ML20029C901
ML20029C901 | |
Person / Time | |
---|---|
Site: | Grand Gulf |
Issue date: | 12/31/1993 |
From: | Hutchinson C ENTERGY OPERATIONS, INC. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
GNRO-94-00067, GNRO-94-67, NUDOCS 9405020351 | |
Download: ML20029C901 (152) | |
Text
{{#Wiki_filter:p g= , N e Entsrgy opsrations,Inc. 3 - ENTERGY r o w se Port G bson, MS 39150 , Tel 601437 2800 I
;i" C. R. Hutchinson I vx e F+<sieri l April 20 -1994 cx m m 1 ca.., anwea, sw,e 'j U.S. Nuclear Regulatory Ccmmission Mail Station P1-37 Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Grand Gulf Nuclear Station Docket No. 50-416 ' License No. NPF-29 .] Annual Radiological Environmental Operating ; Report for 1993 s GNRO-94/00067 ! P Gentlemen: 'vi -:
!{'y / In accordance with the Grand Gulf Nuclear Station Unit 1 Technical Specifications 6.9.1.6 and 6.9.1.7, attached is the Annual' Radiological Environmental Operatina Report for the period January 1, 1993 through December 31, 1993.
Yours trul ,
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CRH/SBM/ams
,& i attachment: Annual Radiological Environmental Operating Report cc: (See Next Page)
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y .- April 20,1994 GNRO-94/00067 Page 2 of 3 cc: Mr. R. H. Bernhard (w/a) Mr. H. W. Keiser (w/a) Mr. R. B. McGehee (w/a) Mr. N. S. Reynolds (w/a) Mr. H. L. Thomas (w/o) Mr. Stewart D. Ebneter (w/a) Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager (w/2) Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission / Mail Stop 13H3 Washington, D.C. 20555 ,
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i l Summary H I The Annual Radiological Environmental Operating Report (AREOR) - presents Grand Gulf Nuclear Station (GGNS) Environmental C.urveillance Program (ESP) data obtained through analyses of environmental samples collected for the period January 1,1993 through December 31,1993. The AREOR fulfills the requirements of GGNS Technical Specifications 6.9.1.6 and 6.9.1.7. During 1993 and as in previous years, GGNS detected radionuclides attributable to plant operations in the discharge basin surface water (Tritium), barge slip sediment (Manganese-54, Iron-59, Cobalt-58, Cobalt-60, Chromium-51 and Cesium-137) and sewage sludge (Manganese-54, 1 Cobalt-60 and Cesium-137). GGNS personnel routinely monitor results from these areas to note any trends. Their 1993 review of these areas over previous years indicates the following:
. ! Tritium levels are increasing in the discharge basin surface water.
However, es a comparison,' levels detected are well below the.
' technical s' pecification reporting level of 20,000 pCi/l for drinking l water.
Radionuclides in the barge slip sediment appear to be stabilizing as compared to previous years.
. Radionuclides in the sewage sludge remain at levels similar to those -
of previous years. Section 2.0 of this report provides a discussion of these results. k Environmental Surveillance Program GGNS established the ESP in 1978 before the station became operational 1 (1985) to provide data on background radiation and radioactivity normally present ii l I
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en-in the area. GGNS has continued to monitor the environment by sampling air, milk, water, vegetation, sediment and fish, as well as measuring radiation directly. The ESP includes sampling indicator and control locations within an 18-mile radius of the plant. The ESP utilizes indicator locations near the site to show any increases or buildup of radioactivity that might occur due to station operation, and control locations farther away from the site to indicate the presence of only naturally occurring radioactivity. GGNS personnel compare indicator results with control and preoperational results to assess any impact GGNS operation might have had on the surrounding environment. In 1993, GGNS personnel collected 1,340 environmental samples and had them analyzed for radioactivity. They compared results ofindicator locations with \ control locations and previous studies, and concluded that no signi6 cant relationship exists between GGNS operation and effect on the plant environs. Their review of 1993 data, in many cases, showed undetectable radiation levels in the environment and near background levels in significant pathways associated with GGNS. Therefore, they concluded that GGNS operation has had no harmful-effects or irreversible damage to the environment. Attachments Attachment I contains results of air, milk, water, vegetation, sediment and fish samples collected in 1993 and analyzed by Entergy Services, Inc., (ESI) System Chemistry Section. It also includes ESI Systern Chemistry's results in the Environment i Protection Agency (EPA)Interlaboratory Comparison Program. Attachment II contains results of thermoluminescent dosimeters (TLDs) collected in 1993 and analyzed by Waterford-3's Dosimetry Section. 1 Iii
TABLE OF CONTENTS _Paya , Summary . ... . . . . . . . . .. . .. . . . .. .. ii List of Tables . . . . . . . . . . . . . . ... vii List of Figures . .. . . . . .. . .. .. . . . . . . . viii List of Attachments .. .. . .. . . . .. . . . . . . . . ix Section Tonic 1.0 Introduction . .. . . . ... ... . . . . . . . . . . . . . . . . . . 1.i 1.1 Radiation.'.. . . . . . . . . . . . . . . . . . . .. .. .. 11 1.2 Benefits ofRadiation.. . . . . . . . . . . . . . . . . . 1-1 1.3 - Safety of' Radiation.. .. .. . . .. . . . . . .. . . . . . . 12 1.4 Environmental Surveillance Program Purpose and Design Criteria ,. . ... . .. .. .. .. .... . 'l.2 1.5 Dose Pathways Associated with
~ G G N S ........ .. . .. . .. . . . . . . . . . . 13 1.6 ' Pathways Monitored.. . . .. . . . . . . . . .. . ' l .3 -
1.7 Previous Data Comparison . ...... ... . . . . . . . . . . 14 2.0 Environmental Surveillance Program ..... .. .. . . 2-i ~i { 2.1 Air Particulates and Radioiodines.. .. . . .. 21 2.2 Thermoluminescent Dosimetry.. .. . . .. 25 1 1 2.3 Milk . . . . . . . . . . . . . . . . 2 11 l l 2.4 Water . . . . . . . 2-13 ; iV a _ _. _-
TABLE OF CONTENTS Section Tonic Eag 2.5 Vegetation .. . . . . . . . . . . . . . . . . . . . . . . 2-17 2.6 Sediment.... .. . . . . . . .. . 2-19 2.7 Fish . . . . . . . . . . . . . . . . . . 2-23 2.8 Special Samples .. .. . . . 2 2.9 Annual Land Use Census.. . .. . . . . . .. . 2-27 3.0 Analytical Program Technical Description . . . 3-i 3.1 . Sample Handling and Treatment . . . . .. . 3-1 3.2 Gross Beta Air Sample Analysis .. .. . . . . . . . 3-2 3.3 . Gross Beta Water Sample Analysis . ... .. . . . . 3-2 3.4 Tritium Water Sample Analysis . . ... .. . .. ...... . 32 3.5 - Iodine-131 Sample Analysis . . .. . . . . . . . . . . 3-3 3.6' Gamma Isotopic Sample Analysis . .. . . . . . 3-3 . l
' 3.7 Thermoluminescent Dosimetry.... . . . . . . . 3-5 3.8 Data Reporting Conventions .. . ..... .. . .. . . 3-5 4.0 Environmental Surveillance Program Summary . . . . ' 4-i I 4.1 - 1993 Program Results Summary . .. '4-1 1
5.0 Quality Control Data . . .. . .. . .. .. 5-i 5.1 Cosscheck Program Results . . . 5-1 5.2 Duplicate Samples . . . . . 5-1 i V 1 l
TABLE OF CONTENTS Section Tonic _Pa_ge 6.0 1993 Sampling and Analytical Results .. . 6.i 6.1 1993 Data . .. .. . .. . .. . .. . . 6-1 6.2 Lower Limit ofDetection . . . .. . . . . .. . . . . 61 6.3 Reporting Levels .... . . .. . .. . . .. . 6-1 6.4 Sampling Deviations. . . . . . . . . . 6-1 6.5 Radioactivity Not-Attributable to GGNS :. . .. .. 6-2 6.6 Sampling Relocation . .. . .. . . . . . . . . .. .. . . . .. 62-6.7 Comparison to Federal and State Programs . .. . . 6-3~ 6.8 Unavailable Results . . . . . . . . .. .... . . 6-3 6.9 Harmful Effects or Ineversible Damage .. . . . 6-3 1 l l I h@ $ $$- M.6 .MMN .M. M . . l .
e LIST OF TABLES Table No. Title .P._a ge 11 Radiation Risks... . .. . . .. .. . . . . . . . . 1-5 1-2 Air Sample Locations .. . . . . . . . . . . . .. . . . . . . . .1-6 1-3 TLD Locations . . . . .. . .. . . . . . . .. . .. . .. 1-7 1-4 Milk and Water Locations . . . . . . .. . . . . .. . . . . 1 12 15 Vegetation, S'ediment and Fish Locations . . . . . . . . . 1-14 2-1 Average TLD Do'se Rates ... . . . .. . . . . . . . . . .. .. 2-8 '- 2-2 Barge Slip Sediment Analytical Summary . . .. . . . . . .. 2-22 23 19921993 Land Use Census Changes ... . . . . . . . . . . -.2-3 0 2-4 1993 Land Use Census . . . . . . . . . . . . . . . . . . . .. .. 2-31 4 1- Emironmental Monitoring Program Summary .. . . .. . .. 4-2 4-2 Indicator & Control Locations... .. ... . . . . . . . . . . . . . . . . 4-9 i 1
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Vii
LIST OF FIGURES Ficure No. Title _P_gge 1-1 Exposure Pathways . . . . . . . . . . .. . . . 'l-16 1 -2 . Sample Collection Sites - 5 Mile Map .. . . . . . . . .. ..1 17 1-3 Sample Collection Sites .10 Mile Map .. ... . .. . . . 1-18 2-1 Air Sample Cross Beta Concentrations . . . , . . 2-4 2-2 TLD Radiation Dose . . ... . . . . . . . . 29 2-3 GGNS and NRC TLDs . . ... . . . . . . . . . . .~2 10 2-4 Discharge Basin Tritium Results . . .. . . . . . . . . . . . 2-16 5-1 EPA Intercomparison Study .. .. .. ... ...... .. . . .........._5-2 . i l i l l 1
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i 1 l viii
LIST OF ATTACRMENTS Attachment Title Pa2e I 1993 Environmental Sampling and Analytical Report .. . . . . . . . . . . . . . . I.i
~ II 1993 Thermoluminescent Dosimetry Report .. . . . II.i 1
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Introduction 1.1 Radiation Natural radiation affects all people. Natural radiation exposure comes from the sun, naturally occurring radioactive materials present in the earth, dwelling structures, food and water, air and our bodies. Levels of natural or background radiation vary greatly from location to location. For example, the average United States resident receives approximately I 300 millirem in a year from natural background as shown in Table 1-1. Man-made sources, including X-rays, radiation medical treatment, fallout from nuclear explosives testing, and radioactive materials from f nuclear power plants, contribute additional exposure. However, Table 1-1 shows that an individual receives the major portion of dose from natural background and other sources, with nuclear power plants contributing
< 1.0 millirem.
