i 0.2 7.2 i 0.6 6.9103 5.4 i 0.4 5210.4 4310.2 -
WNW-27 5.5 i 0.1 4.8 i 0.2 5Ai03 5.110.6 WNW-28 5 J i 0.2 5.1 1 0.1 53 i OS 5.6 i 0.7 5 A i 0.4 4310.8 NW-29 S J i 0.4 7.8 i 0.2 7.2 1 0.2 5A i 1.0 NW-30 4.8103 7.6 i OS 7.9 i 1 A 43 i 0.1 5.1 i 0.2 4.0103 NNW-31 63iOA SA i 03 4.6109 NNW-32
.53i03 6A i 0.2 6.0 i 1 A 5.6 i 03 5.9 i 0.9 5.1 i 03 N-33 6.210.8 6.2 i 0.5 5.010.2 5.4103 5.6 i 0.2 6.6 1 0 3 - 6.210.8 N-34 6.6103 43iOA 4 A i 0.2 5310.1 NNE-35 7310.1 6.8 i 0.6 7A i 03 SA i 1S 7.5 i 1.1 7.4 i OJ Standard month = 3.4 days (a) TLD missing; tierough scarch made.
f y <. ,_. ,., , ,,
4 ...y , .. . - , . - a v -
_c __ _ ,3_____m, _ _ _y.__w_. m. ._ _ .. ..%
o o O TABLE B-16 (Page 2 of 2)
NORTH ANNA-1989 DIRECT RADMTION MEASUREMENTS - SEKNR QUARTERLY T1.D RESULTS 3
mR/ standard month 12 Sigma STATION FIRST QUARTER NUMBER SECOND QUARTER THIRD QUARTER FOURTH QUARTER
- I/03-04/01 e4/01-06/29 46/29-09/28 AVERAGE 99/29-12/29 1 2 S.d.
NNE-36 6.2 i OA 5 3 i 1.0 NE-37 8.2 i OA 5.6103 5.810.2 5.8 i 0.6 6.0 i 0.9 83 i1.8 8910.6 NE-38 3.9 i 0.2 43103 7.912.5 ENE-39 4.010.2 3.8 i 0.1 6.6 i 03 6.010.2 6.610.2 4.010.4 .
ENE-40 5.110.1 4Ai1A 6.2103 6410.6 E-41 4.810.1 4.510.2 7.1 1 0.2 6.510.2 7.110.2 4.7 i 0.6 E-42 5.6 i 0.1 5.8 i 03 6.4i03 6.810.8 ESE-43 5310.2 6.110.1 6.610.4 6.1 i 0.2 6 3 1 0.6 - 5310.8 ESE-44 6.7 i 0.2 6.9 i 03 -7.010.2 6.6103 7.0103 7.0103 SE-45 6.8103 6.1 i 0.2 6310.4 6.9 i 03 SE-46 8.7103 9.0 i 1 A 53103 . 6.2 i 1.1 79 i 0.7 8.51 OS SSE-47 7.1103 6.110.2 6.1103 8.5 i 09 SSE-48 5.2103 5A i 0.9 6.0103 63 1.1.0 S-49 5310.2 53103 5A i 03 8A i OA 8.9 i 0.4 8.2 i 0.4
< S-50 4.4103 4.8 i 03 7.61 OS 83 i 1.1 SSW-51 3.8 i 0.1 4.610.2 9313.0 9.0 i OA 83 i 0.1' 4.4 i OS co SSW.52 4.510.1 83 i 03 8 9 i 1.2
" 4.1 i C.1 4.210.2 SW-53 93 i 13 83 i 03 3.910.2 4.2103 SW-54 8310.6 83103 6310.2 5.210.2 5S i 0.4 8.8 i 0.7 WSW.55 6.6 i 0.2 5.8 i 03 (a) 5.8 i 1.1 WSW-56 53 i 0.6 6.110.2 6.110.8 6310.2 6.5103 6.010.2 7.210.2-W-57 7.810.1 7.110.2 7A i 03 63 i 1.0 W-58 5.1103 4.910.8 83 i 13 7311.0 WNW-59 5.8 i 0.1 49103 5A i 03 5.1103 6.2iOA 5310.4 -
