Text

PBAPS Annual Radiological Environ Operating Rept,Rept 55 for Jan-Dec 1997
	ML20248E180
Person / Time
Site:	Peach Bottom
Issue date:	12/31/1997
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20248E170	List: ML20248E165; ML20248E180;
References
	55, NUDOCS 9806030204
	Download: ML20248E180 (130)
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. . . .

Docket No: 2 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 and 3 Annual Radiological Environmental Operating Report Report #55 1 January Through 31 December 1997 Prepared By v

PECO Nuclear a Unit of PECO Energy 965 Chesterbrook Blvd.

Wayne, PA 19087-5691 May 1998

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Docket No:

PEACH BOTTOM ATOMIC POWER STATION UNITS 2 and 3 Annual Radiological Environmental Operating Report Report #55 1 January Through 31 December 1997 Prepared By v

PECO Nuclear 96 hes er r o Bk.

Wayne, PA 19087-5691 May 1998 I

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TABLE OF CONTENTS

l. Summary and Conclusions,,,,,,,, , , ... . .. . . . . . . . . . . . , . . . . . . , ,, ........,..1 11, introduction.,,,,, ,,,, ........ . . ... . . . . . . . . . . . . . . . . . , ... . . . , , . . . . ,,,,...3 A. Ob'ectives......

J . , , . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . ......3 B. Implementation,. , , . . . . . . . . . . , , . . . .. . . . . . . . . . . . . . . . . . . .. ,3 Ill. Program Description ... .... . .. .... ... ., , , , . . . . . . . .. . . . . . . . . . . . . ..............4 A. Sample Collection .. . .. , ..... . ... . .... . ... , , . . . . . . . , , , , , . . . . . . , , , ,,.....4 B. Data Interpretation ..... .... . . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . , , ..........,,.........6 C. Program Exceptions.......... .. . . , , , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

...........7 D. Program Changes... .. .. .. . ............ , , , , . . . . . . . . . . , , , , , , . . . . . . . . . . . . . . . . . . . . .,....8 IV. Results and Discussion ..... ......... , . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... 8 A. Aquatic Environment........................., ,, . . . . . . . . , , . . . . . . . . . . . . . . . . . . . . . . . , ,.............8

1. S urface Water. . . . . . , , , , . . . . . . , , , , , ,, . . . . . . . . . . . . . . . . . . . . . . . , , , , . . . . , , , , . . . . . . . . . , . . . . . . 8

2. Drinking (Potable) Water. . . . , , . . . . .. . ,,, .. . , . . .... . . . .. .. . . . .. .. . . . . .. . .. . . . . . . .. . .. . . . . . ,,,8

3. Fish..,,,..................,,.................,......,..........,,.................,,,....9 4 . S e d i me nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . , . . . . . . 9 B. Atmospheric Environment........ ..............................,,.,.......................10

1. Airborne..... . . . , , . . . . . . . . . . . . . ............................... . . . . , . . , . . . . 10 a, Air Particulate. . . . . . . . . . . . . . . . . . . , , , . . . . . . . . . . . . . . . . . , , . . . . . . . . . . . . . . . . . . 10

b. Airbome lodine.., , , . .

, , . . , , ... . . . . . . , , , , , , , , . . . . , , . . . 11

2. Terre stri a l . . . . . . , , ,, , . . . . . . . . . . . . . . , , . . . , . . . . . . . . . , , .. , . . . . .. . . . . . . . . . . . , . . 1 1

a. Milk . ... .... .. .......,,..,,...........................,,,............. ,11 C. Ambient Gamma Radiation... ... ... ...., ,, , .. . . . . . . , , , , , . . , , , . . . . , , , . . . . . . . . , . . . . . .. 12 V. Reference s . . . ,,. . . . . . . . . . , , ,, , . . . . , . . . , , , . . . . . . . . . . . . . . . . . . . . , . . . ,,13 I

Appendix A - Radiological Environmental Monitoring Report Summary Appendix B - Sample Designation and Locations 1

1 Appendix C - Data Tables and Figures - Primary Laboratory Appendix D - Data Tables and Figures - OC Laboratory Appendix E - Synopsis of Analytical Procedures Appendix F - Quality Control- EPA Intercomparison Program Appendix G - PBAPS Surveys ii

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1. Summary and Conclusions '

This report on the Radiological Environmental Monitoring Program conducted for the Peach Bottom Atomic Power Station (PBAPS) by PECO Nucleer covers the period 1

' January 1997 through 31 December 1997 During that tima period,1000 analyses were performed on 896 samples.

Surface water samples were analyzed for concentrations tritium and gamma emitting nuclides. No fission or activation products were found. Tritium activities detected were consistent with those observed in other years.

Drinking (potable) water samples were analyzed for of concentrations of gross beta (soluble and insoluble fractions), tritium, and gamma emitting nuclides. No fission or activation products were found. . Gross beta and tritium activities detected were consistent with those observed in other years.

The remaining sample media representing the aquatic environment included fish

- and sediment samples. These media were analyzed for concentrations of gamma emitters. Fish samples showed no measurable effects from the operation of PBAPS.

Sediment Location 4J, located below the discharge, showed the activation product Co-60 which was attributable to PBAPS operations. Cesium-137 activity was found at all locations and was consistent with data from previous years. The dose to a teenager's skin from the sediment pathway was calculated to be 7.41 E-04 mrem /yr which represents 0.004% of the allowable fraction of 10 CFR 50, Appendix I limits.

The atmospheric environment was divided into two parts for examination: airborne and . terrestrial. Sample media for determining airborne effects included air particulate and air iodine samples. Analyses performed on air particulate samples included gross beta and gamma spectrometry The results from both analyses were consistent with results from the previous years. Furthermore, no notable differences !

between control and indicator locations were observed. These findings indicate no _

i measurable effects from the operation of PBAPS.

High sensitivity _ lodine-131 analyses were performed on weekly air samples. All results were less than the minimum detectable activity.

t i f Examination of the terrestrial environment was accomplished by analyzing milk samples for concentrations of lodine-131 and gamma' emitters. Results from all i analyses were consistent with those from ~ previous years and showed no indication d of any PBAPS effect.

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Ambient gamma radiation levels were measured quarterly throughout the year. All '

measurements were below 10 mR/std. month and consistent with those measured in i previous years.

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In assessing all the data gathered for this report and comprising these results with preoperational data, it was evident that the operation of PBAPS had no adverse impact on the environment.

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ll, introduction Peach Bottom Atomic Power Station (P3APS) is located along the Susquehanna River between Holtwood and Conowingo Dams in Peach Bottom Township, York County, Pennsylvania. The initial load ng of fuel into Unit 1, a 40 MWe (net) high temperature, gas-cooled reactor, began on 5 February 1966, and initial criticality was achieved on 3 March 1966. Shutdown of Peach Bottom Unit 1 for decommissioning was on 31 October 1974. For the purposes of the monitoring program, the beginning of the operational period for Unit 1 was considered to be 5 February 1966. A summary of the Unit 1 preoperational monitoring program was

. presented in a previous report *. PBAPS Units 2 and 3 are boiling water reactors, each with a power output of approximately 1159 MWe. The first fuel was loaded into Peach Bottom Unit 2 on 9 August 1973. Criticality was achieved on 16

- September 1973, and full power was reached on 16 June 1974. The first fuel was loaded into Peach Bottom Unit 3 on 5 July 1974. Criticality was achieved on 7 August 1974, and -full power was first reached on 21 December 1974.

Preoperational summary reports A for Units 2 and 3 have been previously issued and summarize the results of all analyses performed on samples collected from 5 February 1966 through 8 August 1973.

A. Objectives The objectives of the REMP are:

1. To identify, measure, and evaluate existing radionuclides in the environs of PBAPS site and any fluctuations in radioactivity levels

~which may occur.

2. To monitor and evaluate ambient radiation levels

3. .To determine within the scope of the program, any measurable quantity of radioactivity introduced to the environment by the operation of PBAPS.

B. Implementation implementation of the stated objectives is accomplished by identifying-significant exposure pathways,- establishing baseline radiological data of media within those pathways, and monitoring those media during plant operation to assess plant effects (if any) on man and the environment.

r in order to achieve the stated objectives, the current programs include the following analyses on samples collected:

1. Concentrations of beta emitters in drinking (potable) water, and air l

particulate.

2. Concentrations of gamma emitters in surface and drinking (potable) water, air particulate, milk, fish, and sediment.

3. Concentrations of tritium in surface and drinking (potable) water.

4. Concentrations of I-131 in air and milk.

5. Ambient gamma radiation levels at various site environs.

t Ill. Program Description A. Sample Collection This section describes the collection methods used to obtain environmental samples for the PBAPS REMP in 1997. Samples for the PBAPS REMP were collected for PECO by Normandeau Associates, RMC Environmental Services Division. (RMC). Sample locations and descriptions can be found in Table B-1 and Figures B-1 through B-3, Appendix B.

Aauatic Environment The aquatic environment was examined by analyzing samples of surface water, drinking water, fish, and sediment. Surface water from two locations (1LL and 1MM) were collected weekly by automatic sampling equipment.

Drinking water from two locations (4L and 61) were collected weekly from a tank at each location Both surface and drinking water samples were each composited into separate monthly sample for analysis. Two quarts of water are removed from the tank each week and placed into a clean two-gallon polyethylene bottle to form a monthly composite. Control locations were 1LL and 61.

Fish samples comprising the flesh from two groups: Bottom Feeder (catfish) and Predator (smallmouth bass, largemouth bass, or bass) were collected semiannually at two locations: 4 (indicator) and 6 (control) using several methods such as trapnet, seine or electroshocking.