1.2 Benefits of Radiation Uranium used in nuclear power p'ays an important part in meeting 3 today's electricity needs, and it will continue to serve as an important source of energy well into the future. Also, other uses for radiation have f benefited our everyday lives during the past 20 or 30 years. Industries use radioisotopes and controlled radiation to sterilize medical supplies, to improve food preservation, in industrial processes, in medical science, and in the study of environmental pollution, agriculture and hydrology. The public receives its main exposure to man-made radiation from medical - 1 diagnosis and treatment sources, but the benefit in terms of human lives and health is enormous. 1-1 L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ - - . - - - - - -
l 1.3 Safety of Radiation Radiation and the safety of radiation cornmand considerable public attention. Although it is not generally realized, safety regulations for radioactive materials are much stricter than for other potentially dangerous substances. For example, a person living near a 1000 megawatt electrical (MWe) coal fired plant could receive 7.2 millirem in a year frem the -i naturally occurring radioactive materials contained in the coal that is burnt. A person living adjacent to a similar sized nuclear plant could expect to receive < 1.0 millirem in a year. In addition, radioactive elements lose their radioactivity, and I resulting toxicity with time. Potentially toxic non-radioactive materials, such as lead, silver and mercury, can remain to be a problem until properly treated and stabilized. Table 1-1 presents illustrations of relative radiation exposure risks as compared to other health risks. 1.4 Environmental Surveillance Program Purnose and Desien Criteria GGNS established the ESP to minimize any associated radiation- l l endangerment to human health or the environment by ensuring that plant operating controls function properly. The ESP purnose involves: Evaluating environmental sampling procedures, equipment and techniques '
+ Measuring radiation levels and their variations in environmental .
media in the area surrounding the plant J e Determining average levels of radiation and radioactive material in various environmental media .
. Detecting effects, if any, of GGNS operation on the environmental radiation levels and concentrations.
1-2 1
The ESP design criteria includes: Analyzing important pathways for anticipated types and quantities of radionuclides released into the environment Considering the possibility of a buildup oflong-lived radionuclides in the environment and identifying physical and biological accumulations that may contribute to human exposures Considering the potential radiation exposure to plant and animal life in the environment surrounding GGNS Correlating levels of radiation and radioactivity in the environment with radioactive releases from station operation. 1.5 Dose Pathways Associated with GGNS Figure 1-1 shows potential exposure pathways that could occur as a result of a nuclear power plant. However, direct dose from gaseous effluent and thyroid dose from ingesting milk involves the most significant environmental dose pathways from a nuclear power station. GGNS f operations have little, if any, impact on these pathways due to very low levels of radiation released, remote location and absence of milking animals i within five miles of GGNS. In addition, the GGNS Final Environmental ' Report lists the first use of drinking watec from the Mississippi River as j more than 200 miles downstream. Therefore, GGN3 operations have little, if any, impact on this pathway. 1.6 Pathways Monitored The ESP includes the sampling program for monitoring airborne, waterborne, ingestion and direct radiation pathways as required by the Offsite Dose Calculation Manual (ODCM) Specifications. GGNS u i 1-3
.]
i i
= i
_ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - ~~^ ' '
I' I supplements this program with additional sampling in order to provide a ! comprehensive and well-balanced program. Tables 1-2 through 1-5 provide a description of the GONS ESP sample locations. Only sample locations required by ODCM Specifications are keyed to Figures 1-2 and 1-3 as shown in the Tables. I.7 Previous Data Comparison GGNS personnel observed no significant changes between 1993 results and those from previous years. Results remained at levels similar to those of previous years. Such results confirm proper functioning of GGNS effluent controls and equipment. l I
/
(,
-TABLE 11 Radiation Risks. _
Estirnsted Loss of Average Life Radiation Risks In Perspective Expectancy From Various Health Risks c
' Radiation Dose Comparisons Estimated Days Aeproximata - cf Life Expectancy +: . Natural Background - lAREM/ Year.
Mestth Risk . ~ Lost (average) Average U.S. Resident ... . . . .. . .300 . Smcking 20 Cigareties/ Day ~ . .. . 2370(a.sg Average Denver Res! dent. .. . . .... .380. Overweighterzw . . ........ . 985 ruren; Radon in average households All Accidents Combined :
' +35 p.: ven; New York /Now Jersey . . . . . -360 ... 475 . Auto Accidents . ... . . .. .. . . 200' Massachuset1... .... . . . . .. ..
Atcohol Consumption (v.s. Avnge) . 130 Medical Exposure Average U.S. Citizen .... .. . . ... .. .. ... 50 Home Accidents ' 95 Typical Medical Examinaton D mwnbg ------- . .-- ------.--,M Dental X. Rays (Mwun .. ... . . ~.. . -. 3,000 (sxn .
-8 .. . . ... . ~.. . . . ~10 (sm,; Natural Background Radiation .._.
ChestX. Rays.
.~1,400(s#4 Medical Diagnostic X Rays ru.s. Avnge) .... 6 Gastro-intestinal Ser!es runw4 aw o..
Occupational Exposure All Catastrophes (sanneuexe, mm.) .. .. 3.5 Average Piigrim Station .600 ese., One REM Radiation .. ........ 1 Radiation Worker wm ,sso; ... . . . Background Radiation Sources Radon 55%
,C.jnm -
w a. ;m. p , gt..g y -- k, .w. G@\ .-$dMhD m . 3 ...Mgh .... (g
%*I- .aycyu. m g "gy m y .
N
$g: 7 3.;
y.. : . i.,.e p j o j l { $u; ;y'%..::Q. ~ . Ccsmic 8% > iff' s t - .. fq;p IIJ[M;$ . 1 ": ;. . Terrestria! 8% gM: ' . . . . . . .
>$$;p$ % D , . . a 4.- / +--- Nuclear Medicine 4%
R. yv . 9 q w & h g ,. cg ; y . 3.< .d.~ ' .-" p.. + Consarner Products 3% Intemal 11% >g -
. .-j -+ 0:ner <1%
w wp . Q . f.. -glm,p .' MA Occupaiiona10.3%
> ED8h: %Q.b . ,;.?d7D 5 S ? ? i. 4 Fallout 0.3%
Medica' X-Rays 11%
$5MW%Wb y - ' Cr*
QV -i.) Nuclear Fue! O.1% Miscenaneous 0.1%
~' % ,p~n +a, , , . * * -
7
% as . 5 Tne per:antage contribution of var!cus radhtian sour:ss to the totalaverage eMa:ilye dose squ! vale ..... O e 30 1-5
TABLE 12 f - Air Sample Locations Air Sample Number - Figure Location AS-1 PG 13 - Southeast of GGNS at the Pon Gibson City Barn (Sector G, Radius 5.5 miles) AS-3 61VA 1-3 North-northeast of GGNS on Hwy 61, nonh of the Vicksburg Ahport (Sector B, Racus 18 miles) AS-4 GJOE Not - Southwest ofGGNS, Glodjo propeny on Shown Bald Hill Road (-Sector L, Radius 0.9 miles) - AS.5 TC Not South of GGNS behind the Support Services Shown- Center (Sector J, Radius 0.4 miles) l AS-6 RS 12 Northeast of GGNS, south side of Grand Gulf Road (Sector C,' Radius 0.5_ miles)- . AS.7 MT . 12 Nonh o' f G' GNS, locatedInext to the. Meteorological Tower ..
- (Sector A, Radius 0.8 miles) .
l AS-8 WR 12 East of GGNS, located at former site of Maggie Jackson's trailer on Bald Hill Road near the eastern SITE BOUNDARY , (Sector E, Radius 0.6 miles) AS-10 HR Not Near County Road / Heavy Haul Road Shown intersection (Sector P, Radius 0.8 miles) j AS-11 BB Not Near influent end of Basin B (Sector M, l I Shown Radius 0.3 miles) ; M. MMN.. M O O 16 l-
) . TABLE 1-3 - TLD Locations t . TLD No. . Location Figure Sector Mile M-00 Maintained in lead shield during the exposure period - .. - ;
M Across the road from the - Lake Claiborne entry gate 1-2 E' 3.5 M-07 Port Gibson City Barn, AS-1 1-3 G. 5.5 M-09 Warner Tully Camp 1-2 D 3.5 M-10 Grand GulfMilitary Park l-2 A 1.5
- M-14 Hwy 6_l, AS-3-61VA, north (Control) ofVicksburg Airport 1-3 .B 18.0 M-16 AS-7 MT, Meteorological .
Tower 1-2' A 0.8 M-17 AS-6-RS, Grand GulfRoad . 1-2 'C 0.5
. M-19 Behind burn pit on fence at eastern SITE BOUNDARY 1-2 E. . 0.5 .:M-20 Hazardous Waste Storage Area - 1 F~ ~ 0.5 I . M-21 AS-5-TC, Support Services Center 1-2 J . 0.4 M-22 Former RR entrance crossing 12 G 0.5 M-23 County Road / Heavy Haul Road 50 yards north on power pole 1-2 Q 0.5 M-25 Radial Well Number 1 12 N 1.6 1-7 i
3
- TABLE 1-3
- TLD Locations -
1 TLD No. ' Location : Figure Sector Mile - M-27 _ South point SITE BOUNDARY , 200 yards along propertyline 11-2 M 1.5 ; 1 M-28 ' AS-4 GJOE, Glodjo residence : 1-2 L- 0.9 i M-31 Duplicate TLD installed quarterly at varying locations -- - -
-M-32 Duplicate TLD installed . !
quarterly at varying locations - - - M-33, Newellton, Louisiana, Water l Tower ' 1-3 . JP 12.5 l l
- M-36 Curve on 608, point nearest i GGNS at power pole - 1-2 P. '5.0' l
- . M-38 ' Lake Bruin Statj Park, '
l second pole- ~1-3 : M. 9.5 : M-39 St. Joseph,' Louisiana, Aux.- Water Tank .1-3 M- l13.0 M-40 International Paper Road, 5 miles from site 1-2 M ' 5.0 M-41 Radial WellNumber 4 1-2 P 1.5 f M-45 Old Visitor Ce' nter gate . 2 D 0.5 } M-47 Bridge 0.6 miles west of Rodney Westside Road / Mont Gomer Road intersection, north side 1-3 L 5.2 1-8 t
TABLE 1-3
' TLD Locations TLD No. Location ' Figure Sector Mile M-48 Property line fence 0.4 miles on Mont Gomer Road on West side 1-2 K 4.8 j
M-49 Fork in Weathers Road 1-2 H ..4.5 ' l-50 Panola Hunting Club entrance 1-3 B 5.5
' M-51 Ingelside/ Deer Ctenp Road intersection 1-2 C. 4.2 .