WNW-60 5A i 03 6.010.6 43103 5.5 i 1.5 N W 5310.1 5.110.4 83i03 8.2iOA ' 8.2 i 1.0 7.611.1
~ 5.510.8 NW-F2 53103 53 t 03 ' 4.6 i D.2 8.110.6 NWW-63 63 i OA 6.2 i 0.5 4A i 03 5.1113 NNW-64 53 i03 5910.2 6.1103 6.1 i OA - 5.6 i 0.1 6.1 i 1.1 C-1 6.0103 4.9 i 03 4.8 i 0.6 5.7 i 1.2 5.2 i 0.2 4.910.1 C.2 5A i 0.4 5310.5 6.010.6. 53 i1.0 C-3 43103 4.6103- 6.010.7 5.710.8 C-4 39 i 03 3.810.1 4.210.8 4.6103 4310.6 - 4A i 03 C-5 5 3 1 0.2 4.1 i 0.2 5.110.6- 4310.6 5.0103' SA 10.7
- C-6 3 9 i 0.8 5.110.1 43 i0.1 5.0 i 13
- C-7 6.010.9 5.0 i OS 4.6 i 1.1 6.0 i 03 63103 7.110.1-C-8 6.510.2 6.1103 63 iOA 6.4 i 1.0 6.6 1 0.6 6.510.5 Average 6A i 2.8 5.9 i 2.6 i 2 s.d.
6.9 i 2.6. 6.0 1 2J 6.1 i 6.4 Standant month = 3A days (a) TLD missing; thorough scarch made.
4
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)
APPENDIX C l
LAND USE CENSUS - 1989 i
i i
,-l t
I d
.i O -3 I
I 88 }
i
j
-VIRGINIA POWER .
NORTH ANNA POWER STATION j ANNUAL RADIOLOGICAL ENVIRONMENTAL LAND USE CENSUS DATA FOR 1989 (CONDUCTED AUGUST 28 - 29, 1989) l NEAREST -
NEAREST SITE MILK MEAT' MILK VEG. GARDEN SECTOR' RESIDENT BOL'NDARY COW
- ANIMAL GOAT * >-500 Sq.Ft.
(km) (km) (km)' (km)- M (km)
~
N 1,43 1.40 4.02 2.62 ,
NNE 1.61 1.36 2.82 3.06 ,
NE 1.53 1.32 6.44 3.62 ENE 2.94 1.31 4.18 3.02 E 2.09- 1.33~ '5.23 3.46 I ESE 2.01 1.37 4.02 4.02 SE 2.62 1.41 2.62 2.62 SSE 1.81 1.47- 2.62 1.81 S 1.85 1.52 2.62 2.62 SSW 2.25 1.62 -2.49 2.25 SW 2.62 1.70 2.66 2.62 WSW 2.21 1.75 2.90- 2.90 W 2.66 1.71 3.22 3.22-WNW 2.90 1.64 6.84 4.43' NW 2.62 1.56 4.22 2.62
,. NNW 1.21 1.45 3.42 3.46
- Note: No milk cows or milk goats within a five mile radius of North Anna Power Station.
n ,
%gj 4
89
yA w1NiA POWER - NORTH ANNA POWER STATION ANNUAL RAD 101.OCICAL ENVIRONMENTAL LAND USS CENSUS NAP F Nk ,.