Sediment samples composed of recently deposited substrate were collected semiannually at three locations: 4J, 4T (indicators), and 6F (control) using one of two methods, determined by the depth from which the sediment was obtained. In water greater than 4 feet deep, sediment was collected by either a Ponar or Ekman Grab with a surface area of 81 square inches. In shallow

l water (1-4 feet), sediment was collected by scooping up mud with a plastic bucket.

Atmospheric Environment The atmospheric environment was examined by analyzing airborne and terrestrial samples. These consisted of air particulate, airborne iodine, and milk. Air particulate and air iodine samples were collected and analyzed weekly from five locations (1 B,1Z, 2, 3A, and 5H2). The control location was 5H2. Air samples were obtained using a vacuum sampler, glass fiber and charcoal filters, respectively. The filters were replaced weekly and sent to the laboratory for analysis. The vacuum samplers were run continuously at approximately 1 cubic foot per minute.

Milk samples were collected from five locations (A, G, J, O and R) monthly from December through March and biweekly April through November.

Additionally, samples from six locations (B, C, D, E, L, and P) were collected quarterly. Locations A, B, C, and E were controls. Milk samples were obtained by removing two gallons from the dairyman's bulk tank after mixing.

The sample from each location was therefore a composite of all the milk collected from the dairy herd (from 1 to 3 milkings). The milk was scooped from the agitated bulk tank and placed in new plastic containers.

Ambient Gamma Radiation Direct radiation measurements were made using Panasonic 801 calcium sulfate (CaSO4) thermoluminescent dosimeters (TLD). The TLD locations were placed on and around the LGS site as follows:

A site boundary rina consisting of thirteen locations (1L,1A,2,11,1C, 1J, 1 F, 40, 1NN,1H,1G,1B, and 1E) near and within the site perimeter representing fencepost doses (i.e., at locations where the doses will be potentially greater than maximum annual off-site doses) from LGS release.

An intermediate distance rina consisting of nineteen locations (15, 22, 44, 32, 45.14,17, 31 A, 4K, 23, 27, 48, 3A, 49, 50, 51, 26, 6B, and 42) extending to approximately 5 miles from the site designed to measure possible exposures to close-in population.

The balance of eight locations (43, 5,16,24,46,47,18, and 19) representing ,

control and special interests areas such as population centers, schools, etc. '

The specific TLD locations were determined by the following criteria: l 1

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1. The presence of relatively dense popu!ation;

2. Site meteorological data taking into account distance and elevation for each of the 36 ten-degree sectors around the site, where estimated annual dose from PBAPS, if any, would be more significant;

3. On hills free from local obstructions and within sight of the vents (where practical);

4. Near the dwelling closest to the main stack in the prevailing down wind direction.

A TLD set was placed at each location in a locked formica " birdhouse" or polyethylene jar located approximately six feet above ground level. The TLD sets were exchanged monthly and quarterly, then sent to the laboratory for analysis.

B. Data interpretation Several factors are important in the interpretation of the data. These factors are discussed here to avoid undue repetition in the discussion of the results.

1. Lower Limit of Detection and Minimum Detectable Activity The lower limit of detection (LLD) was defined as the smallest concentration of radioactive material in a sample that would yield a net count (above background) that would be detected with only a 5% probability of falsely concluding that a blank observation represents a "real" signal. The LLD was intended as a before the fact estimate of a system (including instrumentation, procedure and sample type) and not as an after the fact criteria for the presence of activity. All analyses were designed to achieve the required PBAPS detection capabilities for environmental sample analysis.

The minimum detectable activity (MDA) is defined above with the exception that the measurement is an after the fact estimate of the presence of activity.

2. Net Activity Calculation and Reportino of Results Net activity for a sample was calculated by subtracting background activity from the sample activity. Since the REMP measures extremely small changes in radioactivity in the environment, background variations will result in sample activity being lower than

the background activity effecting a negative number. For a more detailed description of the result calculations, see Appendix E.

Results for each type of sample were grouped according to the analyses performed. For gamma analyses, fifteen nuclides (Be-7, K-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Zr-95, Nb-95, Cs-134, Cs-137, Ba-140, La-140, Ra-226 and Th-232) were reported.

Annual means and standard deviations of the individual results L

were calculated. The standard deviation represent the variability of measured results for different samples rather than the single analysis uncertainty.

l C. Program Exceptions i

For 1997 the PBAPS REMP nad a sample collection recovery rate of better l than 99%. The exceptions to this program are listed below.

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! 1. The first quarter TLDs from location 6B was recovered wet from its holder. The TLDs were not read.

2. Surface water sampler at location 1MM was out of service for the following dates: 01/15/97 to 03/05/97 due to adverse weather and from 12/10/97 to 12/13/97 due to electrical problems. Daily grab L

samples were taken.

3. Surface water sampler at location 1LL was out of service for the following dates: 01/15/97 to 03/05/97 due to adverse weather and from 06/23/97 to 06/27/97 due to mechanical problems. Daily grab samples were taken.

4. Drinking water sampler at location 4L was out of service on 03/21/97 and 11/21/97 due to mechanical problems and from 12/19/97 to 01/04/98 for pump replacement.

Each program exception was reviewed to understand the causes of the l program exception. Sampling and maintenance errors were reviewed with the personnel involved to prevent a recurrence. Occasional equipment

breakdowns and power outages were unavoidable. The overall sample recovery ra;e indicates that the appropriate procedures and equipment are in place to assure reliable program implementation.

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D. Program Changes There were no program changes to the 1997 PBAPS REMP:

IV. Results and Discussion

'A. Aquatic Environment

1. Surface Water Samples were collected from two locations monthly (1LL and 1MM).

1LL served as the control location. The following analyses were performed Tritium Samples from both locations were analyzed for concentrations of tritium (Table C-l.1, Appendix C). Results ranged from -3 to 180 pCi/l and averaged 68 pCi/l at the control location and 47 pCi/l at the indicator location. Concentrations found were lower than those obsented during the preoperational period.

Gamma Spectrometry Samples from both locations were analyzed for concentrations of gamma emitters (Table C-l.2, Appendix C). No statistically significant fission or activation products were found.

2. Drinkina (Potable) Water Samples were collected from two locations monthly (4L and 61). 61 .

served. as the control location. The following analyses were performed Gross Beta Samples from both locations' were analyzed for concentrations of gross beta activity in insoluble and soluble fractions (Tables C-II.1 and C-II.2 and Figures C-1 and C-2, Appendix C). Gross beta activity in the insoluble fraction ranged from -1.9 to 3.9 pCi/l. The values in the soluble fraction ranged from -1.4 to 4.3 pCi/l. No differences'were observed between the means of the control and indicator stations.

The values were generally below those seen in the preoperational period..

1 l Tritium Samples from both locations were analyzed for tritium concentration

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quarterly (Table C-II.3, Appendix C). The values for the indicator

. location (4L) ranged from 30 to 16n ,nCi/l with a mean of 74 pCill.

Control location (61) values rangeo n om -25 to 92 pCill with a mean of 36 pCi/l. The concentrations found were lower than those observed ~

during the preoperational period.

Gamma Spectrometry Samples from both locations were analyzed for concentrations of gamma emitters (Table C-II.4, Appendix C). ). No statistically significant fission or activation products were found.

, 3. Fish Samples were collected from two locations semi-annually (4 and 6).

The control location was 6. The following analyses were performed.

Gamma Spectrometry Statistically significant activity was observed only for the nuclide K-40 which ranged from 2500 to 3600 pCi/kg (wet) (Table C-!':.'., Appendix C). . No statistically significant fission or ~ activation products were found. Figure C-3 illustrates the Cs-137 activity for indicator and control locations from the beginning of the operational period through the . present. Cesium-137 activity has' declined to non-detectable levels.

4.- Sediment Samples were collected from three locations semi-annually (4J, 4T-

and 6F). The control location was 6F. The following analyses were peiferired.

Gamma Spectrometry Samples- from all locations ware analyzed for concentrations of l 1

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gamma emitters (Table C-IV.1, Appendix C). Statistically significant I i

activity for naturally ~ occurring Be-7, K-40, Ra-226 and Th-228 was found at all locations. K-40 results ranged from 8,200 to 22,000 PCi/kg (dry).

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i Statistically significant activity for the Plant produced nuclide Co-60 was found in one sample from the indicator location 4J located downstream of the discharge. The results ranged from -4 to 50 pCi/kg (dry) for the indicator locations and -1 to 6 pCi/kg (dry) for the control location. Statistically significant activity for Cs-137 was found at all locations with a mean value of 141 pCi/kg (dry) for the indicator locations and 27 pCi/kg (dry) for the control location. The maximum calculated dose from this pathway to a teenager's skin was 7.41 E-04 mrem /yr. This_value.is based upon the assumption the maximum concentrations of Co-60 and Cs-137 at the downstream location (4J) were present the entire year. This dose represents 0.004% of the allowable fraction of 10 CFR 50, Appendix 1 limits. Results found were consistent with those from previous years. Figure C 4, Appendix C illustrates the comparison of activities of Cs-137 detected at the control location and indicator locations from the preoperational period through the present.

B. Atmospheric Environment

1. Airborne

a. Air Particulate Samples were collected from five locations (18,1Z, 2, 3A, and 5H2). Control location was 5H2. The following analyses were performed Gross Beta Samples from all locations were analyzed for concentrations of gross beta (Tables C-V.1 and C-V.2 and Figures C-5 and C-6, Appendix C). Air particulate locations were divided into three groups: Group I, consisting of 1B,1Z, and 2, located on site at PBAPS; Group 11, comprised of 3A, located at an intermediate distance from PBAPS; and Group lil, consisting of SH2, located at a remote distance from PBAPS. Comparison of results among these three groups aids in determining the effects, if any, resulting from the operation of PBAPS. The results from site location samples ranged from 7 to 44 E-3 pCi/m', with a mean of 17 E-3 pCi/m'. The results from intermediate distance IJeation ranged from 5 to 29 E-3 pCi/m', with a mean of 16 E-3 pCi/m*. The results from the distant location ranged from 7 to 31 E-3 pCi/m', with a mean of 16 E-3 pCi/m'. Comparison of the values indicate no notable difference among the three I

groups suggesting no effects from the operation of PBAPS (Figure C-5, Appendix C).