M-55 Behind Bonner's Beauty Shop at MSDH air sampler 1-2 D 5.0 !
.M-56 A.W. Watson Elementary and Junior High School 1-2 G- 4.2 !
M-57 Hwy 61, behind the Welcome to Port Gibson sign at Glensdale - Subdivision ~ 1-2 .F 4.5 M-58 Hwy 61, Big Bayou Pierre bridge, southeast end 1-2 E 5.0 M-59 Offlevee at Wm' ter Quarters Hunting camp 1-3 N~ 5.1 M-60 Duplicate TLD installed quarterly at varying locations - - - M-61 Protected area fence Not D Onsite Shown M-62 Protected area fence Not E Onsite Shown 1-9
e TABLE 13 TLD Locations TLD No. . Location - Figure . Sector Mile [. M.63 Protected area fence .Not N Onsite Shown M-64 Protected area fence Not; M Onsite Shown M-65 Protected area fence Not ' 'L Onsite Shown - M-66 Protected area fence Not - K Onsite . Shown f M-67 Protected area fence Not J Onsite l Shown - M.68 Protected area fence - Not - H- Onsite - Shown . f ! M-69 Protected area fence Not ; G - Onsite ! Shown L M.70 Protected area fence Not. F Onsite Shown M-71 Protected area fence Not C Onsite - Shown
'M.72 Protected area fence Not B Onsite !
Shown M-74 Protected area fence Not P Onsite Shown I. 1 M.76 Protected area fence Not A Onsite - Shown i . . I ! 1-10 i
TABLE 1-3 TLD Locations l TLD No. Location Ficure Sector Mile M-77 Protected area fence ' Not R- Unsite
'Shown M-81 Administration Building Not .Q Onsite Shown -
M-86 Bechtel gate north-SITE BOUNDARY 12- B _ 0.5 M-88 ' River mile marker 409.5 1-2 A ~4.2 M Middle Grou$dIsland :1 2 RT 4.4 ' M-90 Across from Middle Ground Island ~ 12- Q 3.5 M-91 Transmission line by pond . l .2 J 4.5 M-92 ' Fence behind orchard '- 1 K: ' O.4 M-93 Underground cable sign 12 H' O.4 - M-93 Sector R garden 1-2 R 0.8 l 1-11 . I
TABLE 1-4 Milk and Water Locations
. Milk Figure ' Location Alcorn State University 1-3 Located south-southwest of GGNS (Sector K, Radius
[ 10.5 miles) I f Cistern Water McGee Cistern f < 1-2 Located north ofGGNS at l the McGee house (Sector A, p Radius 0.9 miles) - ) Willis Cistern 1-3 Located at the C E. Willis }. house east-northeast of GGNS across from the Shiloh Baptist Church'(Sector D, l . Radius 6.0 miles) .. Surface Water
. Upstream 1-2 4500 ft upstream of the GGNS discharge point into . the Mississippi River to allow -
adequate mixing of the Mississippi and Big Black Rivers (Sector Q-R,1.8 miles) Downstream 1-2 5000 ft downstream of the GGNS discharge point into the Mississippi River near Radial Well No.1 (Sector N,1.6 miles) ~ r. I Discharge Basin 1-2 West-northwest of GGNS in parking lot (Sector P,0.3 miles) !- 1-12
]
.~, .-. . . . . . , . .
f TABLE 1-4 Milk and Water Locations Groundwater Figure '- .' Location PGWELL l ' PORT GIBSON WELLS -
. Taken from distribution' '
system or.one of the five wells (Sector G, Radius 5.0 miles) .
~ AAWELL l-2 Arnold Acres Trailer Park, inactive (Sector J, Radius . -
1.1 miles) i i
'f P -i 5
1 4 1-13
.i t
[ l TABLE 15 Vecetation Sediment and Fish Locations Vegetation Figure . Location BroadleafVegetation 1-2 South of GGNS near the Support Services Center (Sector J,0.4 miles) 1-2 North-northwest ofGGNS near the Meteorological Tower (Sector R,0.8 miles) 13 Alcorn State University south-southwest of GGNS (Sector K,10.5 miles) when f available, otherwise a location: 15-30 km distant Sediment SEDHAM 12 - Downstream of the GGNS discharge point into the Mississippi River in the vicinity of the boat landing l near Hamilton Lake outfall I (Sector N,2.0 miles) SEDBAR Not Barge slip (Sector Q,1.5 Shown miles) I SEDCONT Not Upstream from the GGNS Shown discharge point into the Mississippi Riverin the f vicinity ofupper Grand Gulf Landing (Sector R,2.0 miles) f 1-14
~ ' '
TABLE 15 - Vecetation, Sediment and Fish Locations Fish Figlig i Location Commercially or . 1-2 Downstream of the GGNS recreationally discharge point into the important Mississippi River species 12 Upstream of the GGNS discharge point into the Mississippi River uninfluenced by the plant operations - l 1 l (
. .M.
1-15 i
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g i.j .) ry '[',, 7:Y{ .. .'.4. ; ; f.,a < s r E Y . . y
. . . . . . . . . . . /. . . ., . . . a q'l r L:F ;t -';2:'
ENVIRONMENTALSU.RVEILLANCE P.ROGRAME w ,
%a y' , '!b: :# 9: : < s IN. TERPRETATIONS AN.D T. RENDS DF lisSD, LTS.1 '2 .'e->
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.m -- - PROGRAM DESCRIPTIONu e 1 i w ~
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i 2.1 AIR PARTICULATES AND RADIOIODINES f : L
> Note: Analytical results presentedin Tables 1.1 through 1.13 ofAttachment I and summari:. edin Section 4.0.
r 2-1 4 i
2.1.1 gterpretations and Trends of Results I Air particulate and Iodine-131 results for 1993 compare similarly to those obtained in previous years of the operational and preoperational ESP. Iodine-131 remained undetectable with gross beta concentrations for indicator locations l ranging from 0.002 - 0.026 pCi/m3 with a mean of 0.012 pCi/m3 as compared to control locations which ranged from 0.003 - 0.029 pCi/m3 with a mean of 0.013 pCi/m .3 These results indicate the airborne exposure pathway has not been affected by the operation of GGNS and that airborne concentrations ) continue to be at background levels. 4 Gross beta concentrations shown in Figure 2-1 further emphasize that GGNS has had no influence on ambient radiation levels. This figure shows 1993 monthly average results compared to preoperational results, and 1985 through 1993 yearly average results for indicator locations compared to controls. Values compare similarly over the period. > 2.1.2 Program Description The GGNS ESP utilizes nine continuous air samplers to provide gross beta, gamma and radioiodine activity measurements by the airborne exposure pathway. These air samplers range in distances from 0.3 to 18 miles I (Figures 1-2 and 1-3, and Table 1-2). Five air samplers met the requirements of ODCM Specification 4.12.1, located as follows:
. Three near the SITE BOUNDARY in areas of the highest calculated annual average groundlevel D/Q values . One in a community that has the highest calculated annual average groundlevel D/Q value (Port Gibson) . One in a control location (Vicksburg, MS). ;
i l i
)
2-2 l 1 1 _J
l 1 i GONS personnel located the remaining four air samplers in areas which provide supplemental data for the ESP. I GGNS personnel placed air samplers one meter above the ground in weatherproof houses, with a 2-inch glass fiber filter in the intake line af the vacuum pump and a 2 x 1-inch charcoal cartridge located directly f downstream. GGNS personnel maintained air flow at 1.25 cubic feet per minute. They changed filters and cartridges weekly and had them analyzed for 1 gross beta radionuclides and radiciodine activity, respectively. The analytical contractor analyzed quarterly composites of air filters for gamma radionuclides. i i
V FIGURE 2-1 Air Sample Gross Beta Concentrations 1993 Gross Beto Results # for Indicator Locations Avg pCl/m3 0.03 ..... ... i
. 1979 - 1984 Prooperational Avg -
0.04 - . 1993 Operational Avg
~ . . . . . . . . . . . . . . . . . . . . .
i 0.03 -
)
0.02 - JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 1985 - 1993 Gross Beto Results Indicators Versus Controls Avg pCf/m3 0.05
' ' ' h h d '~ ) ~
cnernoeys zneio nt 0.03 - 0.02 - j / / / ,
/
{T,j/'/
/ / / / $ l lll3
- /l 1985 1986 1987 1988 1989 1990 1991 1992 1993 2-4
l l 2.2 TIIERMOLUMINESCENT DOSIMETRY r l l l )
~
[ l I Note: A nalytical results presented in A ttachment 11 and summarized 1 in Section 4.0. 1~ f 1 2-5
t 2.2.1 Interpretations and Trends of Results Gamma radiation dose in 1993 compared similarly to that obtained in previous years as illustrated in Table 2-1. This indicates that the ambient [ , radiation levels remained at or near background and have been uninfluenced by the operation of GGNS. Figure 2-2, which further represents this conclusion, shows 1993 quarterly average results compared to 1979-1984 preoperational data, and 1985 - 1993 annual average results for indicator locations compared to the Vicksburg control This figure indicates that ambient radiation levels have remained at or near background levels. As in previous years, GGNS personnel performed an independent verification of the accuracy of GGNS TLD results through the use ofNRC TLDs. Figure 2-3 presents NRC and GGNS results through the third quarter of 1993. The ESP collects consistent, valid data based on the similarity of TLD results. 2.2.2 Prouram Description f The ESP measures ambient radiation in the environment sun ounding I GGNS with 59 TLDs to provide a quantitative measurement of the area radiation levels. GGNS personnel placed these environmental TLDs at distances from 0 to 18 miles (Figures 1-2 and 1-3, and Table 1-3). They collected dosimeters quarterly. The ESP used the following criteria in establishing TLD locations: }
. ODCM Specification 4.12.1 requires 40 TLDs, positioned as outlined below:
An inner ring of 16 stations in the general area of the site boundary with one TLD in each meteorological sector 1 2-6
- An outer ring of 16 stations approximately in )
the 3- :a 5-mile range with one TLD in each 1 meteorological sector
- Eight TLDs located in special interest areas such as population centers and residences or utilized as controls. 4 . Sixteen permanent TLD stations at the protected area boundary. . . The remaining 3 TLDs utilized as duplicates at varying locations.
4 - 4
-1 2-7 .s
TABLE 2-1 l Aversee TLD Dose Rates * .