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- APPENDIX D
. SYNOPSIS OF ANALYTICAL PROCEDURES 1 I, I 4
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i l i 4 ANALYTICAL PROCEDURES SYNOPSIS
],v l
i Appendix D is a synopsis of the analytical procedures performed on samples collected for { the North Anna Power Station's Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPCO and Teledyne Isotopes and include those i recommended by the USNRC Branch Technical Position, Rev.1 November 1979. i i ANALYSIS TITLE EMjE i G ro ss Beta Analysis of S amples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Preci pita tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Airborne Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A n a l y si s o f S a m p l e s fo r Tri tiu m.. . ... .. . .. .. .. .. . .. .. .. . . . .... .. . .. . ... .. . .. .. . . . .. . . . . .. . .. ... . . . .. . .. . Water................................................................................................100 Analysis of S amples for Strontium.89 and 90. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Total Wa te r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Milk.................................................................................................101 So il and Sedime n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . m Organic S olids . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Air P a r t i c u l a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Analysis of Samples for Iodine-131.....................................................................105 Milk or Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Gamma Spectrometry of Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Milk and Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i Dried Solids other than Soils and Sediment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Fish.................................................................................................106 Soils a n d S e d i m e n t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Charcoal Cartridges (Air Iodine) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 i Airborne Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Environmen tal Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 96
--n O
DETERMINATION OF GROSE BETA ACTIVITY IN WATER SAMPLER
1.0 INTRODUCTION
The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved. One liter of the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size. After evaporating to a small volume in a beaker, the sample is rinsed into a 2 inch diameter stainless steel planchet which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps. O Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self absorption curves which allow for the change in effective counting efficiency caused by the residue mass, s I O 1 97
2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually represented on the . planchet, the background and the efficiency of the counting instrument, and upon self-absorption of beta panicles by the mounted sample Because the radioactive species are not identined, no decay corrections are made and the reported activity refers to the counting time. The minimum detectable level (MDL) for water samples is nominally 1.6 picoeuries per liter for gross beta at the 4.66 sigma level (1.0 pCl/l at the 2.83 sigma level), assuming that 1 liter of sample is used and that f gram of sample residue is mounted on the planchet. These figures are based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respe:tively. The MDL becomes significantly lower as the mount weight decreases because of reduced self absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoeuries per liter. These values reDect a beta counting efficiency of 0.38. t i O l i 98
GROSS BETA ANALYSIS OF SAMPLES
"} Air Particulates i
After a delay of five or more days, allowing for the radon 222 and radon 220 (thoron) ! daughter products to decay, the filters are counted in a gas flow proportional counter. An unused air particulate filter, supplied by LILCO, is counted as the blank. Calculations of the results, the two sigma error and the lower limit of detection (LLD): RESULT (pCi/m3) = ((S/F)- (B/t))/(2.22 V E) TWO SIGMA ERROR (pCi/m3) = 2((S/r2) + (B/t2))l/2 (2.22
/ V E)
- LLD(pCi/m3) =
4.66 (B1/2)/(2.22 V E t) where: S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Numberof minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) l l l l i O 99
I ANALYRIE OF SAMPLES FOR TRM - O i WEtt ! One of two methods is used. Each has the same measurement sensitivity. One method of ; tritium analysis is to count 8 ml of sample by liquid scintillation for 1000 minutes. The other ' method is to convert approximately 2 ml of water to hydrogen by passing the water, heated to its : vapor state, over a granular zine conversion column heated to 400* C. The hydrogen is loaded into ! a one liter proportional detector and the volume is determined by recording the pressure, j 5 The proportional detector is passively shielded by lead and steel and an electronic, ' anticoincidence system provides additional shielding from cosmic rays. l Calculation of the results, the two sigma error and the lower limit detection (LLD)in pCi/l: RESULT = 3.234 TN VN(CG B)/(CN Vs) J TWO SIGMA ERROR = 2((Co + B)At)l/23.234 TN VN/((CN VS)(Co B)) l 11D
.;] =
4.66 (3.234)TN VN(Co)l/2 (At / CN Vs) where: TN = tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/l VN = volume of the standard used to calibrate the efficiency of the 4 detectorin psia j Vs = volume of the sample loaded into the detector in psia
=
CN the epm activity of the standard of volume VN ! CO = the gross activity in epm of the sample of volume Vs and the detector volume B = the background of the detectorin epm At = counting time for the sample i O 100
l l 2 i ANALYSIR OF SAMPLES FOR STRONTIUM.89 AND .90 i O i
= !