Gamma Spectrometry

-Weekly samples from five locations (1B,1Z, 2, 3A, and 5H2) were composited and analyzed quarterly for the presence of gamma emitters (Table C-V.3). Naturally occurring Be-7 was found in all samples with activity values similar to those from the preoperational years. No statistically significant activation orfission products were detected.

b. Airborne lodine Continuous air samples were collected weekly at five locations l (1B,1Z,2, 3A, and SH2) and analyzed for 1-131 (Table C-VI.1, Appendix C). All results were less than the minimum detectable activity.

2. Terrestrial

a. Milk Samples were collected from eleven locations (A, B, C, D, E, G, J, L, 0, P and R). Farms A, B, C, and E were control locations. The following analyses were performed lodine-131 Samples from all locations were analyzed for concentrations of I-131 (Tables C-Vil.1, Appendix C). All results were less than the minimum detectable activity and ranged from -0.2 to 0.3 pCi/l.

Gamma Spectrometry

Samples from five locations were analyzed quarterly .for

concentrations for ' gamma (Table . C-Vil.2, emitters l

Appendix C). Naturally occurring K-40 was found in all l samples with values ranging from 1,200 to 1,500 pCi/l. All l other nuclides searched for were less than the minimum i

. detectable activity. Figure C-7 (Appendix C) illustrates the

'Cs-137 activity in milk from the beginning of the operational

- _ _ _ _ _._--_ ___ . - - - . - -. -)

l period through the present. Cesium-137 activity has declined to non-detectable levels.

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Ambient Gamma Radiation C.

Ambie.:.t gamma radiation levels were measured quarterly at forty locations (as described in the program description section) using Panasonic 801 (CaSO4) thermoluminescent dosimeters (Tables C-Vill.1 through C-Vill 3 and Figures C-8 and C-9, Appendix C). All TLD readings were below 10 mPlstd.

month with a range of 3.3 to 7.5 mR/std. month. No notable differences were observed between the site, intermediate, and distant TLD groupings.

VI. References

1. Preoperational Environs Radioactivity Survey Summary Report, March,1960 through January,1966. (September 1967).

2. Interex Corporation, Peach Bottom Atomic Power Station Regional Environs l Radiation Monitoring Program Preoperational Summary Report, Units 2 and l-3, 5 February 1966 through 8 August 1973, June 1977, Natick,

Massachusetts.

3. Radiation Management Corporation Publication, Peach Bottom Atomic Power Statien Preoperational Radiological Monitoring Report for Unit 2 and 3, l January,1974, Philadelphia, Pennsylvania.

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4 APPENDIX A RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT

SUMMARY

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N E OP MA QWVT EOE E L T RLLD AA Y, C MNT I

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OTO R S ER 9 LTC E SO 5 1

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D R UNE A HO CY NAP RAE P:

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I T L YL R TI E I C T LA I

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T D N/ S E ON I E L T P T, AG M N I T

DN A E

_ RS M AE

_ OY E RO M AF R TR UWOU I HTS A CI E LL D

EAT IN E RI U D( M I

MP(M

4 i

i

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l APPENDIX B I'

SAMPLE DESIGNATION '

AND LOCATIONS l

4 I

l l

l l-l l

APPENDIX B: SAMPLE DESIGNATION AND LOCATIONS LIST OF TAbtE0 AND FIGURES TABLES TABLE B-1: Sample Collection and Analysis Program for the Radiologicd Environmental Monitoring Program, Peach Bottom Ator . ower Station,1997 FIGURES FIGURE B-1: Environmental Sampling Locations on Site or Near the Peach Bottom Atomic Power Station,1997 FIGURE B-2: Environmental Sampling Locations at Intermediate Distances from the Peach Bottom Atomic Power Station,1997 FIGURE B-3: Environmental Sampling Locations at Remote Distances from the Peach Bottom Atomic Power Station,1997 l

l' r

B -i l

l l

l t

- C U E P P G a U G B*

TE

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P -

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L mP G mno t t

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l

& y e ly r l) m n

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s r a - s a B m- B a s a a a g lyof mm e s

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cu m sm e m e n ar n e mu t r

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i n

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l r e t

C oolo t eh c is ain e lp e twct t

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mh e r wcla on a aid qaluiy mtat h n h a m ht o ot ma o T agc S Wwa2d oa r ps WHcqac o ou2 o ist or f Fb o S m

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s s s C w H c toS e s in ae le le in laio ni acP li m im i

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6 5

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en V s s s s s s s s le yn c oS e e e le H e le R e le lai o ni t P

i m

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P m m m m m n r m m im m m im im im im nt 9 2 5 9 8 3 AtSa t

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cc o r u o o a ip P iv t

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loo s e a f E w o P ,

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amwo r

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s e

r DS W k t Su HS auB B c F (C R m e

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ENE WNW

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elg s

Figure B-1 Environmental Sampling Locations Within One Mile of the Peach Bottom Atomic Power Station,1997 B-7

" N 61 NW 43 NNE 7 I

N?f 42e N NW f

.\ % *15 NE 22 ENE w

% y i(

n- E

G 23 4J ,

17 v) -

N s WSW 7/* e3A b ESE

31A

/

8 46 8h 47' 48 f ssW S WLE R AGO- S 'k

'y S N -

13;

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l Figure B-2 Environmental Sampling Locations Between One and Approximately Five Miles of the Peach Bottom Atomic Power Station,1997 8-8

4 0

\

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c

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h i

l APPENDIX C DATA TABLES AND FIGURES PRIMARY LABORATORY l

)

L

APPENDIX C: DATA TABLES AND FIGURES - PRIMARY LABORATORY TABLES Table C-l.1 Concentrations of Tritium in Surface Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-l.2 Concentrations of Gamma Emitters in Surface Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-II.1 Concentrations of Gross Beta Insoluble in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-II.2 Concentrations of Gross Beta Soluble in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-II.3 Concentrations of Tritium in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-II.4 Concentrations of Gamma Emitters in Drinking Water Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-Ill.1 Concentrations of Gamma Emitters in Fish Samples Collected in the Vsinity of Peach Bottom Atomic Power Station,1997.

Table C-IV.1 Concentrations of Gamma Emitters in Sediment Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-V.1 Concentrations of Gross Beta in Air Particulate Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-V.2 Monthly and Yearly Mean Values of Gross Beta Concentrations (E-3 pCi/cu. meter) in Air Particulate Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-V.3 Concentrations of Gamma Emitters in Air Particulate Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-VI.1 Concentrations of I-131 in Air lodine Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-Vil.1 Concentrations of I-131 in Milk Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

C-i

Table C-Vil.2 Concentrations of Gamma Emitters in Milk Samples Collected in the Vicinity of Peach Bottom Atomic Power Station,1997.

Table C-Vill.1 Quarterly TLD Results for Peach Bottom Atomic Power Station,1997.

Table C-Vill.2 Mean TLD Results from Peach Bottom Atomic Power Station Site Boundary, Middle, and Outer Rings,1997.

Table C-Vill.3 Summary of the Ambient Dosimetry Program for Peach Bottom Atomic Power Station,1997.

Table C-lX.1 Summary of Collection Dates for Samples Collected in the Vicinity of Peach Bottom Power Station,1997.

FIGURES Figure C-1 Monthly Insoluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of PBAPS,1997.

Figure C-2 Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Collected in the Vicinity of PBAPS,1997.

Figure C-3 Mean Annual Cs-137 Concentrations in Fish Samples Collected in the Vicinity of PCAPS, 1971-1997.

Figure C-4 Mean Semi-Annual Cs-137 Concentrations in Sediment Samples Collected in the Vicinity of PBAPS,1971-1997.

Figure C-5 Mean Weekly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of PBAPS,1997.

Figure C4 Mean Monthly Gross Beta Concentrations in Air Particulate Samples Collected in the Vicinity of PBAPS,1970-1997.

Figure C-7 Mean Annual Cs-137 Concentrations in Milk Samples Collected in the Vicinity of PBAPS, 1971-1997.

Figure C-8 Mean Quarterly Ambient Gamma Radiation Levels (TLD) in the Vicinity of PBAPS, 1973-1997.