' ~.= -
Year Inner Ring Geter Ring Special Interest : Control - On-Site (Within 2-Mile Radius) (Witnic %Miic Radius) Areas (M-14) (Protected Area Boundary) 1985 16.1 16.6 17.0 20.1 20.0 1986 18.6 18.3 18.4 .19.8 21.3 1987 18.3 17.7 17.9 18.8 21.8 1988 17.8 16.7 17.3 .17.5 22.8 1989 18.0 17.6 18.5 18.2 20.9 1990 17.2 17.0 17.6 17.5 20.7 1991 18.1 17.9 17.8 18.0 23.7 1992 17.6 17.9 17.3 17.4 28.4 1993 17.8 17.9 18.5 19.8 25.3
- Units in milliremiquarter 1
1 2-8
1 l l I FIGURE 2-2 TLD Radiation Dose 1993 TLD Results l Inner and Outer Rings ODCM Specificottons l Within Six (6) Mile Radius 30
- 1979 - 1954
. Prooperationo! . , 29 - ., 1993 inner and -
- outer Rings 20 -
4
,/ / ~ ' , / / // / '" ~ / ,- (/,/ ' b /'
0
~
6, /;$ [// ,4 1ST Q1R 2ND QTR 3RD QTR 4TH QTR 1985 - 1993 R.D Results Inner and Outer Rings ODCM Specificottons
'~
Within Six (6) Mlle Radius
~ ' ~ ~ ~ "
Annual Avg mR/Qtr 30 ,,, ..........,,,,.......... ,
- Vicksburg Control .
! (M-14) i 29 -
- inner and Outer $
; Rings j 20 - / % ~ / / /. / , / / / 'o - ,/ /; / ',/ ,/ / /
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'l., 4 2.3 :. MILK - f t ~ Note: ' Analytical resultspresentedin Table 6.1 ofAttachment I and summari: edin Section 4.0. 2-11
=: .. _
2.3.1 Interpretations and Trends of Results GGNS personnel did not collect milk samples within five miles of the GGNS site in 1993 due to the absence of milking animals. However, they did collect milk samples from the Alcorn State University control location and had them analyzed for Iodine-131 and gamma radionuclides. As in preoperational and previous operational years, GGNS has not detected any radionuclides attributable to plant operations. The ingestion pathway shown in ODCM Specification Table 3.12.1-1 specifies the frequency and location for obtaining milk samples. In addition, Table 3.12.1-1 provides for the use of a food product pathway as an alternative in instances ofunavailable milk sampling locations. The ESP utilized this alternative in 1993. 2.3.2 Program Description ODCM Specifications require sample collection from milking animals in three locations within a five km distance having the highest dose potential. If unavailable, ODCM Specifications require one sample from milking animals in each of three areas, between five to eight km, where calculated doses exceed 1.0 millirem per year. ODCM Specifications also require one control sample at a distance of 15-30 km. GGNS personnel collect a control milk sample semiannually from the l t Alcom State University Dairy (Figure 1-3 and Table 1-4) to establish background data. However, the ESP did not include milk animals in 1993 within eight km (five miles) of GGNS due to unavailability. Therefore, Section 2.5, Vegetation, i addresses the unavailability of milk samples within the vicinity of GGNS. l l [ 2-12
i 2.4 WATER l l l l f i ) 1
- Note: Analytical resultspresented in Tables 2.1 through 4.6 ofAttachment I
\. and summarizedin Section 4.0. 2-13
l i 2.4.1 Internretations and Trends of Results l Cistern Water GGNS personnel collected cistern water samples and had them analyzed for gross beta radionuclides, Iodine-131, tritium and gamma radionuclides. Iodine-131, tritium and gamma radionuclides during 1993, and as in preoperational and previous operational years, remained at or near background levels. Gross beta concentrations for indicator locations ranged from 2.3 - 7.5 pCi/l with a mean of , 4.8 pCi/l as compared to the control which ranged from 1.4 - 10.1 pCi/l with a mean of 4.7 pCi/1. In addition, the 1993 gross beta indicator mean is similar to the average preoperational mean of 4.4 pCi/1. Overall, concentrations continue to remain at background levels. Surface Water GGNS personnel collected surface water samples and had them analyzed for tritium and gamma radionuclides. As in preoperational and previous operational years, gamma radionuclide concentrations remained at background ; levels. i Tritium levels for Discharge Basin surface water ranged from 2560.0 - 5440.0 pCi/l with a mean of 4026.7 pCi/1. Plant operations and radwaste discharges in 1993 contributed to these levels. Figure 2-4, which shows an increase in tritium levels, presents results from 1985 through 1993 for the ~ p }; Discharge Basin. GGNS personnel closely monitors results from this area, even though levels continue to be below the technical specification reporting level of 20,000 pCi/l for drinking water, as a comparison. Tritium activity at the upstream and downstream Mississippi River locations continue to remain at background levels. 2-14 x _.
Groundwater GGNS personnel collected groundwater samples quarterly and had them analyzed for gamma radionuclides and tritium. As in preoperational and previous operational years, concentrations remained at background levels. 2.4.2 Procram Description ODCM Specifications require water sample collection in the vicinity of GGNS for the measurement of radioactivity by the waterborne exposure pathway. GGNS personnel sampled cistern water monthly at two locations, an indicator near the site (McGee) and a control (Willis) (Figure 1-2 and Table 1-4). They collected samples in labeled containers and had them analyzed for gross beta radionuclides, Iodine-131, gamma radionuclides and a quarterly composite tritium. GGNS personnel sampled surface water from the Mississippi River monthly at points upstream (control) and downstream (indicator) of the plant discharge (Figure 1-2 and Table 1-4). They collected samples in labeled containers and had them analyzed for gamma radionuclides and a quarterly composite tritium. GGNS personnel took an additional surface water sample from the GGNS Discharce Basin. They composited this sample monthly with an automatic sampler that collected a preset volume at hourly intervals. They collected the sample in a labeled container and had it analyzed for gamma radionuclides and a quarterly composite tritium. l GGNS personnel sampled croundwater quarterly from two locations (Figure 1-2 and Table 1-4), Arnold Acres (indicator location) and Port Gibson City (control location). They collected samples in labeled containers and had them analyzed for gamma radionuclides and tritium. 2-15
FIGURE 2-4 Discharge Basin Tritium Results Tritium Results for Discharge Basin Avg pCi/l +
'5,000 4.0 / ~
4,000 - - 3jE6 I 1992 A0 "" . l (957 pCl/.I) g i / j 1985 Baseline Avg (473 pCl/l) .
/
3,000 p p ,
/ - / i / /
2.000 -
/ / . / ~
1,283 / 1,109 /. s000 - 902 798 913
/ ,y . 9s a 3 .....R5 / ?
3 .............. 0 31 ?l si 61 81 31 s1 6 . 1986 1987 1988 1989 1990. 1991 1992 1993 2-16
- 2.5 VEGETATION i
Note: Analytical resultspresentedin Tables S.] through S.3a ofAttachment I and summarizedin Section 4.0. I 2-17
2.5.1 Interpretations and Trends of Results GGNS personnel collected vegetation samples and had them analyzed for gamma radionuclides and Iodine-131. As in preoperational and previous operational years, GGNS did not detect any plant-related radionuclides. 2.5.2 Program Description GGNS personnel collected broadleaf vegetation samples monthly for measurement of radioactivity by the ingestion exposure pathway, due to the unavailability of milk samples within five miles of GGNS. ODCM Specifications require samples of three different kinds of broadleaf vegetation grown nearest each of two different offsite locations with highest anticipated l annual average groundlevel D/Q. GGNS personnel met vegetation sampling requirements by maintaining two gardens inside the SITE BOUNDARY, Sectors J and R. These sampling locations (Figure 1-2 and Table 1-5) provided a more conservative assessment of doses due to the higher deposition rates (D/Qs) than would be measured at t offsite sampling locations. , ODCM Specifications also require control samples of each of the similar types of onsite vegetation 15-30 km from the site. To fulfill this t requirement, the ESP established a control vegetation sample location in Sector K at A] corn State University (Figure 1-3 and Table 1-5). The ESP prefers green-leafy vegetables suitable for human consumption as the primary source of broadleaf vegetation. At times, GGNS personnel took samples of any vegetation with relatively broad l 1 leaves on which airborne radioactive particulate material might be j l deposited, due to unavailability of green-leafy vegetables suitable for l i human consumption. They had the raw samples analyzed for gamma radionuclides and Iodine-131. 2-18
l 2.6 SEDIMENT __ l 3 i Note: Analytical results presented in Table 8.1 ofAttachment I and summarized an Section 4.0, 2-19
2.6.1 Internretations and Trends of Results GGNS personnel collected sediment samples and had them analyzed for gamma radionuclides. Even though GGNS detected Cesium-137 during the preoperational years at a concentration of 200,0 pCi/kg and over previous operational years which averaged 77.7 pCi/kg, gamma radionuclides remained undetectable at the upstream location. The downstream location (Hamilton Lake) contained a Cesium-137 average concentration of 79.0 pCi/kg, as compared to the preoperational average of 295.0 pCi/kg and operational average of 85.9 pCi/kg. Therefore, levels at the upstream and downstream locations continue to remain similar to those of previous years. i ' Table 2-2 provides an analytical results summary for 1985 through 1993 barge slip sediment samples. GGNS personnel attributes the presence of this radioactivity to buildup of very small amounts of particulates since 1985. Although this table shows an increase in activity during 1993, a comparison over previous years shows radionuclide concentrations in the barge slip sediment f stabilizing. Although, previous sampling of the barge slip sediment revealed a wide range of activity, GGNS personnel have found no definite correlation between radionuclide concentrations and plant operating levels, effluent releases or river elevation. 2.6.2 Procram Description GGNS personnel collected sediment samples semiannually at the following locations (Figure 1-2 and Table 1-5): 1 River shoreline in plant effluent discharge (Barge Slip) l Downstream of the barge slip in the vicinity of the Hamilton Lake outfall(indicator location) Upstream from the GGNS discharge (Upper Grand Gulf ; Landing) ' 2-20
n i p ODCM Specifications require only a sediment sample from the downstream location (indicator) However, the ESP utilized additional samples from an upstream location (control) and the barge slip (indicator), : GGNS personnel collected sediment samples near the shoreline l from the top one-inch layer of sediment. They then discarded foreign t objects and transferred the samples to clean, labeled containers for gamma radionuclide analyses. i j k
.i i
t i t t 4 2-21 l
i 3 9 a n 0 2 0 0 0 5 " 5 9 e 9 3 3 4 9 1 7 D 7 4 1 M 2 1 5 1 9 4 N 1 1 2 n 0 " " 0 " " 0 9 ae 4 D D 4 D D 6 9 6 1 M 1 N N 9 2 N N 7 0
- 0
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- 0 0
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/
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I 2.7 FISH i l l i f I Note: Analyticalresultspresentedin Tables 7.1 and 7.2 ofAttachmentI and summari: edin Section 4.0. ( 2-23
I' 2.7.1 Interpretations and Trends of Results GGNS personnel collected fish samples semiannually from two locations and had them analyzed for gamma radionuclides. Analytical results for fish in 1993 ! and previous preoperational and operational years have shown no data which was j attributable to the operation of GGNS. 2.7.2 Program Description t GGNS personnel collected fish semiannually in the Mississippi River at the following locations (Figure 1-2 and Table 1-5): Downstream of the GGNS discharge point into the Mississippi River (indicator location) [ . Upstream of the GGNS discharge point into the Mississippi River uninfluenced by plant operations (control location). f GGNS personnel collected fish by net, trotline, electroshock or purchased from commercial fishermen. They accompanied commercial fishermen, when purchasing samples, to ensure representative and valid samples from required loc.t ions. GGNS personnel collected a sufficient amount from each location to L provide a minimum of 1000 grams (wet weight) of eviscerated fish sample. L They had the samples analyzed for gamma radionuclides, a f 2-24 1 ;
1 f' 2.8 SPECIAL SAMPLES I i I i Note: Analytical results presented in Tables 9.1 through 12.2 ofAttachment 1 l andsummarizedin Section 4.0.
h-2.8.1 Interpretations and Trends of Result.s In 1993, GGNS personnel collected eight special samples and had them analyzed for gamma radionuclides. Discussion below provides descriptions of special samples collected and their results.