l Stable strontium carrier is added to I liter of sample and the volume is reduced by { evaporation. Strontium is precipitated as Sr(NO3)2 using nitric acid. A barium scavenge and an ! iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium canier and a minimum of 5 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer St 90 activity. Strontium 89 activity is determined by l precipitating SrCO3from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber Sr low level beta counting. Milk Stable strontium carrier is added to 1 liter of se.mple and the sample is first evaporated, then ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as phosphate, then is dissolved and precipitated as SrN0 3 using fuming (90%) nitric acid. A barium chromate scavenge ; and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the O sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then ; precipitated as hydroxide, dissolved and re precipitated as oxalate. *Ihe yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr 90 activity. Strontium 89 is determined by precipitating SrC0 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with en 80 mg/cm2 aluminum absorber for low level beta counting. Soil and Sediment The sample is first dried under heat lamps and an aliquot is taken. Stable strontium carrier is added and the sample is leached in hydrachloric acid. The mixture is filtered and strontium is precipitated from the liquid portion as phosphate. Strontium is precipitated as Sr(NO3 )2 using ; fuming (90%) nitric acid. A barium chremate scavenge and an iron (ferric hydroxide) scavenge are then performed. Stable yttrium carrier is added and the sample is allowed to stand for a minimum of 5 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer Sr-90 activity. Strontium 89 activity is determined by precipitating O - 101 s
,n-. , ,n-..
I SrC03from the sample after yttrium separation. This precipitate is mounted on a nylon planchet i O >#8 is cever a -ith # 8o m 'e=2 aiuminum abso,be, fo,iew ieve, be,a coun,in,. Orcanic Solids i l A wet portion of the sample is dried and then ashed in a muffle fumace. Stable strontium carrier is added and the ash is leached in hydrochloric acid. The sample is filtered and strontium is 4 precipitated from the liquid portion as phosphate, Strontium is precipitated as Sr(NO3 ) using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition j of stable yttrium carrier and a minimum of 5 days period for yttrium ingrowth. Ytuium is then ! l precipitated as hydroxide, dissolved and re precipitated as oxalate. 'Ihe yttrium oxalate is mounted I l on a nylon planchet and is counted in t low level beta counter to infer strontium 90 activity, . Strontium 89 activity is determined by precipitating SrC0 3 rom f the sample after yttrium j separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting, Air Particulates Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by i evaporation. Strontium is precipitated as Sr(NO 3 )2 using fuming (90%) nitric acid. A barium scavenge is used to remove some interfering species. An iron (ferric hydroxide) scavenge is performed, followed addition of stable yttrium carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, dissolved and re precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium 90 activity. Strontium 89 activity is determined by precipitating SrC03from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 2 mg/cm aluminum absorber for level beta counting. Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume orpCi/ mass: - RESULT Sr 89 = (N/Dt BCA-B )/(2.22 V Y3 DFSR-89ESR 89) TWO SIGMA ERROR St-89 A )/At)l/2/ (2.22 V Ys DF
=
2((N/Dt+B C +B SR-89ESR 89) LLD St 89 = / 4.66((BC+BA)/At)l/2 (2.22 V YS DFSR 89ESR 89) 102 e
RESULT Sr 90 = (N/At B)/(2.22 V Y 1 Y2 DFIFE) TWO SIGMA ERROR Sr 90 =
/ (2.22 V Y1 Y2DF E IF))
2((N/At+B)/At)1/2 LLD Sr 90 4.66(B/At)l/2/ (2.22 Y Y
=
1 Y2IF DF E) i l i i - O i l I P f
- O .