C - ii

S. I TABLE C l.1 CONCENTRATIONS OF TITIUM IN SURFACE WATER SAMPLES COLLECTED )

IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 I RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 1LL 1MM PERIOD 1 JAN-MAR 18 iS8 18 158 APR-JUN 62 i60 46 ISO )

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TABLE C.4L1 CONCENTRATIONS OF GROSS BETA INSOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L 61 PERIOD JAN 0.5208 08108 FEB 0.1 21.0 0.3 21.0 MAR 1.3 to 6 0.2 to 5 APR -1.9 21.0 1.5 21_0 MAY -0.5 to.9 -0.7 20.9 JUN 0.5 21.0 0.5 21.0 JLiL 0820.9 0420.8 AUG -0.3 to 9 -0.6 to B SEP -0 9 11.3 -1.3 11.3 OCT 0521.1 0.7 21.1 NOV 0.3206 0.5 10.6 DEC 2.7 21.1 3.9 *1.2 MEAN 0.3 12.3 0.3228 TABLE 11.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 )

RESULTS IN UNITS OF PCl/ LITER +I 2 SIGMA l

l COLLECTION 4L 61 PERIOD JAN 1.9 21.0 2.5 21.1 FEB 1.2 21.2 0 8 11.2 MAR 1.2 to 6 1.6 20.6 APR 1.3 21.1 1.6 21.1 MAY 1.9 11.1 1.8 11.1 l

JUN 2.3 21.0 2.5 21.0 JUL 1.7 11.1 3.6 21.2 AUG 2.5 21.4 2.1 21.4 SEP 1.3 21.4 2.6 21.5 OCT 4.3 21.5 3.7 11.5 NOV 1.7209 1.5209 DEC -0.5 21.5 1 4 11.4 MEAN 1.7 12.2 1.9 12.7 TABLE 11-3 CONCENTRATIONS OF TRITIUM IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L 61 PERIOD JAN-MAR 37 159 -25 257 APR-JUN 67 160 56 260 JUL-SEP 160 270 92 270

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l l TABLE C-V.1 CONCENTRATIONS OF GROSS BETA IN AIR PARTICULATE SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 RESULTS IN UNITS OF E 3 PCl/CU METER +/-2 SIGMA GROUPI GROUP ll GROUP ll1 WEEK NO 1B 12 2 3A SH2 1 18 14 23 25 17 24 22 25 16 24 2 1414 14 24 1424 1324 16 14 3 23 14 21 14 25 t5 29 15 17 24 4 17 24 17 24 22 24 17 24 21 24 5 17 23 13 13 20 24 1423 18 24 6 17 24 13 4 13 24 10 4 17 24 7 16 23 11 24 14 24 12 24 1524 8 20 25 22 25 23 25 20 15 14 24 9 12 24 10 13 11 24 10 t4 14 23 10 9 13 7 13 7 23 7 23 15 24 11 19 24 14 23 14 23 15 13 20 24 12 16 24 16 24 17 25 14 4 13 24 13 9 13 13 24 14 24 9 13 10 24 14 14 24 15 24 15 14 12 24 14 t4 15 18 25 17 25 15 24 1815 13 t4 16 18 24 19 24 17 24 19 24 19 t4 17 14 14 10 t4 1424 11 14 12 24 18 9 t4 10 24 8 24 10 24 16 t4 19 19 15 15 t5 14 t4 1525 1224 20 14 t4 13 24 18 24 12 to 14 24

9 24 8 24 10 24 10 4 8 13 10 23 13 23 13 t3 12 23 11 24

. 8 23 7 13 7 23 9 13 7 23 24 12 23 11 23 12 23 12 23 1523 25 13 24 11 24 15 24 1014 17 24 26 12 23 23 14 24 24 22 24 22 24 27 16 24 13 24 11 24 12 24 17 210 28 14 14 17 24 19 24 15 24 18 25 29 27 24 24 25 24 24 22 24 22 24 l 30 11 23 1424 12 13 13 24 1424 31 1824 16 24 16 24 14 24 1924 32 19 24 19 24 1524 16 24 17 24 33 25 24 20 24 27 24 24 t4 18 24 34 14 24 11 24 15 24 15 14 12 24 35 16 14 14 24 13 14 12 4 15 23 36 20 t4 19 t4 17 t4 15 23 16 25 37 17 t4 18 24 21 24 18 24 1624 38 24 24 21 14 28 14 23 24 29 24 39 17 24 1624 17 24 19 24 1224 40 16 24 20 24 14 24 15 14 22 24 41 36 26 44 26 33 26 29 26 21 14 42 22 24 26 4 21 4 23 24 21 t4 43 19 25 15 25 25 25 1825 8 24 44 17 25 18 25 20 25 15 24 16 24 45 13 13 1323 17 t4 14 23 11 24 46 15 25 11 15 12 25 9 15 11 24 47 21 24 21 14 23 24 19 24 1924 48 24 24 20 24 22 24 23 24 15 24 49 20 23 1613 15 13 17 23 1024 50 10 4 10 24 10 24 5 24 12 23 51 24 24 22 24 22 24 21 24 31 25 52 15 24 1814 1524 1824 1324 53 17 25 21 26 10 15 12 25 N/A MEAN 17 211 16 212 17 211 16110 1629 C-7

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TABLE C-VI.1 CONCENTRATIONS OF l-1311N AIR LODINE SAMPLES COLLECTED IN THE VICINITY OF PE BOTTOM ATOMIC POWER STATION,196T RESULTS IN UNITS OF E-3 PCl/CU METER +/ 2 SIGMA GROUP 11 GROUP lli GRObdi 2 3A 5H2 WEEK NO 1B 1Z

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TABLE C-Vil.1 QUARTERLY TLD RESULTS FOR PEACH BOTTOM ATCMIC POWER STATION,1997 RESULTS IN UNITS OF MILLl-ROENTGEN /STD. +/. 2 SIGMA STATION MEAN CODE +/- 2 S D JAN-MAR APR-JUN JUL-SEP OCT-DEC 1A 5.2 to 4 5 4 iO.6 5 t0 9 5.3 20.2 5 20.3 1B 46104 4720.5 47204 4.7 20.2 4.3 to 4 1C 5920.7 6.1204 5821.2 6.1 20.9 5420.3 1E 53205 5620.4 5.2 20.7 5.3 to 6 5 to 4 1F 67206 6910.6 6.5204 7 t0.2 6.3 20.7 1G 4120.5 4520.4 4.2 20.3 4.1206 3 8 t0.5 1H 56106 5.7204 5720.9 5 9 to.2 5.2 20.1 il 4420.5 4720.2 4320.3 4.5204 4.2 to.5 IJ 6421.1 7.1 t1.1 6104 6.5 20.6 5920.3 IL 44208 49204 45204 4.1 20.3 4120.5 2 5420.3 55204 5.5 21.0 5 4 to 4 5.2206 3A 4 to 4 4.3 20.1 4 20.7 3.7 20.3 3920.3 4K 3520.3 37201 3.5 20.2 3 4 to.2 3.3 10.3 5 5.3204 5.5209 5.30.5 54205 5 20.9 1NN 64206 68208 6.1207 6.5 20.2 6420.3 6B 4520.6 (2) 4820.4 4.2 20.1 44*0.3 14 5.6 20.5 5.8 to 3 56206 5.7 20.1 5.2 20.7 15 5920.2 6 t0.3 6 to.3 5820.1 5.8 20.6 16 6104 6.3203 5 8 to.5 6204 5.9 20.5 17 65205 69 0.7 6.3 20.4 6.6 20.5 6.3 20.7 18 6.2205 6.5 20.3 5.9 t0.3 6.2 to 6 6.1 20.3 19 59204 6.2204 5.7 20.3 6 20.4 5.8 21.2 22 61204 6.2 to.6 6 to 4 5 8 to.7 6.2 20.5 23 6203 6 20.3 5.9204 6.2 20.9 5.9 20.8 24 4.5 to 4 48204 4.3 20.7 46203 4.5 20.5 26 6.3208 6.7108 5.8204 6410.3 6410.3 27 5.7204 58103 56204 5.9 20.8 54204 31A 4.2 10.5 4 3 t0.2 4204 45204 4 20.3 32 6120.9 6.4 20.6 5620.5 6.5 20.4 5920.3 40 7 20.9 7.2 10.3 6.7 10.3 7.5 20.3 6.7 20.5 42 47106 5.1204 4.5203 4 7 to 4 46 08 43 6 4 to7 64204 6 10.4 6820.2 6.5 to 6 44 5320.5 5520.5 5 20.2 5.5 20.2 5.2 to.3 45 6207 5820.3 5820.5 65204 5.9 20.2 46 5.2207 5204 4.8 20.7 55204 5.3208 47 64208 6720.3 5.9204 6810.7 6.3203 48 5.9204 6.1204 5620.5 6120.2 5.9 20.5 49 5820.5 6.1 to 4 5.5 20.1 5.8 20.3 5820.2 50 68to7 7.3 20.1 6.5203 6.8 20.5 6.6204 51 5.9 to 5 6 to.1 56to5 6.2 to 4 5.9 to.7 (1) Mean and two times the standard deviation of the quarterly results (2) See Program Exceptions Section for explanation C - 13

N A 7 3 8 E .

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7E S T S PY 1 9T T 5 5 5 5 UT E 9I EF I ML T -

1 S RO S SA R A SN A L A

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T T R A A AY T T 3 RRS EA S

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l l G G P D G G l

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T E P J A J O T L S M O

i TABLE C4X.1

SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATK%t,1997 ;

l i

SURFACE WATER (TRITIUM) 1 l

COLLECTION 1LL 1MM PERIOD JAN-MAR 12/31/96 04/02/97 12/31/96 - 0402/97 )

APR JUN 04/02/97 - 07/02/97 04/02/97 - 07/02/97 JUL SEP 07/02/97 - 10/01/97 07/02/97 - 10/01/97 i l

OCT-DEC 10/01/97 12/31/97 10/01/97 - 12/31/97 SURFACE WATER (GAMMA SPECTROSCOPY)

COLLECTION 1LL 1MM PERIOD JAN 12/31/96 - 01/29/97 12/31/96 - 01/29/97 FEB 01/29/97 - 02/26/97 01/29/97 02/26/97 MAR 02/26S7 - 0402/97 02/26/97 - 04/02/97 APR 04/02/97 04/30/97 04/02/97 - 04/30/97 MAY 04/30/97 - 05/28/97 04/30/97 - 05/28S 7 JUN 05/28/97 07/02S7 05/28/97 - 07/02/97 JUL 07/02/97 07/30/97 07/02/97 - 07/30/97 AUG 07/30/97 - 09/03/97 07/30/97 - 09/03S7 SEP 09/03/97 10/01/97 090 3/97 - 10/01/97 (

OCT 10/01/97 10/29/97 10/01/97 10/29/97 l NOV 10/29/97 - 12/03/97 10/29/97 - 12/03/97 I DEC 1203/97 - 12/31/97 12/03/97 - 12/31/97 DRINKING WATER (TRITlUM)