. Surface Water - One sample from Outfall 010 -
I Plant-related radionuclides not detected.
. Sediment - One sample from Basin A and one sample from Basin B - Cesium-137 detected in Basin A.
Section 4.0 summarizes results.
. Sewane Sludge - Four samples from Unit 1 Sewage Plant sludge (Outfall 010) - Plant-related radionuclides detected.
I Section 4.0 summarizes results.
. Venison - One sample from Bucksnon Hunting Camp.
[ Plant-related radionuclides not detected. 2.8.2 Program Description GGNS personnel collected special samples occasionally from - y nonroutine ESP locations to provide supplementary data and to address areas of special interests. Sample media may include sediment, water, milk, fish, meat and vegetation and may be analyzed for gamma radionuclides, Iodine-131, tritium or gross beta radionuclides depending upon current interest. L p I f 2-26 l
i l 1 i f' b 2.9 ANNUAL LAND USE CENSUS \ ) . L l
- 2-27
b l I 2.9.1 Interpretations and Trends of Results , GGNS did not modify the ESP, even though some minor changes
)
occurred from 1992 to 1993, as shown in Table 2-3. Also, the land use census identified no location which would yield a calculated dose or dose f commitment greater than those currently being calculated. L The 1993 Land Use Census results indicated land uses in the zero to 5-mile area surrounding GGNS have remained basically the same as b those reported in the 1991 and 1992 Annual Land Use Census. Table 2-4 presents the 1993 Land Use Census data sheets.
}
2.9.2 Program Description GGNS personnel conducted an Annual Land Use Census as required by ODCM Specification 3.12.2. This census identifies changes in uses ofland in unrestricted areas surrounding GGNS which would require modifications to { the ESP or ODCM. The land use census identified important criteria in each of the 16 meteorological sectors, such as nearest: i'
. Residence }- .
Animal milked for human consumption Garden of greater than 50 m2 (500 ft2) producing broadleaf vegetation. GGNS personnel conducted the 1993 Land Use Census by: h . Five mile field survey confirmation in each sector to locate: Nearest permanent residence Nearest unoccupied residence
)
l- - Nearest garden and approximate size Nearest milking animal. 2-28
l Telephone confirmation in several instances when personal contact could not be made. Identifying locations on the map, measuring distances to GGNS and recording results on data sheets. . Comparing 1993 census results to 1992 census results. 1 f i k i 2-29
TABLE 2-3 I 1992-1993 Land Use Census Chances Sector Parameter 1992 Data 1993 Data - Reason for Change A Nearest Occupied Elizabeth McGee Henry Gaines Ms. McGee died and Mr. Gaines (brother) is now living in her Residence house. E Nearest Occupied Roy Rogers Johnnie Hadad Mr. Rogers died and wife married Mr. Hadad. They are living Residence at the former Mr. Rogers residence. [ F* Nearest Broadleaf Garden Wilbert Porter, Sr. 7.8 " David Killingsworth Closer garden identified during census.
' 7.2 *
- f G* Nearest Occupied Sherman Williams Will Hawthorne Williams house vacant. Hawthome now closest residence.
Residence 3.1 " 3.3 " 11' Nearest Occupied John Nichols Bobby Waddle Nichols house vacant. Mr. Waddle is living part-time in Residence 1.8 " ' l .8 *
- Amold house across road, K Nearest Broadleaf Jim Cassell, Jr.. . Jim Cassell, Jr. Mr. Cassell grew a larger garden.
Garden ~ 50 m2 ~ 400 m2 P Nearest Occupied Wallace Watson Wallace Watson Number of occupants decreased from four (4) to three (3). Residence R Nearest Broadleaf GGNS (ENV) Map changes. GGNS (ENV) Garden 1.2 " . l .6 * *
- Represents changes associated with Land Use Census requirements.
*
- Distances in kilometers.
2-30
-l TABLE 2-4 1993 Land Use Census .:
Parameter Sector A Sector n Sector C Sector D
- 1. Nearest
- a. Distance (km) 1.5 Occupied Residence 1.2 1.1 4.3
- b. Name
!!cmy Gaines
- Mary L Dotson
- c. Address Lane!I Frazier Rt. 2. Box 391 Ethel M. Ryals Rt. 2 Box 391 P.O. Box 33 Port Gibson, MS Rt. 2, Box 372B Port Gibson, MS Port Gibson, MS Port Gibson, MS
- d. Numberof Occupants 1 4 3 6
- 11. Nearest
- a. Distance (km) None Unoccupied Residence None None None Ill. Nearest
- a. Distance (km) None
,1tilk <inimal None None None
- b. Owner's Name IV Nearest
- a. Distance (km) None
!!roadleefGarden None 7.7 4.5
- b. Owner's Name
- c. Address Issac Mays John 1 Jackson Rt.2 Rt.2 Dox 371E Port Gibson, MS Port Gibson, MS 2
- d. Garden Size (m )
~290 -200 V. Census a. Is nearest occupied residence Compariren in same location as last census? Yes l
Yes Yes Yes
- b. Is nearest milk animal in same location as last census? N/A N/A N/A N/A
- c. Is nearest broadleafgarden in same location as last census? N/A N/A Yes Yes 2-31
. _ ~ , , _ _ . - - - - *- . . . _ , -- - -- - ^
TADLE 2-4 1993 Land Use Census Parameter Sector E Sector F Sector G Sector 11 1 Nearest
- a. Distance (km) 1.0 IkcupiedResidence 7.0 3.3
- 1.E *
- b. Name Johnnielisdad
- Dykes Cupstid
- e. Address Willllawthorne
- Dobby Waddle
- P.O. Dox 783 Rt. 2. Ucx 156 Rt. 2, Box 415 Port Gibson, MS Port Gibson, MS Rt. 2 Box 414 Port Gibson, MS Pon Gibson, MS
- d. Number ofOccupants 2 4 4*
II. Nearest 2*
- a. Distance (km) None Unoccupied Residence None None None Ill. Nearest
- a. Distance (km) None Afilk Animal None None None
- b. Owner's Name IV. Nearest
- a. Distance (km) 1.3 ffroadleafGarden 7.2
- 3.4 6.7
- b. Owner's Name Iliram Wells David Killingsworth *
- c. Address Rt. 2, Box 399A Buckner(David Doyle) L C. Jones Rt. 2, Box 150C Port Gibson, MS Rt. ?. Dox 416A P.O. Box 174 Port Gibson, MS Port Gibson, MS Port Gibson, MS
- d. GardenSize(m2 ) -100 -l80 * ~1000 (Grapes) ' ~100 V. Census s. Is nearest occupied residence
' Comparison in same location as last census? Yes Yes No No b Is nearest milk animal in same location as last census? N/A N/A N/A N/A
- c. Is nearest broadicargarden in same location as last census? Yes No Yes Yes .
- Changed since 1992 census.
2-32 i _._,--______---__----.___.__N.-_-_ . _ _ ~ _ _ . - _-
71 TAILLE 2-4 1993 Lanti Use Census I Parameter SectorJ Ttor K Sector 1. Sector M
- l. Nearcsr a. Distance (km) 5.0 35 Occupied Residence 1.4 None
- b. Name Steve Price Jim Cassell, Jr. Glodjo (Buddy Roddey)
- c. Address Rt.1 Box 412D Rt. 2, Box 401 Rt. 2, Dox 401 ~
Port Gibson, MS Port Gibson, MS Port Gibson, MS d Number of Occupants 2 4 4 II. Nearcir a. Distance (km) 3.8 Mone None None l/noccupirJ Residence (Dill CassellIlause) III Nearest a. Distance (Lm) None None He None Ali!L sinimal
- b. Owners Name IV Nearest a. Distance (km) 0.6 3.5 1.4 UroadleafGarden None
- b. Owner's Name GGNS (ENV) Jim Cassell, Jr.
- c. Address Glodjo(Buddy Roddey)
P.O. Dox 756 Rt. 2, Box 404 Rt. 2, Box 40t Port Gibson, MS Port Gibson, MS Port Gibson, MS 2
- d. GardenSize(m ) 4 10 ~400* ~100 V. Census a. Is nearest occupied residence comparison in same location as last census? Yes Yes Yes N/A
- b. Is nearest milk animal in same Ic:"bn as last census? N/A N/A N/A N/A
- c. Is nearest broadleaf garden in same location as last census? Yes Yes Yes N/A
' Changed since 1992 census.