f
~~
103
l q wheret N = total counts from sample (counts) at = counting time for sample (min)
= background rate of counter (cpm) using absorber configuration BC l
2.22 = dpm/pCi V = volume or weight of sampic analyzed
= background addition from Sr 90 and ingrowth of Y 90 BA BA = 0.016 (K) + (K) EY/ abs)(IGy.90)
Ys = chemicalyield of strontium
=
DF SR 89 decay factor from the mid collection date to the counting date for SR 89 Egg.g9 = cfficiency of the counter for SR 89 with the 80 mg/cm.sq. aluminum absorber i K ' / (NAt B C)Y 90(Ey.90 IFy.90 DFy.90Y1)
=
DFY90) the decay frator for Y 90 from the " milk" time to the mid count time , O EY.90 = emcieecx ae mueien-y 90
=
IFY-90 ingrowth factor for Y 90 from scavenge time to milking time
= the ingrowth factor for Y 90 into the strontium mount from the IGY 90
" milk" time to the mid count time 0.016 =
the efficiency of measuring SR 90 through a No. 6 absorber EY/ abs = the efficiency of counting Y-90 through a No. 6 absorber B = background rate of counter (cpm)
=
Yi chemicalyield of yttrium
= chemical yield of strontium Y2 DF =
decay factor of yttrium from the radiochemical milking time to the mid count time E = efficiency of the counter for Y 90 IF = ingrowth factor for Y 90 from scavenge time to the radio-chemical milking time O 104
9 ANALYSIS OF SAMPLFS FOR IODINE.131 O Milk or Water Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from the resin with sodium hypochlorite solution, reduced with hydroxylamine hydrochloride and extracted into carbon tetrachloride as free lodine. It is then back extracted as iodide into sodium bisulfite . solution and is precipitated as palladium iodide. The sodium bisulfite solution is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet t for low level beta counung. The chemical yield is corrected by measuring the stable lodide content of the milk or the water with a specific ion electrode, i Calculations of results, two sigma error and the lower limit of detection (LLD) in pCi/h RESULT = (N/At B)/(2.22 E V Y DF) TWO SIGMA ERROR = 2((N/At+B)/4t)l/2(2.22 E V Y DF) LLD
= 4.66(B/At)l/2/ (2.22 E V Y DF)
=
where: N = total counts from sample (counts) At = counting time for sample (min) . B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date ! E = cfficiency of the counter for 1 131, corrected for self absorption effects by the formula l E = Es(exp 0.0061M)/(exp-0.0061Ms ) Es = efficiency of the counter determined from an I 131 standard mount Ms = mass of Pd12 on the standard mount, mg t M = mass of PdI2on the sample mount, mg O 105 4
GAMMA SPECTROMETRY OF SAMPLER O Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer based data acquisition system which performs pulse height analysis. Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature,less than 100'C. As much as possible (up to the total sample)is loaded into a tared 1 liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer based data acquisition system which performs pulse height analysis. Eith As much as yssible (up to the total sample) of the edible portion of the sample is loaded into a tared Mannel .1 and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(L1) detector coupled to a mini computer based data acquisition system which performs pulse height analysis. l Soils and Sediments i o V Soils and sediments are dried at a low temperature,less chan 100'C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini computer based data ! acquisition system which performs pulse height and analysis. Chairoal Cartridges (Air Jodine) Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and u p to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I 131 of each charcoal cartridge can be determined (assuming no positive I 131) uniquely from the volume of air which passed through it. In the event I 131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector. Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini computer based data acquisition system which performs pulse height analysis. A mini computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. 'Ihe calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass: 106
i RESULT = (S B)/2.22 t E V F DF)
'O -
TWO SIGMA ERROR = 2(S+B)l/2/ (2.22 t E V F DF) l. LLD = 4.66(B)l/2/(2.22 t E V F DF) where: / = S Area,in counts, of sample peak and background (region of spectrum ofinterest) { B = Background area, in counts, under sample peak, ! determined by a linear interpolation ofilw representative backgrounds on either side of the peak ; i t = length of time in minutes the sample was counted . 2.22 = dpm/pCi i 1 E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams) I F = fractional gamma abundance (specific for each emitted gamma) DF = decay factor from the mid collection date to the counting date O T k I O 107
1 ENVIRONMENTAL DOSIMETRY ' O Teledyne Isotopes uses a CaSO i 4 :Dy thermoluminescent dosimeter (TLD) which the ; company manufactures. This material has a high light output, negligible thermally induced signal ! loss (fading), and negligible self dosing. The energy response curve (as well as all other features) I satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. 3 1 1 Following the field exposure period the TLDs are placed in a Teledyne Isotopes Model l 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence)is recorded. The TLD is then annealed and exposed to a known Cs 137 dose; each ' 4 area is then read again. This provides a calibration of each area of each TLD after every field use. l The transit controls art read in the same manner. ' Calculations of results and the two sigma error in net mit!iRoentgen (mR): [ RESULT = D = (Di +D2 +D3+D4)/4 TWO SIGMA ERROR = 2((Di D)2+(9 2D)2+(p .0)2+(p4 0)2y3)t/2 3 WHERE: Di = the net mR of area 1 of the TLD, and similarly for D2 , D3, and D 4 O D1
- 11 K/R i A
= the instrument reading of the field dose in area 1 11 K = the known exposure by the Cs 137 source
= '
R1 the instrument reading due to the Cs 137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs D = the average net mR of all 4 areas of the TLD.