COLLECTION 4L 61 PERIOD j JAN-MAR 01/03/97 - 04/0497 01/03/97 - 04/03/97 i APR-JUN 04/04/97 - 07/03/97 0403/97 - 07/03/97 JUL-SEP 07/03/97 - 1003/97 07/03/97 - 10/03/97 l OCT-DEC 10/03/97 - 01/04/98 10/03/9/ - 01/03/98 l DRINKING WATER (GROSS BETA & GAMMA)

COLLECTION 4L 61 l PERIOD JAN 01/03/97 02/01/97 01/03 S 7 - 0201/97 FEB 02/01/97 - 02/28/97 02/01/97 - 02/28/97 MAR 02/2BS7 - 04/04/97 02/28/97 - 04/03/97 APR 04/04S7 05/02/97 0403/97 - 05/02/97 MAY 05/02/97 - 05/30/97 0502S7 - 05/30/97 l JUN 05/30/97 - 07/03S 7 05/30/97 - 07/03/97 JUL 07/03S7 - 08/01/97 07/03/97 - 08/01/97 AUG 08/01/97 0905/97 08/01 S 7 - 09/05/97 SEP 09/05S7 - 10/03/97 09/05/97 - 10/03/97 OCT 10/03/97 - 10/30/97 1003/97 - 10/30/97 NOV 10/29/97 - 12/03S 7 10/29/97 - 12/03S7 DEC .12/03/97 - 12/31/97 12/03/97 - 12/31/97 )

l NOV 10/30/97 - 12/07/97 10/30/97 - 12/07/97 l C - 15 i

I L__.____..___

TABLE CJX.1

SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH BOT ATOMIC POWER STATION,1997 AIR PARTICULATE & AIR IODINE 2 3A SH2 WEEK NO is 12 1 12/28/96 - 01/03/97 12/28/96 - 01/03/97 12/28/96 - 01/03/97 12/28/96 - 01/03/97 12/30/96 - 01/06/97 2 01/0497 - 01/10S7 01/03/97 - 01/10/97 01/03/97 01/10/97 01/03/97 - 01/10/97 01/06/97 - 01/13/97 l 3 01/10/97 - 01/17/97 01/10/97 - 01/17/97 01/10/97 - 01/17/97 01/10/97 - 01/17/97 01/13/97 - 01/20/97 4 01/17/97 - 01/2497 01/17/97 - 01/2497 01/17/97 01/2497 01/17/97 - 01/24/97 01/20/97 - 01/27/97 5 01/2497 - 02/01/97 01/24/97 - 02/01/97 01/24/97 - 01/01/97 01/2497 - 02/01/97 01/27/97 - 02/03/97 6 02/01/97 - 02/07/97 02/01/97 02/07/97 02/01/97 - 02/07/97 02/01/97 - 0207/97 02/03/97 - 02/10/97 7 02/07/97 - 02/15/97 02/07/97 - 02/15/97 02/07/97 - 02/15/97 02/07/97 - 02/15/97 02/10/97 02/18/97 6 02/15/97 - 02G1/97 02/15/97 - 02/21/97 02/15/97 - 02/21/97 02/15/97 - 02/21/97 02/18/97 - 02/2497 9 02/21/97 - 02/28/97 02/21/97 02/28/97 02/21/97 - 02G8/97 02/21/97 - 02/28/97 02/24/97 03/03/97 10 0208/97 - 03/07/97 02/28/97 - 0307/97 02/28/97 - 03/07/97 02/28/97 - 03/07/97 03/03/97 - 03/10/97 11 03/07/97 - 03/15/97 03/07/97 - 03/15/97 03/07/97 - 03/15/97 03/07/97 - 03/15/97 03/10/97 - 03/17/97 12 03/15/97 - 03/21/97 03/15/97 - 03/21/97 03/15/97 03/21/97 03/15/97 - 03/21/97 03/17/97 - 03/24/97 93 03/21/97 03/28S7 03/21/97 - 03/28S7 03/21/97 - 03/28/97 03/21/97 - 03/28/97 03/24/97 - 03/31/97 10 03/28/97 04/04S7 03/28/97 - 04/0497 03/28/97 - 04/04/97 03/2W97 - 04/04/97 03/31/97 - 04/07/97 15 040497 - 04/10S7 04/0467 - 04/10/97 04/04/97 - 04/10/97 04/04/97 - 04/10/97 04/07/97 - 04/14/97 16 04/10/97 - 04/18S7 04/10/97 04/1&G7 04/10/97 - 04/18/97 04/10/97 - 04/18/97 04/14/97 - 04/21/97 17 04/18/97 - 0425/97 04/18/97 - 0425/97 04/18/97 - 04/25/97 04/18/97 - 04/25/97 04/21/97 - 04/28/97 18 0425/97 - 050297 0425/97 05/02/97 0425/97 - 05/02G7 0425/97 - 05/02/97 04/28/97 - 0505/97 19 05/02/97 - 05/09/97 0502S7 - 05/09/97 05/02/97 - 0509/97 05/02/97 - 05/09/97 05/05/97 - 05/12/97 20 05/09/97 05/16/97 05/09/97 05/16/97 05/09/97 - 05/16/97 05/09/97 - 05/16/97 05'12/97 - 05/19/97 31 05/16/97 - 05/23/97 054 6S7 - 05/23/97 05/16/97 05/23/97 05/16/97 - 05/23S7 05/19/97 - 05/27/97 22 05/23S7 - 05/30/97 05/23/97 - 05/30/97 05/23/97 - 05/30/97 05/23/97 - 0500/97 05/27/97 - 06/02/97 23 0500/97 - 06/06S7 05/30/97 - 06/06/97 0500/97 06/06/97 0500/97 - 06/06/97 06/02/97 - 06/09/97 24 06/06/97 - 06/13/97 06/06/97 - 06/13/97 06/06/97 - 06/13S7 06/06/97 06/13/97 06/09/97 - 06/1697 25 06/13/97 - 06/20S7 06/13/97 - 06/20/97 06/13/97 - 06/20/97 06/13S 7 - 06/20/97 06/16/97 - 06/23/97 26 06/20/97 - 06G7/97 06/20/97 - 06/27/97 06/20S7 - 06/27/97 06/20/97 - 06/27/97 06C3/97 - 06/30/97 27 06/27/97 - 07/03/97 06/27/97 07/03/97 06/27/97 07/03S7 06/27/97 - 07/03/97 06G0/97 - 07/07/97 28 07/03/97 - 07/10/97 07/03/97 - 07/10/97 07/03/97 - 07/10S 7 07/03/97 - 07/10/97 07/09/97 - 07/14/97 29 07/10/97 - 07/18/97 07/10/97 07/18/97 07/10/97 07/18/97 07/10/97 - 07/18/97 07/14/97 - 07/21/97 30 07/18/97 07/25/97 07/18/97 - 07/25/97 07/18/97 - 07/25/97 07/18/97 - 07/25/97 07/21/97 - 07/28/97 31 07/25/97 - 08/01/97 07/25/97 - 08/01/97 07/25/97 - 08/01/97 07/25/97 - 08/01/97 07/28/97 - 08/04/97 32 08/01/97 - 08/08/97 08/01/97 - 08/08/97 08/01/97 - 08/08/97 08/01/97 08/08/97 08/04/97 - 08/11/97 33 08/08/97 - 08/15/97 08/08/97 - 08/1597 08/08S7 - 08/15/97 08/08/97 - 08/15/97 08/11/97 - 08/18/97 34 08/15S7 - 08/22/97 08/15/97 - 08/22/97 08/15/97 - 08/22/97 08/15/97 - 08/22/97 08/18/97 - 08C5/97 35 08/22/97 - 08/29/97 08/22/97 - 08/29 S7 08/22/97 - Da29/97 08/22/97 - 0829/97 08/25/97 - 09/02/97 36 08/29S7 - 09/05/97 08/29S7 - 09/05/97 08/29/97 - 09/05/97 08/29/97 - 09/05/97 09/02/97 - 09/08/97 37 09/05/97 09/12/97 09/05/97 - 09/12/97 09/05/97 - 09/12/97 09/05/97 - 09/12/97 09/08/97 - 09/15/97 38 09/12/97 - 09/19/97 09/12/97 - 09/19/97 09/12/97 - 09/19/97 09/12/97 09/19S7 09/15/97 09/22/97 39 09/19/97 - 09/26/97 09/19/97 09/26/97 09/19/97 09/26/97 09/19S7 09/26/97 09/22/97 - 09/29S7 40 09/26/97 - 1003/97 09/26/97 - 10/03/97 09/26S7 - 10/03/97 09/26/97 10/03/97 09/29 S7 - 10/06/97 41 10/03/97 - 10/09S7 10/03/97 - 10/09/97 1003/97 - 10/09S7 10/03/97 - 10/09/97 10/06/97 - 10/13/97 842 10/0957 - 10/17/97 10/09/97 10/17/97 10/09/97 - 10/17/97 10/09/97 - 10/17/97 10/13S7 - 10C0/97 43 10/17/97 - 10/24/97 10/17/97 - 10C4/97 10/17/97 - 10/24/97 10/17/97 - 10/24/97 10/20/97 - 10/27/97 44 10!24/97 - 10/30/97 10/24/97 - 10/30/97 10/24/97 - 10/30/97 10/24/97 - 10/30/97 10/27/97 - 11/03/97 45 1000/97 - 11/07/97 10GOS7 - 11/07/97 10/30/97 - 11/07/97 10/30/97 - 11/07/97 11/03/97 11/10/97 46 11 07/97 - 11/13/97 11/07/97 - 11/1 % 7 11/07/97 11/13/97 11/07/97 - 11/13/97 11/10/97 - 11/17/97 47 11/13/97 - 11/21/97 11/13/97 11/21/97 11/13!97 11/21/97 11/13/97 - 11/21/97 11/17/97 - 11/24/97 48 11/21/97 - 11/28/97 11/21/97 - 11/28/97 11/21/97 11/28/97 11/21/97 - 11/28/97 11/24/97 - 12/02/97 49 11/28S7 - 12/07/97 11/28/97 - 12/07/97 11/28/97 - 12/07/97 11/28/97 - 1207/97 12/02/97 - 12/08/97 ED 12/07/97 12/12/97 1207/97 - 12/12/97 12/07/97 - 12/12/97 12/07/97 - 12/12/97 12/08S7 - 12/16S7 51 12/12/97 - 12/19/97 12/12/97 - 12/19/97 12/12/97 - 12/19/97 12/12/97 - 12/19/97 12/16S7 - 12/22/97 52 12/19S7 - 12/26/97 12/19/97 - 12/26/97 12/19/97 - 12/26/97 12/19S7 - 12/26/97 12/22/97 - 12/29S7 53 12/2657 - 12/31/97 12/26/97 - 12/31/97 12/26S 7 - 12/31/97 12/26/97 - 12G1/97 N/A CJR PARTICULATE (GAMMA SPECTROSCOPY)