p 2-33
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3.1 Samnle Handline and Treatment The laboratory staff treats and stores samples upon receipt. Environmental samples frequently require treatment prior to analysis, depending on media and analyses type. W 3.1.1 Water Samples Generally, field personnel acidify one-gallon water samples with five milliliters (ml) of concentrated hydrochloric acid when collected, unless otherwise directed by the ana'ytical laboratory. Tritium samples for analyses are not usually L stored in polyethylene bottles for more than three or four months because water can evaporate through polyethylene. 3.1.2 Air Filters The laboratory handled air filters with care during heavy dust loadings to j avoid removing any particulate matter. They normally received air filters in plastic containers; the container as well as sample required analysis for some extremely f low-level analyses. 3.1.3 Milk I The laboratory usually refrigerated milk samples until analyzed. They added a preservative (formaldehyde), if analyses delayed for more than a few days, to inhibit bacterial growth and retard spoilage. Unless shipped on ice, milk samples analyzed for Iodine-131 require addition of 100 ml formaldehyde, of which field personnel normally add 40 ml prior to shipment, to avoid binding of the iodine that may occur with smaller levels of formaldehyde. } 3.1.4 Soil and Bottom Sediment The laboratory dried, pulverized and sieved soil and sediment samples before analysis. They then mixed the samples to ensure a homogeneous mixture. f 3.i
3.1.5 [ ther Samples 4 The laboratory preserved perishable samples by refrigeration or freezing. Vegetation and other samples may require drying, pulverizing or ashing before or I after analysis for long-term storage. 3.2 Gross Beta Air Sample Analysis The laboratory counted air filters for 100 minutes, or until required LLDs shown in ODCM Specification Table 4.12.1-1 were achieved, in a low-background alpha-beta counter at least 24 hours after collection to allow for decay of short-lived materials such t as radon and thoron. 3.3 Gross Beta Water Sample Analysis This process is used to measure overall beta radionuclides of water samples without identifying specific radioactive isotope present. This analysis involves evaporating a two hundred mi sample in a beaker and then drying beaker residue in a 2-inch stainless steel planchet at 100 C. l The laboratory counted the planchets for 100 minutes, or until required LLDs shown in GGNS ODCM Specification Table 4.12.1-1 were achieved, in a low- ' background alpha-beta counting system. Activity calculation includes a self-absorption correction factor for counter efficiency based on weight of residue on each planchet. 3.4 Tritium Water Sample Analysis The laboratory addc.' five ml ofwater to 15 ml ofliquid scintillation solution in a 25 ml vial and then inserted the vial into a liquid scintillation spectrometer for a 300-500 minute count, or until required LLDs shown in GGNS ODCM Specification Table 4.12.1-1 were achieved. ! f 3-2 1
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3.5- Iodine-131 Sample Analysis I The laboratory mixed up to four liters of sample with a stable iodine carrier solution and passed the sample through an anion exchange resin column to remove iodine from the sample. Next, they strip the iodine from the resin with a sodium
- 7. hypochlorite solution, reduce with hydroxylamine hydrochloride and extract into carbon tetrachloride as free iodine. They then back-extract the free iodine into sodium bisulfite solution and precipitate as silver iodide. The laboratory weighs the precipitate to determine chemical yield and mounts on a stainless steel planchet for low-level beta
) counting for 300 - 600 minutes, or until required LLDs shown in ODCM Specification Table 4.12.1-1 were achieved. Finally, they correct the chemical yield by measuring the stable iodide content of milk or water with a specific ion electrode. 3.6 Gamma Is9 topic Sampic Analysis 3.6.1 Milk and Water The laboratory fills a 3.5-liter Marinelli beaker with a representative , aliquot of the sample and counts for a minimum of 240 minutes, or until required - t LLDs shown in GGNS ODCM Specification Table 4.12.1-1 were achieved, in a shielded Germanium-Lithium (GeLi) detector coupled to a computer-based data acquisition system which performed a pulse height analysis. A computer software program defmes peaks by certain changes in slope of the spectrum. The program also compares energy of each peak with a library of peaks for radionuclide identification and then performs calculation using appropriate fractional gamma ray abundance, halflife, detector efliciency and net b counts in the peak region. 3.6.2 Vecetation, Food and Garden Crons, and Fish 1 i The laboratory loads a maximum quantity of undried vegetation, food or _ l l
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l garden crop sample into a tared 3.5-liter Marinelli beaker and weighs. They then" count the sample for a minimum of 200 minutes, or until required LLDs shown in i GGNS ODCM Specification Table 4.12.1-1 were achieved, in a shielded GeLi detector as described in Section 3.6.1. The laboratory loads as much as possible (up to the total sample) of the j edible portion of a fish into a tared Marinelli beaker and weighs. They diluted the sample with deionized water to weigh 3.5 kg and then count for a minimum of 240 minutes in a shielded GeLi detector as described in Section 3.6.1. ' s 3.6.3 Soils and Sediments The laboratory dries soils and sediments at a low temperature (less than 100 C), loads into a tared 1.0-liter Marinelli beaker and weighs. They then a count the sample for 240 minutes, or until required LLDs shown in GGNS ODCM Specification Table 4.12.1-1 were achieved, in a shielded GeLi detector as described in Section 3.6.1. 3,6,4 Charcoal Cartridges The laboratory counts charcoal cartridges in a Marinelli beaker, with one to four cartridges positioned on the face of a GeLi detector and up to seven i cartridges on its side. They calibrate each detector for both top and side 4 positions and determine counting efficiency. They determine the Iodine-131 detection limit for each charcoal cartridge, assuming no positive results for Iodine-131, by utilizing smallest volume of air n: corded for a cartridge within the l Marinelli beaker. The laboratory counts each cl arcoal separately, ifIodine-131 ; observed in the screening count, by positioning on face of the detector. [ i l l 3-4 .
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3.6.5 Air Particulate t The laboratory stacks 12 to 14 (depending on calendar quarter) air p particulate filters for a quarterly composite for each field station one on top of another. They then count the samples for at least four hours, or until required p LLDs shown in GGNS ODCM Specification Table 4.12.1-1 were achieved, in a shielded GeLi detector as described in Section 3.6.1. L 3.7 Thermoluminescent Dosimetry J- The GGNS ESP uses TLDs manufactured by Panasonic (Model UD-814). Although, these TLDs contain one lithium borate and three calcium sulfate phospor elements, only the calcium sulfate phospor element results are used for reporting purposes. [ The laboratory anneals the TLDs prior to shipment. Upon arrival at GGNS, personnel sort and place designated TLDs in a plastic bag (two TLDs/ bag) prior to placing in field. The laboratory reads the TLDs, upon return from the field, in a Panasonic Model !- UD-710 TLD reader. 3.8 Data Reportine Conventions The laboratory calculated mean of analytical results as folio vs: X = E Xi / n where: ._X = . Mean Xi => Individual sample results
- 1 n = Number of sample results 3-5 i-
They rounded calculated values by inspection of digits to the right oflast reported " digit, with values less than 5 rounded down and values greater than 5 rounded up. They rounded a reported value to an even number, when value equaled 5. , The laboratory reported analytical results less than the 2 sigma counting error as .
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= January - March Ist Quarter 2nd Quarter =
April - June
=
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4.1 1993 Program Results Summary Table 4-1 summarizes required ODCM Specifications and supplemental l ESP sample results for 1993. Table 4-2 lists indicator and control locations ) utilized to develop Table 4-1. GGNS personnel did not use values reported as less than (<) for determining indicator and control location ranges and means. Overall,1993 results compare to that encountered in previous years. e m 4-1
\ t
k l TABLE 4-1 Environmental Monitorine Program Summary Name of Facility Grand Gulf Nuclear Station Docket No. 50-416 Location of Facility Claiborne. Miscissioni Reporting Period January - December 1993 (County, State) LLD b Indicator Locations ; Imcation with liighest Annual Mean Control Locations Number of - Sample Type Type & Number a Mean ( F) C Nooroutine ( Units ) of Analyses . Mean ( F ) C C [ Range 1 [ Range ] Results Location d Mean ( F) C l Range 1 AS-8 WR 0.014 ( 52 /52 ) 0.013 ( 102 / 102 ) 0 Air Particulate GD 462 0.01 0.012 ( 358/360 )- ( pCi/m3) [ 0 002 - 0.026 } l .( Sector E,0.6 mi) [ 0.004 -0.026 ) [0.003 -0.029) GS 36
<LLD .'N/A .N/A <LLD 0 Cs-134 0.05 <LLD N/A N/A <LLD 0 Cs-137 0.06 <LLD N/A N/A <LLD 0 Airborne lodine 1 131 462 0.07 (pCi/m3) . M-27 23.0 ( 2 /2 ) N/A 0 Inner Ring TLDs Gamma 61 (f) 17.8 ( 61 /61 )
[ 9.5 - 24.5 ) ( Sector M,1.5 mi) [ 21.5 - 24.5 } ( mR/Qtr ) M-49 20.9 (4 /4 ) N/A 0 Outer Ring TLDs Gamma 60 (f) 17.9 ( 60 / 60 ) ~ [l1.5 - 23.0 ] .( Sector II,4.5 mi ) {l8.0 -22.0 ] ( mR/Qtr )
' M-01 20.6 (4 /4 ) N/A- 0 Special Interest TLDs Gamma 28 (f) 18.5(28/28 ) . [ 14.5 - 22.0 ] . ( Sector E,3.5 mi ) [.18 0 -22.0 }
( mRIQtr ) N/A N/A N/A 19.'8 ( 4 / 4 ) 0 Control TLDs Gamma 4 (f) [ 17.5.- 22.0 ] ( mR/Qtr ) Gamma 63 . M-69 53.1 (4 /4 ) N/A 0 Protected Area TLDs (f) 25.3 ( 63 /63 )'. [ 12.0 - 69.5 } - ( Sector G, Onsite ) ( 31.0 - 69.5 ) ( mR/Qtr ) 4 #
, s __ m .A -_x -_____A__. ._ _ _ _
M _ ___,m ._ ____m___ __ . _ __ _ _ _ - _ _ _ . _ . _ _ _ _ _ _
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TABLE 4-1 Environmental Monitorine Program Summary Name of Facility Grand Gulf Nuclear Station Docket No. 50-416 Lecation of Facility Claiborne. Mississippi Reporting Period January - December 1993 i (County, State) l Sample Type Type & Number LLD b Indicator Locations ' :. Location with Illghest Annual Mean Control Iecations - 8 Number of ' ( Units ) of Analyses Mean ( F )
- Mean ( F )
- Nonroutine i
[ Range ) [ Range ] Results
- 1 Location d y,,n(y)c
[Rancei Cistern Water GB 24 4 4.8 ( 4 /12 ) McGee Cistem 4.8 ( 4 /12 ) 4.7 ( 7 / 12 ) 0 ( pCill) -[ [ 2.3 - 7.5 l . ( Sector A,0.9 mi ) [ 2.3 - 7.5 ] . [ 1 A - 10.1 } . 1-131 24 1.0 <LLD .N/A N/A <LLD 0 II-3 8 2000 270.0 ( l / 4 ) McGee Cistern 270 0(l/4 ) <LLD 0 [ N/A ] ( Sector A,0.9 mi ) [ N/A ] GS 24 Mn-54 15 <LLD N/A N/A <LLD 0 Fe-59 30 <LLD N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Co-60 15 <LLD N/A N/A <LLD 0 Zn-65 30 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD N/A N/A <LLD 0 Nb-95 15 <LLD :N/A N/A ' <LLD .O Cs-134 15 ' <LLD N/A N/A <LLD 0 Cs-137 '18 '
<LLD N/A N/A <LLD 0 Ba-140 60 <LLD - : N/A N/A <LLD 0 La-140 15 . <LLD N/A ' N/A - ' <LLD- 0- '4-3:
i
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- TABLE 4 Environmental Monitorins Program Summary Name of Facility Grami Gulf Nuclear Station Docket No. 50-416 Location of Facility Claiborne. Mississippi Reporting Period January - December 1993 - (County, State)
Sample Type Type & Number LLD b Indicator lecations . lecation with Ilighest Annual Mean Control locations Number of ( Units ) of Analyses a Mean ( F ) C- Nonroutine Mean ( F ) C
' [ Range ] [ Range ] Results C Iecation d Mean ( F ) C I Range l Surface Water 11-3 12 2000 4026.7 ( 3 /.8 ) . Discharge Basin < LID 4026.7( 3 /4 )' 0 (pci/1) [ 2560.0 - 5440.0 } ( Sector P,0.3 mi ) ' [2560.0- 5440.0 ]
GS 36 Mn-54 15 <LLD N/A N/A <LLD 0 Fe-59 30 <!l D N/A N/A <LLD 0 Co-58 15 <LLD N/A N/A <LLD 0 Co40 15 <llD N/A N/A <LLD 0 Zn-65 30 <LLD N/A N/A <LLD 0 Zr-95 30 <LLD- N/A N/A <LLD 0 Nb-95 15 <LLD N/A N/A <LLD 0 Cs-134 15 <LLD N/A N/A < LID 0 Cs-137 18 <LLD N/A N/A <LLD 0 ! Ba-140 60 -<LLD N/A N/A <LLD ! 0 La-140 15 <LLD N/A ' N/A <LLD 0 , Outfal1010 GS 1 Surface Water Mn-54 15 <LLD N/A ' N/A N/A 0 ( pCI/I ) Fe-59 30 <LLD N/A N/A N/A 0 Co-53 15 <ILD N/A'- N/A N/A 0 CM0 15 <LLD. N/A' N/A N/A 0 Zn-65 30 <LLD N/A N/A N/A 0 Zr-95 30 <LLD .N/A N/A N/A 0 Nb-95 15 . < LID LN/A'- N/A N/A 0 Cs-134 15. ~<LLD N/A N/A ' N/A 0 Cs-137 18 <LLD . N/A: N/A N/A 0 Ba-140 60 <LLD N/A N/A N/A 0 12-140 15 <ILD N/A . N/A N/A 0 l '4-4 ' l
- - ~ .. .. .- - .. _ . -. . = -. _ _ _.