- O .
I r 108
._.. _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ - - _ _ . _ - - _ _ - - _ _,
=
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i l I t I 4 i i i s , d ! 4 ! i 4 4 h ) APPENDIX E i j EPA INTERLABORATORY COMPARISON PROGRAM t 8 . i P 1 I l e r i t
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l l 1 i EPA INTERI ABORATORY COMPARIRON PROGRAM Teledyne Isotopes participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. In this section trending graphs (since 1981) and the ! 1989 data suminary tables are presented for isotopes in the various sample media applicable to the North Anna Stations Radiological Environmental Monitoring Program. The footnotes of the table ' discuss investigations of problems encountered in a few cases. L O - I 4 6 110
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1 o o O , NORTil ANNA - 1989 US EPA IfGERLABORA70RY COMPARISON PROGRAM 1989 (Page 1 of 4) EPA Date 11 Melled Date EPA EPA Tl Norse Dev. ** Warming Preparation Results issued Results Media Nuclide Results(a) Results(b) (K eewr:) *Actles 12/16/88 02/09/89 04/17/89 Waser Ra-226 3.50 1 0.50 3.40 1 0.00 -035 Ra-228 1930 i 1.50 8.83 1 0.81 -1.69 01/06/89 03/07/89 05/01/89 Waner Sr-89 40.00 1 5.00 37.00 1 2.65 -1.04 Sr-90 25.00 i 1.50 26.00 1 2.00 1.15-01/20/89 02/17/89 04/28/89 Waser Gr-Alpha 8.00 1 5.00 8.00 i 1.00 0.00 Gr-Bcea 4.00 1 5.00 6.00 1. 0.00 0.69 02/10/89 03/14/89 05/12/89 Waser Cr-51 . 235.00 1 24.00 245.67 i 11.72 0.77 Co40 10.00 1 5.00 12.67 i 1.53 0.92 Zn-65 159.00 i 16.00 18133 1 5.51 2.42 **(c) Ru-106 178.00 1 18.00 191.00 1 9.85 1.25 Cs-134 10.00 1 5.00 19331 0.58 0.12 Cs-137 10.00 1 5.00 13.67 1 0.58 1.27 02/17/89 03/22/89 05/12/89 Weser I-I31 106.00 i I1.00 98.67 i 0.58 -1.15 U 02/24/89 03/22/89 05/01/89 Waner H-3 2754.00 1 356.00 - 2866.67 i 251.66 0.55 03/10/89 05/26/89 06/16/89 Waser Ra-226 4.90 i . 0.70 5.07 i 0.29 0.4I Ra-228 1.'/01 030 1.47 1 0.29 -135 03/31/89 06/08/89 07/10/89 Air Pher Gr-Alpha 21.00 1 5.00 28.67 i 1.15 2.66 **(d) Gr-Beta 62.00 i ' 5.00 65.67 i 1.53 1.27 Sr-90 20.00 i 1.50 19.67 1 2.06 -938 Cs-137 20.00 i 5.00 18.00 1 - 1.00 --0.69 04/18/89 06/21/89 07/28/89 IJb Perf Gr-Alpha 29.00 i . 7.00 2133i 2.31 -1.90 SampleA . Ra-226 3.50 i 0.50 3.47 i 0.23 -0.12 Ra-228 - 3.60 1 0.50 3.60 1 0.10 0.00 Sampic B Gr-Bcea 57.00 i 5.00 53.00 i 3.61 -139 Sr-89 8.00 1 5.00 .s.00 1 0.00 0.00 Sr-90 8.00 i 1.50 7.67 i 0.58 -038 Cs-134 20.00 i 5.00 19.67 i 1.53 -0.12 Cs-I37 20.00 i 5.00 20.00 1 2.65 0.00 Foomotes at end of tal>le. _ ___.- -. - - - . - . - - . . . - - . = -- . -