COLLECTION PERIOD 1B 1Z 2 3A SH2 JAN-MAR 12/28/96 - 03/28/97 12/28/96 - 03/28/97 12C8/96 - 03/28/97 12/28/96 - 03/28/97 12/30/96 - 03/31/97 APR-JUN 03/28/97 - 06/27/97 03/28/97 - 06/27/97 03/28/97 - 06/27/97 03/28/97 - 06/27/97 03/31/97 - 06/30/97 JUL SEP 0 627/97 09/26/97 06/27/97 - 09/26/97 06/27/97 - 09/26/97 06/27/97 - 09/26/97 06/30/97 - 09/29/97 OCT-DE C 09/26/97 - 12/31/97 09/26/97 - 12/31!97 09/26/97 - 12/31/97 09/26/97 - 12/31/97 09/29/97 - 12/29/97 C - 16 i

TABLE C-IX.1

SUMMARY

OF COLLECTION DA7ES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM .

i ATOMIC POWER STATION.1997 Staten Code JAN-MAR APR-JUN JUL-SEP OCT-DEC 1A 01 03S 7 - 04/04/97 04/04/97 - 07/03/97 07/03S7 10/03/97 10/03/97 - 01/04/98 18 01/03/97 - 04/04/97 04/04/97 07/03/97 07/03/97 - 10/03/97 10/03/97 01/04/98 ,

1C 01/0197 - 04/04/97 0404/97 - 07/02/97 07/02/97 - 10/02S7 10/02/97 - 01/04/98 l 1E 01/03S7 - 04/04/97 04/04/97 - 07/03/97 07/03/97 10/03/97 10/03/97 01/0498 1F 01/03/97 - 04/04/97 04/0497 - 07/03/97 07/03/97 - 10/03/97 100197 - 01/04/98 SG 01/03/97 - 04/04/97 04/04 S7 - 07/03/97 07/03/97 10/03/97 10/03/97 - 01/04/98 j 1H 01/03/97 04/04/97 04/04/97 07/03/97 07/03/97 - 10/04/97 10/04/97 - 01/04G8 l 11 01/03/97 04/04/97 04/04/97 - 07/02/97 07/02/97 10/02/97 10/02/97 - 01/04/98 l 1J 01/03/97 0404/97 04/04/97 - 07/03/97 07/03/97 10/03/97 10/03S7 - 01/04/98 1L 01/03/97 04/04/97 0404/97 - 07/03/97 07/03/97 - 10/0497 10/04/97 - 01/0498 1 2 01/03/97 04/04/97 04/0497 - 07/03/97 07/03/97 10/0357 1003/97 - 01/04/98 3A 01/03/97 - N/04/97 04/04/97 07/03/97 07/03/97 10/03/97 1003/97 - 01/0498 4K 01/03/97 04/0497 0404/97 - 07/03/97 07/03/97 10/03S7 1003/97 - 01/0498 5 01/02/97 - 04/03S7 04/03S7 - 07/02/97 07/02/97 - 10/02/97 10/02/97 - 01/03/98 1NN 01/03/97 - 0404S7 04/04/97 - 07/03S7 07/03/97 - 10/0497 10/04/97 - 01/04/98 6B 01/03/97 - 04/03/97 0403/97 - 07/03/97 07/03/97 - 10/0197 10/03/97 - 01/03/98 14 01/02/97 - 04/03/97 -0403/97 07/02/97 07/02/97 - 10/02/97 10/02/97 - 01/03/98 10 01/02/97 - 0403/97 0403/97 - 07/03S7 07/03/97 - 10/02/97 10/02/97 - 01/03G8 l 16 01/02/97 - 04/03/97 0403/97 - 07/02/97 07/02/97 10/02/97 1002/97 01/03/98 l 17 01/02/97 - 04/03S7 0403S7 - 07/02/97 07/0297 10/0297 1002/97 - 01/03/98 l 18 01/0297 - 0403/97 0403/97 - 07/02/97 07/0297 - 10/02/97 1002/97 - 01/03/98 19 01/02/97 - 0403/97 0403/97 - 07/02/97 07/02/97 - 1002/97 10/02/97 - 01/03/98 22 0102/97 - 0403/97 040197 - 07/02/97 07/02/97 - 100297 10/02/97 - 01/03/98 23 01/03/97 04/0497 040497 - 07/03/97 07/03/97 10/03/97 10/03/97 - 01/0498 3G G1/02/97 04/03/97 0403/97 - 07/02/97 07/02/97 1002/97 1002/97 01/03/98 26 01/02S7 - 04/0197 0403/97 - 07/02/97 07/02/97 10/02/97 10/02/97 - 01/03/98 27 01/03/97 040497 040497 - 07/02/97 07/02/97 10/02/97 100 2/97 - 01/03/98 i 31A 01/0297 - 04/03/97 040.ws? - 07/02/97 07/02/97 - 10/02/97 10/02/97 - 01/03S8 )

33 01/02/97 - 0403/97 0403/97 - 07/02/97 07/0297 10/02/97 10/02/97 - 01/03/98 l 40 01/03S7 040497 04/04/97 - 07/03/97 07/0397 - 10/03/97 10/0197 - 01/04/98 42 01/02/97 - 04/03/97 04 03/97 - 07/02/97 07/02/97 10/02S7 1002/97 - 01/03/98 43 01/02/97 - 04/03G7 04/03/97 - 07/02/97 07/02/97 - 10/02/97 10/02/97 01/03S8 ,

44 01/02/97 - 0403/97 0403S7 07/02/97 07/02/97 - 10/02/97 10/02/97 - 01/03G8

]

43 01/02/97 - 04/03/97 0403/97 - 07/02/97 07/02/97 - 10/02/97 1002/97 01/0198 46 01/0197 - 04/0497 04/04/97 - 07/02/97 07/02/97 - 10/02S 7 10/02/97 - 01/03/98 47 01/03/97 - 04/04/97 040497 - 07/02/97 07/0297 e 10/02/97 10/02/97 - 01/03/98 48 01/03S 7 - 04/04/97 04/0497 - 07/02/97 07/02/97 - 10/02/97 10/02/97 - 01/0aS8 49 01/02/97 - 0403S7 0403S7 - 07/0297 07/02/97 - 10/02 S7 10/02/97 - 01/03/98 50 01/0297 - 0403/97 0403S7 - 07/02/97 07/02/97 - 10/02/97 10/02/97 01/03/98 51 01/02/97 - 0403/97 0403/97 07/02S7 07/02/97 1002S7 10/02/97 - 01/03/98 l

i C - 17

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APPENDIX D: DATA TABLES AND FIGURES - COMPARISON LABORATORY t-TABLES Table D-l.1 Concentrations Of Gross Beta insoluble in Drinking Water Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1997.

Table D-l.2 Concentration Of Gross Beta Soluble in Drinking Water Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1997.

Table D-l.3 Concentrations Of Gamma Emitters in Drinking Water Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1997.

Table D-II.1 Concentrations Of Gross Beta in Air Part:culate Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1997.

Table D-II.2 Concentrations Of Gamma Emitters In Air Particulate Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1997.

Table D-Ill.1 Concentrations Of I-131 By Chemical Separation And Gamma Emitters in Milk Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station, 1997.

Table D-IV.1 Summary Of Collection Dates For Samples Collected in The Vicinity Of Peach Bottom Atomic Power Station,1997.

FIGURES Figure D-1 Comparison Of Monthly Insoluble Gross Beta Concentrations in Drinking Water Samples Split Between GPU And TBE.1997.

Figure D-2 Comparison Of Monthly Soluble Gross Beta Concentrations in Drinking Water Samples Sp!!t Between GPU And TBE,1997.

l Figure D-3 Comparison Of Weekly Gross Beta Concentrations in Air Particulate Samples Collected From Collocated PBAPS Locations 1 A And 1Z,1997.

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The following section contain; ata and figures illustrating the analyses performed by the quality control laboratory. Duplicate samples were obtained from several locations and media and split between the primary laboratory, GPU nuclear and the quality control laboratory, Teledyne Brown Engineering (TBE).

Comparison of the results for most media were within expected ranges, though occasional differences were seen:

TBE's results of gross beta insoluble and soluble in drinking water samples were slightly higher than the results from GPU (Figures D-1 and D-2, Appendix D). The differences were probably due to variations in the respective laboratory's analytical procedures. TBE counts the semples for 50 minutes, GPU counts for 100 minutes.

The gross beta results for air particulate samples collected at the collocated stations 12 and 1 A compared very well (Figure D-3, Appendix D). No significant differences were noted. Both laboratories use Cs-137 a., a calibration source.