. ~ - .
TABLE 4-1 Ensironmental Monitorine Program Summary Name of Facility Grand Guir Nuclear Station Docket No. 50 -t16 Location of Facility Claiborne, Mississippi Reporting Period January - December 1993 (County, State) Sample Type Type & Number LLDb Indicator Locations - lecation with flighest Annual Mean Control Locations - Number of - ( Units ) of Analyses * . Mean ( F ) C - Mean ( F) C Nonroutine '
. [ Range ] [ Range ] Results * - ,
location d Mean ( F ) C [ Range 1 Well Water 11-3 8 2000 <LLD N/A N/A 270.0 ( l / 4 ) 0
-( pCi!1 )
GS s [ N/A ] Mn-54 15 <tLD N/A. N/A <LLD 0 Fe-59 30 <LLD N/A N/A <LLD 0 Co-53 15 . <LLD N/A N/d <LLD 0 CW 15 <LLD N/A N/A. <LLD 0 Zn-65 30 <LLD- N/A N/A <LLD 0 Zr-95 30 < LID N/A N/A <LLD 0 Nb-95 15 <LLD N/A N/A (LLD 0 Cs-134 15 <LLD N/A N/A < LID -0 Cs-137 18 <LLD- ' N/A N/A. <LLD 0 Ba-140 60 < LID . N/A - N/A <LLD 0 La-140 15 <LLD N/A N/A <LLD 0 Milk I-131 2 Lo N/A N/A . N/A . <LLD 0 ( pCill ) GS 3 Cs-134 15 N/A N/A. N/A < LID 0 - Cs-137 18 N/A :N/A N/A (LIB . O Ba-140 60 N/A- . N/A N/A <LLD 0 La-140 15 N/A N/A N/A <LLD 0 Vegetation I-I 31 108 60 -- <LLD_ N/A N/A <LLD 0 ( pCilkg net ) GS 108 Cs-134 Y20 <LLD' N/A N/A <LLD Cs-137 80 0
' <LI D N/A N/A . <l.LD 0 4-5.. 'i
TABLE 4-1 Environmental Monitorine Procram Summarv Name of Facility Grand Gulf Nuclear Station Docket No. 50-416 ' Location of Facility Claiborne, Mississippi Reporting Period January - December 1993 (County, State) Sample Type Type & Number LLD b Indicator lecations location with IIighest Annual Mean Control Locations Number of of Analyses a Nonroutine ( Units ) Mean ( F) C Mean ( F) C [ Range ] ; [ Range ] Results
- Iecation d Mean ( F) C
[ Range 1 Fish GS 4 ( pClikg wet ) Mn-54 130 <LLD N/A N/A <LLD 0 Fe-59 260 (LLD N/A' N/A <LLD 0 Co-58 130 <LLD N/A N/A <LLD 0 Co-60 130 <LLD N/A. N/A <LLD 0 Zn-65 260 <LLD N/A N/A <LLD 0 Cs-134 130 <LLD N/A N/A <tLD 0 Cs-137 150 <LLD N/A N/A <LLD 0 Bottom GS 6 Sediment ( pCi/kg dry ) Mn-54 (f) 1202.0 ( 2 /4 ) ' Barge Slip 1202.0 ( 2 / 2 ) <LLD 0 [ l54.0 - 2250.0 } ( Sector Q,1.5 mi ) [ t54.0-2250.0 ] Fe-59 (f) 53.0 ( l / 4 ) . Barge Slip ' 53.0 ( l / 2 ) ' <LLD 0 [ N/A ] . ( Sector Q,1.5 mi ) [N/A] Co-58 (f) ~ 143.0 ( l !4 ) _ Barge Slip - 143.0 ( l / 2 ) <LLD 0 [ N/A ] . ( Sector Q,1.5 mi) [ N/A ] Co-60 (f) 94 9.0 ( 2 / 4 ) Barge Slip 949.0 ( 2 / 2 ) <LLD 0 [ 267.0 - 1631.0 ] ( Sector Q,1.5 mi ) [ 267.0 - 1631.0 ] Cr-5I (f) -471.5 ( 2 /4 ) Barge Slip ' 471.5 ( 2 / 2 ) <LLD 0 [423.0 -520.0 ). . ( Sector Q,1.5 mi ) .[423.0 -520.0 } Cs-134 150 (LLD N/A' N/A <LLD 0 98.3 (4 /4 ) - Barge Slip 117.5 ( 2 /2 ) . <LLD 0 Cs-137 180 -[ 64.0 - 137.0 ] . ( Sector O,1.5 'mi ) - [98.0 -137.0 1 6 ~
~ - . . . _ _ . ~ . - _ - . _ _ _ - . - -. _ -
-~. ~ , = ,. .
TABLE 4-1 Environmental Monitorine Program Summary Name of Facility Grand Gulf Nuclear Station Docket No.50-416 Location of Facility Claiborne. Miseissippi Reporting Period January - December 1993 (County, State) Sample Type Type & Number - LLD b Location with flighest Annual Mean Control I ocation: ' Number of 8 l - Indicator locations ( Units ) of Analyses Mean ( F) C - Mean ( F) C - NonRoutine [ Range ]1 [ Range ] ' ResaltsC Location d Mean ( F ) C [ Range l Basins A and B GS 2 Sediment ( pCi/kg dry ) Cs-134 150 <LLD N/A N/A N/A 0 Cs-137 180 ' 22.0 ( l / 2 ) - . Basin A ' 22.0 ( l /1 ) N/A 'O
- I N/A 1 -( Sector R,0 3 mi )- ' { N/A ]
Unit 1 GS 4 Sewage SIudge Mn-54 150 - I53.3 ( 4 /4 ) . Unit 1 Sewage Plant 153.3 ( 4 /4 ) N/A 0 ( pCilkg wet ) [36.0 -.270 0 } - ( Sector A,0.3 mi ) [36.0 -270.0 ] Co-60 150 425.0 ( 4 /4 ) . Unit i Sewage Plant 425.0 ( 4 /4 ) N/A 0 [ 129.0 - 807.0 )'._ ( Sector A,0.3 mi ) [ 129.0 -807.0 ] Cs-134 150 <LLD 'N/A <LLD N/A 0 - Cs-137 180. ' 26.0 ( l / 4 ) Unit 1 Sewage Plant 26.0 ( l/4 ) N/A 0 f N/A } ( Sector A,0.3 mi ) { N/A 1 Bucksnort Camp GS .I Venison Meat ( pCilkg wet ) Fe-59 260 <LLD. N/A. N/A N/A 0 Zn-65 260 <LLD' N/A' N/A' - N/A 0 Cs-134 130 <LLD .N/A N/A N/A ~ 0 Cs-137 130- -<LLD 'N/A ' N/A N/A 0 4-7 -
. ~ . . - - . . , . . -. .. .. - . .. .. . - . ....~ . . , . . = . - . . - , . - . ..- . . . . ~ ...
TABLE 4-1 Environmental Monitorine Program Summary Name of Facility Grand Gulf Nuclear Station Docket No. 50-416 Location of Facility Claiborne. Mississioni Reporting Period January - December 1993 , (County, State) - r a GB = Gross beta;I-131 = Iodine-131;11-3 = Tritium; GS = Gamma scan. b LLD = Requiredlower limit ofdeteition based on Grand GulfNuclear Station ODCMSpecification Table 4.12.1-1. c Mean and range based upon detectable measurements only. ' Fraction ofdetectable measurements at specified locations is indicated in parentheses (I-). d Locations are specified (1) by name and (2) sector relative to reactor site. Non-routine results are those shich exceed ten times the control station value. Ifno controlstation value is available, the result is considered non-routine ifit erceeds ten times the preoperational valuefor the location. l LLD not definedin GGNS ODCMSpecification' Table 4.12.1-1. 4 . - - ._- m. m ~ _ .- __ , . , _ _ .. . . , .
. __ . .% - s _ - _- . _ _
TABLE 42
.. Indicator & Control Locations Sample Type Locations Total Total & Type of Analyses Samples p.
AIR . Indicators - AS-4 GJOE' 52 52 ca. - Gross Beta, I 131; 4-Gamma AS-5 TC* 51 51 ea. - Gross Beta, I-131; 4-Gamma AS-6 RS 51 51 ea. - Gross Beta,1-131; 4-Gamma AS-7 MT 52 52 ea. - Gross Beta,1-131; 4-Gamma AS-8 WR 52 52 ea. - Gross Beta, I-131; 4-Gamma
! AS-10 HR* 50 50 ea. - Gross Beta, I-131; 4-Gamma AS-11 BB* 52 52 ea. - Gross Beta, I 131; 4-Gamma ) . Controls - AS-1 PG 50 50 ea. - Gross Beta, I-131; 4-Ganuna AS-3 61VA 52 . 52 ca. - Gross Beta, I-131; 4-Gamma L
TLDs . Indicators Inner Ring .