o o O NORTH ANNA - 1989 US EPA INIERLABORA70RY COMPARISON PROGRAM 1989 (Page 2 of 4) EPA Date TI Malled Date EPA EPA TI Preperstles Results Nerin Dev. **Werming Isseed Results Media Nuclide - Results(a) Results(b) (Keews) *** Actice 04/28/89 06/21/89 08/07/89 Milk Sr-89 39.00 1 5.00 36.671 1.15 -0.81 Sr-90 55.00 1 3.00 5633i 1.53 0.77 Cs.137 50.00 i 5.00 53331 231 1.15 K 1600.00 i 80.00 1760.00 i 113.58 3.46 ***(c) 05/05/89 07J06/89 08/l4j89 Weser Sr-89 6.00 1 5.00 6331 0.58 0.12 Sr.90 6.00 i 1.50 633i 0.58 038 06dD9/89 07/19189 08/28/39 Ws:cr Ba.133 49.00 1 5.00 33.00 1 3.61 -534 ***(f) Co.60 31.00 i 5.00 30.00 i 2.65 -035 Zn45 165.00 i 17.00 16533 i 038 0.03 Ru 106 128.00 1 13.00 113.67 1 17.50 -1.91 Cs.134 39.09 i 5.00 . 34.00 1 2.65 -I.73 Cs-137 20.00 i 5.00 22.00 1 3.61 0.69 06/23/89 07/19/89 08/14/89 Waner H-3 4503.00 1 450.00 4466.67 1 152.75 -0.14 08/25/89 12/19/89 Air Fileer Gr. alpha 6.00 i . 5.00 8331 0.98 0.81 Cs-137 10.00 1 5.00 12.00 i 1.00 0.69 09/22/99 10/19/89 11/13/89 ' Wsser Gr-Alpha 4.00 i 5.00 ~ 5.001 0.00 035 Gr-Beta 6.00 i 5.00 8.00 1 0.00 0.69 10J06/89 If/16/89 12/19/89 Waecr Ba-133 59.00 1 6.00 51.00 1 436 -231- **(g) Co40 30.00 i_ 5.00 - 30.67 i 2.08 0.23 - 2n45 129.00 1 13.00 - 12833 i 2.89 -0.09 Re-106 161.00 1 16.00- 139.00 i 15.72 -238 **(g) Cs-I34 29.00 1 5.00 23.67 i 1.15 -1.85 - Cs-137 59.00 i 5.00 61.67 i 1.53 0.92 10/20/89 11/16/89 12/19/89 Waser . H-3 3496.00 1 364.00 343333i 57.74 -030 11/10/89 01/05/90 ' 01/30/90 Waser Ra-226 8.70 i 'l 30 8.47 1.. 0.49 -031 { Ra-228 ~930i 1.40 ; 8.57 i 1.46 -0.91 fimermtes at end of table.
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O- O NORTH ANNA - 19189 - US EPA INTERIABORATORY COMPARISON PROGRAM 1989 (Page 4 of 4) i Footenetes: (a) Averageiexperimental sigma. (b) Expecsed laimseory precision (I sigma. I descrmination). (c) He three Zn45 measuremenes were 184.175 and 185 pCi/ liter. Hese were measmed on three detectors using the same aliquot. De othe Ru-106. Cs-134. Cs-137) were all within two standard deviations of the EPA results. His would indicaec that the ddoenen made was corre energies is only 60 kev from Zn-65. the detector efficiencies must be arrect. Dere is no almou (d) De EPA deposits activity on the filter over a srnali deameter (nearly a point source) whereas our calibracon is based on a deposit In ordernearly to 2 inches in correct to point source geometry our practice has been to divide our resuks by 1.2. We neglecsed so do it on this nest. ' (c) Dere is no potassium apparent in mg/lieer. reason why the potassian was high. Three sepersee desecaors were used and the K-40 value for each waicorrecdy divi (f) Deze is no apparent reason why Be-133 was low by 5.54 standard deviation while the other isosopes were within i 2 standard deviations. The deseesc 133 branchmg insensities were checked med found to be correct. On 10/31/89. 300 ml of she enganal. undilueed sample we cosmeed giving 43.915 , (g) Dis EPA samples was conneed in two geomeines; one in dilueed stage, the asher undilueed. There was no significant G", A Companns detector shu. annual sets did not reveal any significant difference. Hus there is no apparent reason why our results differed as much as they did. s i
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