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l D-1

TABLE D-l.1 CONCENTRATIONS OF GROSS BETA INSOLUBLE IN DRINKING WATER SAMPLES COLLEC THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L PERIOD JAN 0.5 10.8 FEB 0.7 to.9 MAR 0.7 10.9 APR 1.7 21.0 MAY 0.4 11.0 JUN 1.1 20.9 JUL 0.3 21.0 AUG 1.8 11.0 SEP 0.9 20.9 OCT -0.8 10.9 NOV 0.6 20.8 DEC 0.6 21.1 MEAN 0.7 21.4 TABLE D-l.2 CONCENTRATIONS OF GROSS BETA SOLUBLE IN DRINKING WATER SAMPLES COLLECTED IN THE VICINITY OF PEACH BOTTOM ATOMIC POWER STATION,1997 RESULTS IN UNITS OF PCl/ LITER +/- 2 SIGMA COLLECTION 4L PERIOD JAN 2.1 21.2 FEB 2.7 ti.3 MAR 2.5 11.2 APR 4.9 21.4 MAY 1.4 11.2 JUN 1.8 21.2 JUL 3.1 21.4 AUG 5.7 11.9 SEP 4.2 21.8 OCT 3.1 11.5 NOV 2 11.3 DEC 2.9 21.5 MEAN 3 12.6 l

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SUMMARY

OF COLLECTION DATES FOR SAMPLES COLLECTED IN THE VICINITY OF PEACH !

BOTTOM ATOMIC POWER STATION,1997 )

DRINKING WATER (GROSS BETA & GAMMA SPECTROSCOPY)

COLLECTION 4L PERIOD JAN 01/03/97 02/01/97 FEB 02/01/97 02/28/97 MAR 04/04/97 04/10/97 APR 04/04/97 - 05/02/97 i I

MAY 05/02S7 05/30/97 JUN 05/30/97 - 07/03/97 JUL O'7/03/97 08/01/97 AUG 08/01/97 - 09/05/97 SEP 09/05/97 10/03/97 OCT 10/03/97 - 10/50/97 NOV 10/30/97 - 12/07/97 DEC 12/07/97 - 01/0498 AIR PARTICULATE (Gross Beta)

WEEK NO 1A WEEK NO 1A 1 12/28/96 - 01/03/97 27- 06/27/97 07/03/97 2 01/03/97 01/10/97 28 07/03/97 - 07/10/97 3 01/10/97 01/17/97 29 07/10/97 07/18/97 4 01/17/97 01/24/97 30 07/18/97 - 07/25/97 5 01/2497 02/01/97 31 07/25/97 08/01/97 6 02/01/97 02/07/97 32 08/01/97 08/08/97 7 02/07/97 02/15/97 33 08/08S7 08/15/97 8 02/15S7 - 02/21/97 34 08/15/97 08/22/97 9 02/21/97 02/28/97 35 08/22/97 08/29/97 10 02/28/97 03/07/97 36 08/29/97 - 09/05/97 11 03/07/97 - 03/15/97 37 09/05/97 - 09/1297 12 03/15/97 03/21/97 38 09/12/97 - 09/19S7 13 03/21/97 03/28/97 39 09/19 S7 - 09/26/97 14 03/28/97 04/04/97 40 09/26/97 - 10/03 S 7 15 04/0497 04/10/97 41 10/03/97 - 10/09/97 16 04/10/97 04/18/97 42 10/09/97 - 10/17/97 17 04/18/97 0425/97 43 10/17/97 10/24/97 18 04'25/97 05/02/97 44 10/24/97 - 10/30/97 19 05/02/97 05/09/97 45 10/30S 7 - 11/07/97

' 05/09/97 05/1&S7 46 11/07/97 - 11/13/97 20 21 05/16/97 05/23/97 47 11/13/97 - 11/21/97 22 05/23/97 05/30S7 48 11/21/97 - 11/28/97 23 05/30/97 06/06/97 49 11/28/97 - 12/07/97 24 06/06/97 - 06/13/97 50 12/07/97 - 12/12S7 25 06/13S7 - 06/20/97 51 12/12/97 - 12/19,97 l 26 06/20/97 - 06/27/97 52 12/19/97 - 12/26/97 AIR PARTICULATE (GAMMA SPECTROSCOPY)

COLLECTION PERIOD 1B JAN-MAR ~ 12/28/96 - 03G8/97 APR-JUN 03/28/97 06/27/97 JUL-SEP 06/27/97 09/2697 ;

OCT-DEC . 09/26/97 1226/97 ]

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'9 APPENDIX E SYNOPSIS OF ANALYTICAL PROCEDURES a

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APPENDIX E: SYNOPSIS OF ANALYTICAL PROCEDURES The following section contains a description of the analytical laboratory procedures along with an explanation of the analytical calculation methods used by GPU Nuclear and Teledyne Brown Engineering to obtain the sample activities.

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DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)

GPUN Environmental Radioactivity Laboratory This describes the process used to measure the radioactivity of water samples without

. identifying the radioactive species present. No chemical separation techniques are

' involved.-

For surface and drinking water samples,400 ml of the sample is filtered under vacuum through a 0.45 micron filter. This filter represents the insoluble portion of the sample.

The filter is dried and mounted on a planchet. The filtrate which represents the soluble ,

portion of the sample is evaporated on a hot plate, and the residue is transferred and dried on another planchet. ,

The planchets are counted for 100 minutes in a low-background gas flow proportional counter. Calculation of activity includes a seff-absorption correction for counter efficiency based on the weight of residue on each planchet.

Calculation of Samole Activity and 2 Sioma Uncertainty:

R = 2.22xEoxTFxVxT

'2xdC + B 2s =

2.22xEoxTFxVxT 4.66x8 2.22xEoxTFxVxT

' Where:

R = Activity of sample in picocuries per unit volume or weight. Volume or weight units are those used for V.

2s- = 2 Sigma Counting Uncertainty LLD = Lower Limit of Detection C = Sample Counts B =- Blank Counts Eo = . Efficiency of the counter TF = Transmission Factor T = Acquisition time in minutes

.V = Volume or weight of aliquot analyzed.

E-2

DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES (TOTAL SUSPENDED AND DISSOLVED FRACTIONS)

Teledyne Brown Enaineerino This describes the process used to measure the radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.

For surface and drinking water samples, one liter of the sample is filtered under vacuum through a 0.45 micron Millipore filter. This filter represents the insoluble portion of the sample. The filter is dried and mounted on a planchet. The filter which represents the soluble portion of the sample is evaporated on a hot plate, and the residue is transferred and dried on another planchet.

The planchets are counted for 50 minutes in a low-background gas flow proportional counter. Calculation of activity includes a self-absorption correction for counter efficiency based on the weight of residue on each planchet.

Calculation of Sample Activity and 2 Siama Error:

Result *0 \

(pri:1) (2.22)(s)(E) ^ (2.22)(v)(E)

Net Activity Counting Error where:

N = total counts from sample (counts)

t. = counting time for sample (min)

G = background rate of counter (cpm) to = counting time for background (min) 2.22 = dpm/pCi v = volume in liters E = efficiency of the counter 2 = multiple of counting error The MDA is defined as that value equal to the two sigma counting error of the result.

E-3

DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION COUNTING GPUN Environmental Radioactivity Laboratory Seven (7) milliliters of sample is filtered through a 0.45 micron filter into a vial and mixed with 15 ml of liquid scintillation material and counted for a minimum of 480 minutes to determine its activity. The tritium activity is determined by measuring the count rate in the beta activity energy spectrum in Region A. 20.0 to 2000 represents Region C. If the sample Region C cpm is within i 25% of the average background Region C cpm and the sample Quench Indicating Parameter (QlP) is within 20 of the H-3 source OlP the sample has no contamination and the tritium activity may be calculated directly. If not the sample must be purified before recounting.

Calculation of Sample Activity and 2 Siama Uncertainty:

R=

C-0 2.22x EoxVxDF C +p 2x

,,_ T. Ts 2.22x EoxVxDF LLD- 3.29x\ TsT.f$~ S 2.22x EoxVxDF Where:

T. = Total count time of sample in minutes T,i = Total count time of background in minutes R = Tritium activity in picocurie per unit volume (Volume units are those used in V) 2s = 2 sigma Uncertainty in the same units as above LLD = Lower limit of detection in same units as above C = Average count rate of sample p = Average count rate of background Eo = Tritium detection efficiency of counter, calculat?d as shown below V = Volume of aliquot E-4

DF = Decay factor, calculated as shown below

-in hDT DF=enn DT = time difference in years from collection stop date to counting date of sample The efficiency is calculated as follows:

S-B Eo= AsrVsxDFs Where:

S = Average count rate for the " efficiency determination" standard B = Average count rate of background As = Activity of standard in dpm per unit volume Vs = Volume of standard used DFs = Decay factor of standard, calculated as follows:

. in hDTs DFs = e un DTs = time difference (in years) between calibration date and counting date E-5

DETERMINATION OF GROSS BETA ACTIVITY IN AIR PARTICULATE SAMPLES GPUN Environmental Radioactivity Laboratory After allowing at least a three-day (extending from the sample stop date to the sample count time) period for the short-lived radionuclides to decay out, each air particulate filter paper is placed in a 2-inch diameter stainless steel planchet and counted using a gas flow proportional counter.

Calculation of Sample Activity and 2 Siama Uncertainty:

C-B 2.22xEoxTFxVxT 2xJC+ B

~s=-

2.22x EoxTFxVxT \

l 4.66x5 LLD = 2.22xEoxTFxVxT Where R = Activity of sample in picoCuries per unit volume or wr.ight. Volume or weight units are those used for V.

2s = 2 Sigma Counting Uncertainty LLD = Lower Limit of Detection C = Sample Counts B = Blank Counts Eo = Efficiency of the counter TF = Transmission Factor of filter (i.e.1.00 for gross beta,0.80 for gross alpha)

T = Acquisition time in minutes V = Volume analyzed.