. M-16,17,19 20,21,22, 23,25,27,28,41,45,86, q
92,93,94 61 61-Gamma . Outer Ring M-36, 40, 4 7, 48, 49,50, . 51,55,56,57,58,59,88, 89,90,91 60 60-Gamma SpecialInterest Areas M-01, 07, 09,10, 33, . 38,39 28 28-Gamma
. Control - M-14 4 4-Gamma . Indicators Protected Area' F M-61, 62, 63, 64, 65, 66, 67,68,69,70,71,72,74, j 76,77.81 63 63-Gamma
- Not required by ODCM Specifications 4-9 s
TABLE 4-2 Indicator & Control Locations I Sample Type Locations Total Total & Type of Analyses Samples WATER Cistern
. Indicator - McGee 12 12 ea. - Gross Beta, I-131, Gamma; 4-Tritium . Control - Willis 12 12 ca. - Gross Beta, I-131, Gamma; 4-Tritium Surface . Indicators - Dov.nstream Ms. River 12 4 - Tritium; 12-Gamma Discharge Basin 12 4 - Tritium; 12-Gamma . Control - Upstream Ms. River 12 4 - Tritium; 12-Gamma . Indicator - Outfall 010* 1 1 - Gamma Groundwater . Indicator - Arnold Acres 4 4 ea. - Tritium; Gamma . Control - Port Gibson City 4 4 ea. - Tritium; Gamma MILK . Indicator - None N/A N/A . Control- Alcorn State University 3 3-Gamma; 2- I-131 VEGETATION . Indicators - Sector J Garden 36 36 ea. - I-131, Gamma Sector R Garden 36 36 ca. - I-131, Gamma . Control - Sector K (Alcorn State Umversity) 36 36 ca. - I-131, Gamma FISil . Indicator - Downstream Ms. River 2 2-Gamma . Control - Upstream Ms. River 2 2-Gamma l
- Not required by GDCM Specifications 4-10
__ . _ . _ __. ___ _ _ _ . _ . . ~._ _ TABLE 4-2 , Indicator & Control Locations e
- i. 1
- Sample Type Locations Total Total & Type of Analyses
. Samples 4
SEDIMENT . Indicators - Hamilton Lake 2 (SEDHAM) 2 2-Gamma
- Barge Slip (SEDBAR)* 2 2-Gamma Basin A* 1 1-Gamma Basin B* 1 1-Gamma . Control - Upstream Ms. River 0- (SEDCONT)* 2 2-Gamma '. WAGE SLUDGE . Indicator - Unit 1 Sewage Plant Sludge (Outfall 010)* 4 4-Gamma - . Control - None N/A N/A
! VENISON . Indicator - Bucksnort Hunting Camp (Sector N) 1 1-Gamma
. Control - None N/A N/A'
- Not required by ODCMSpecifications
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.r i 5.1 Crosscheck Program Results 9
ESI System Chemistry analyzed EPA crosscheck samples for GGNS. Attachment I contains these results. ESI System Chemistry's analysis participation, shown in Figure 5-1, indicates consistent, valid reported data based on acceptable sample results that fall within the three standard deviation range. 5.2 Duplicate Samples Attachment I contains duplicate samples, identified by suffix "GG" accompanying the laboratory number, submitted by GGNS to ESI System V Chemistry for analysis. Attachment II contains duplicate TLDs submitted to the Waterford-3 Dosimetry Section. Summary below identifies sample media { duplicated. Sample Media Sanmles Duplicated Table No. f Cistern Water 6 2.1 - 2.4 Groundwater 2 3.1 & 3.2 Surface Water 10 4.1 - 4.6 Vegetation 12 5.1 - 5.3a Milk 2 6.1 Fish 2 7.1 & 7.2 Sediment 3 8.1 TLDs 12 4 (Attachment II)' GGNS personnel's review of all duplicate sample results indicates consistent, valid reported data based on similarity of results. i , 5-1
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i F FIGURE 5-1 1 EPA Intercomparison Study l l EPA Interlaboratory Comparison Results for 1993 ' Unacceptable ** (i Analysis)
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6.1 1993 Data Attachments I and 11 present data obtained by ESI System Chemistry and Waterford-3 Dosimetry Section on samples collected from January through December 1993. ESI System Chemistry provides data in monthly progress
- j. reports. Waterford-3 Dosimetry Section provides TLD data in quarterly reports.
1 Data presented in Attachraents I and II compare to that encountered in preoperational and previous operational years.. l 6.2 Lower Limit of Detection j ESI System Chemistry routinely counts lower than the maximum LLD required by ODCM Specification Table 4.12.1-1. Factors such as unavoidable . 1 small sample size, background fluctuations, presence ofinterfering radionuclides I or other uncontrollable circumstances cause ODCM Specifications' LLDs to be 1 unachievable in some instances. However, GGNS personnel's review of 1993 ,
- 1 l results indicates acceptable LLDs within required ODCM Specification limits.
6.3 Reportine Levels GGNS' review indicates that no samples equaled or exceeded reporting levels for radioactivity concentration in environmental samples, as outlined in ODCM Specifications Table 3.12.1-2 when averaged over any calendar quarter, due to GGNS effluents. Therefore,1993 results did not trigger any Radiological
- Monitoring Program Special Reports.
l 6.4 Sampline Deviations The ESP missed three air samples required by ODCM Specifications during i 1993 due to sampling equipment malfunction. Two malfunctions involving a blown fuse at air sampling station AS-1 PG occurred during the sampling periods 6-1
q i l l ofJuly 27,1993 through August 3,1993 and August 10,1993 through August 17, 1993. The remaining malfunction which involved a loss of flow occurred at air sample station AS-6 RS during the sampling period of September 14,1993 through September 21,1993. GGNS personnel replaced these air sampling units upon discovery of the equipment failure. The ESP lost five TLDs required by ODCM Specifications during 1993, due to vandalism or flooding from the Mississippi River. Other TLD programs experience losses of this type. In 1993, GGNS personnel calculated a 97% (155 of 160) recovery rate for required ODCM Specification TLDs, which compares with other TLD programs. The ESP did not include milk sampling within five miles (8 km) of GGNS in 1993 due to unavailability. Therefore, GGNS personnel continue to sample the - Alcorn State University Control location semiannually until such time that milk
- samples become available within five miles (8 km) of GGNS. They collected vegetation samples to monitor the ingestion pathway, as specified in ODCM Specifications Table 3.12.1-1, because of milk unavailability.-
GGNS personnel conducted all other ESP activities required by ODCM - Specification without exception. 6.5 Radioactivity Not Attributable To GGNS The GGNS ESP detected radioactivity attributable to other sources twice. These include the 25th Chinese nuclear test explosion in 1980, and the radioactive : plume release due to reactor core degradation at Chernobyl Nuclear Power Plant in 1986. 6.6 Sampline Relheation Vegetation and milk sampling locations did not change in 1993c Therefore, 6-2 1 , O
=
GGNS personnel did not identify any new locations or report circumstances of a unavailability in the Semiannual Radioactive Effluent Release Report. 6.7 Comnarison To Federal and State Programs GGNS personnel compared GGNS data to federal t and state mori oring ) l programs as results became available. The programs used for comparison include the U.S. Nuc' car Regulatory Commission (NRC) TLD Direct Radiation Monitoring Network and the Mississippi State Department ofHealth (MSDH) ' Division of Radiological Health. The latest available NRC TLD Network results compare to those from the GGNS ESP. In addition, as shown in Section 2.2 of this report, GGNS and NRC TLDs produced similar results on the average. ) L The MSDH and the GGNS ESP entail similar radiological momtonng i' samphng requirements. These programs include collocated air samples and splitting or sharing sample media such as vegetation, water, sediment, meat, fis and milk. Both programs have obtained similar results over previous years. In 1993, and as in previous years, the MSDH and GGNS detected radioactivity attributable to plant effluent in the barge slip. 6.8 Unavailable Results GGNS received analytical contractor results in adequate time for inclusion in this report, in addition, GGNS' review identified no missing results. 6.9 _ Harmful Effects or Irreversible Damaec g ) The ESP monitoring did not detect any harmful effects or evidence of L irreversible damage in 1993. Therefore, GGNS personnel addressed no proble 6-3
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.i l 'l .I GRAND GULF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ;
DECEMBER 1993 b PREPARED BY: SYSTEM CHEMISTRY SECTION ENTERGY SERVICES, INC.
,. . . . - . _ __ __. . - . . . ~. . ._ -
f' GRAND GULF RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE OF CONTENTS PAGE
SUMMARY
OF MONITORING RESULTS 1- ,. DATA TABLES: AIR SAMPLES 2 CISTERN WATER 24 GROUND WATER 28 SURFACE WATER 30 I VEGETATION: BROADLEAF 36 [ 1 MILK 42 ;
-4 FISH 43-SEDIMENT 45 SPECIAL SAMPLES:
ANIMAL MEAT (VENISON) 46 SURFACE WATER (GRAB) 47 - SEWAGE SLUDGE 48 . SEDIMENT i. ,. 49
- l. EPA CROSS CHECK RESULTS L
k
'I Summary ofMonitoring Results
- Plant-related isotopes were detected in the surface water and sewage sludge during this reporting period.
Low-level analysis ofIodine-131 was unable to be performed on ALCONT milk samples 931026 and 931027 sampled June 6,1993 due to sample decomposition. The ALCONT milk sample was re-sampled on June 29,1993 and low-level analysis ofI-131 was , completed. Air samples for the period of 05/25/93 through 06/02/93 and 06/02/93 through 06/08/93 ; totaled eight days and six days, respectively,- due to the Memorial Day Holiday falling on 05/31/93 and Company OfTDay falling on 06/01/93. This resulted in collecting one set of samples (05/25/93 - 06/02/93) a day later than normal and shortening the other set of .; samples (06/02/93 - 06/08/93) by one day. Gross beta and Iodine-131 analysis was unable to performed on air sample station AS-5 for the period of 07/20/93 - 07/27/93 due to insufficient flow. Gross beta and Iodine-131 analysis was unable to performed on air sample station AS-1 for the period of 07/27/93 - 08/03/93 due to insuflicient flow. Gross beta and Iodine-131 analysis was unable to performed on air sample station AS-1 for the period of 08/10/93 - 08/17/93 due to insufficient flow. Gross beta and Iodine-131 analysis was unable to performed on air sample station AS-6 ; for the period of 09/14/93 - 09/21/93 due to insufficient flow. Gross beta and Iodine-131 analysis was unable to performed on air sample station AS-11 for the period of 11/16/93 - 11/23/93 and 11/23/93 - 11/30/93 due to a blown fuse. Lab numbers followed by a ending of"GG" denotes a duplicate sample.
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