E-6 Y

DETERMINATION OF GROSS BETA ACTIVITY IN AIR PARTICULATE SAMPLES Teledvne Brown Enaineerina This describes the process used to measure the overall beta activity of air particulate filters without identifying the radioactive species present. No chemical separation techniques are involved. Each air particulate filter is placed directly on a 2-inch stainless steel planchet. The planchets are then counted for beta activity ir a low-background gas flow proportional counter. Calculation of activity includes an cmpirical self-absorption correction curve which allows for the change in effective counting efficiency caused by the residue mass. Self-absorption is not considered in the case cf air particulate filters because of the impracticality of accurately weighing the deposit and be.s Juse the penetration depth of the deposit into the filter is unknown.

Calculation of Sample Activity and 2 Siama Error:

N N p i*i Resuh

= i*0 +

(pCi m') 2.22(s)(E)(.02832) ~ 2.22(v)(E)(.02832) '

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l Net Activity Counting Error j where:

N

total counts from sample (countc)

t. = counting time for sample (min) l G = background rate of counter (cpm) )

te = counting time for background (min) 1 2.22 = dpm/pCi v = volume of sample analyzed in cubic feet calculated from the elapsed time meter E = efficiency of the counter 2 = multiple of counting error

! .02832 = convers en to cubic meters The MDA is defined as that value equal to the two sigma counting error of the result.

E-7

, DETERMINATION OF l-131 IN MILK SAMPLES GPUN Environmental Radioactivity Laboratory Stable iodine carrier is equilibrated in a 3.5-liter volume of raw milk before pumping through 25cc of anion exchange resin to extract iodine. The system is washed with de-ionized water until clear and the washed resin is transferred to a gamma counting container and analyzed by gamma spectroscopy.

Calculation of Sample Activity and 2 Siama Uncertainty:

' The same calculations are used as in DETERMINATION OF GAMMA EMITTING RADIOISOTOPES below.

E-8

DETERMINATION OF l-131 IN MILK SAMPLES Teledyne Brcwn Enaineerina Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodide from the sample. The iodine is then stripped from the resin with sodium hypochlorite, reduced with hydroxylamines hydrochloride, and extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or water with a specific ion electrode.

Calculation of the Sample Activity and 2 Sigma Error:

E .p E Result t,

~ y tl +ts?

(Pri l) (2.22)(v)(E)(y)(exp") (2.22)(s)(E)(y)(exp*)

Net Activity Counting Error where:

N = total counts from sample (counts)

t. = counting time for sample (min)

B = background rate of counter (cpm) te, = counting time for background (min) 2.22 = dpm/pCi v = volume of sample analyzed (liters) y = chemical yield of the amount of sample counted 2 = is the radioactive decay constant for 1-131 (0.t393/8.05)

At = is the elapsed time between sample collection (or end of the sample collection) to the midcount time 2 = multiple of the counting error E = efficiency of the counter for 1-131, corrected for self absorption effects by the formula:

L. = E, (exp'**'")

.a m,u,,

where:

E. = efficiency of the counter determined from an 1-131 standard mount M = mass of Pdl2 on the sample mount (mg)

M. = mass of Pdl2 on the standard mount (mg)

The MDA is defined as that value equal to the two sigma counting error of the result.

E-9

DETERMINATION OF GAMMA EMITTING RADIOISOTOPES GPUN Environmental Radioactivity Laboratory The procedure for detection of gamma emitting radioisotopes geneiates high resolution gamma spectra which are used for quantitative determination and identification.

Standard geometries have been established to maximize efficiency for sample types:

air particulate filters, water, milk, soil / sediment and food products.

A description of the analytical methods, beginning with air particulate used for each sample type is presented, followed by the general formula used for calculation of the sample activities.

1 Air particulate: At the end of each calendar quarter,13 (or 14) weekly air filters from !

I the given location are stacked in a two inch diameter Petri dish in chronological order, with the oldest filter at the bottom, nearest the detector, and the newest one on top.

The Petri dish is closed and the sample counted.

Water and Milk: A well-mixed 3.5-liter sample is poured into a Marinelli beaker. The samples are brought to ambient temperature and counted.

Soil and Sediment; The sample is dried, sieved and put into a counting container and counted.

Food products: The sample is chopped up and put into a counting container and counted.

Calculation of Sample Activity and 2 Siama Uncertainty; A=

2.22xqxixhx Et x e r (l - e-"')

where:

A = the computed specific activity P = peak area 2.22 = dpm/ picocurie q = sample quantity E = detection efficiency b = gamma-rey abundance Et = elapsed live time 2 = decay constant Ts = acquisition start time En = elapsed real time l

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' AP' # ' Ab' # ' AcV ' sys' #

M=A I (ADecay)2

\\ Pi r b i < e ) <100) where: M = uncertainty in the activity A En ADecay = A Tv2 x .g, - A(Ts + Ea)-1, AP = uncertainty in the peak area P Ab = uncertainty in the S-ray abundance AE = uncertainty in the efficiency sys = systematic Uncertainty estimate ( in %)

AT% = uncertainty in the half-life i

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DETERMINATION OF GAMMA EMITTING RADIOISOTOPES Teledyne Brown Enaineerina Gamma emitting radioisotopes are determined with the use of a lithium drifted germanium (GeLi) and high purity germanium detectors with high resolution spectrometry in specific media; such as, air particulate filters, charcoal filters, milk and water. Each sample to be assayed is prepared and counted in standard geometries such as one liter wrap-around Marinelli containers,300 ml or 150 ml bottles, or 2-inch filter paper source geometries.

Samples are counted on large (>55 cc volume) GeLi detectors connected to Nuclear Data 6620 data acquisition and computation systems. All resultant spectra are stored on magnetic tape.

Tha analysis of each sample consists of calculating the specific activities of all detected radionuclides or the detection limits from a standard list of nuclides. The GeLi systems are calibrated for each standard geometry using certified radionuclides standards traceable to the National Bureau of Standards.

Gamma Spectroscopy Statistically Significant Activity and 2 Siama Error Calculation for the ND6620 and ND6700 Systems:

Attivitv "

AIWA

DECAY pCi LIVETIME(se.:.)* ABN

EFF

0.037 * (writ mass)

( unit mass Statistically Significant Activity 42

BKGND ~ AREA t 200 *

Activity AREA 2 Sigma Counting Error Where:

AREA = Net Peak Area (from Nuclide Line Activity Report)

BKGND = Compton Background (from Nuclide Line Activity Report DECAY = Decay Correction Factor (from Minimum Detectable Activity Report) (Nuclide Half Life - Collection time to Mid Count time)

LIVE TIME = Elapsed Live Time ( from Header Information)

E - 12

ABN = Nuclide Abundance (from Nuclide Line Activity Report)

EFF = Detector Efficiency (from Nuclide Line Activity Report) 0.037 = Conversion Factor (dps to picocurie) unit mass = Sample weight or volume (from Header Information)

Gamma Spectroscopy Statistically Non Significant Activity and ? Siama Error Calculation for the ND6620 and ND6700 Systems:

~ Activity AREA

DECAY PiC LD'ETIME(sec.)* ABN

EFF

0.037 * (unit mass)

I unit mass Statistically Non Significant Activity 42

BKGND - NET 200 *

Net Activity NET 2 Sigma Counting Error where:

NET = Net Peak Area (from Minimum Detectable Activity Report)

BKGND = Compton Background (from Nuclide Line Activity Report)

DECAY = Decay Correction Factor (from Minimum Detectable Activity Report) (Nuclide Half Life - Collection time to Mid Count time)

LIVE TIME = Elapsed Live Time ( from Header Information)

= Efficiency

Abundance (from Minimum Detectable Activity (EFF*B.1)

Report) 0.037 = Conversion Factor (dps to picocurie) unit mass = Sample weight ~ volume (from Header Information)

F - 13

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Gamma Spectroscopy Minimum Detectable Activity Calculation for the ND6620 and .

ND6700 Systems: l MDA 2.83 JBKGN

DECAY pCi " Lil'ETIM T(sec.) * (EFF

B.J.)

0.037 * (unit mass)

(unit mass, where:

BKGN = Total Peak Background Area (from Minimum Detectable Activity Report)

DECAY = Decay Correction Factor (from Minimum Detectable Activity Report) (Nuclido Half Life - Collection time to Mid Count time)

LIVE TIME = Elapsed Live Time ( from Header Information)

(EFF*B.1) = Efficiency

Abundance (from Minimum Detectable Activity Report) 0.037 = Conversion Factor (dps to picocurie) unit mass = Sample weight or volume (from Header Information)

E - 14

ENVIRONMENTAL DOSIMETRY GPUN Environmental Radioactivity Laboratory GPU Nuclear thermoluminescent dosimeters (TLDS) are Panasonic Type 801 AS badges, two of which are deployed at each station. Each badge contains two calcium sulfate and two lithium borate elements. Since each element responds to radiation independently, this provides eight independent detectors at each station. The calcium sulfate elements are shielded with a thin layer of lead, which makes the response to different energies of gamma radiation more linear. The lead also shields the calcium sulfate elements from beta radiation, so that they respond to gamma radiation only.

The two lithium borate elements are shielded differently to permit the detection of beta radiation. Only the calcium sulfate elements normally are used for environmental monitoring; however, the lithium borate elements can be used to evaluate beta exposures or as a backup to the calcium sulfate elements should more data be required.

TLDs are annealed and read using a Panasonic UD701 A TLD Reader equipped with glow curve capture capability. A reader alignment is performed monthly using TLDs irradiated to a known exposure. Run Correction Factors (RCF) are inserted in each read batch to correct for small drifts in reader calibration. An Element Correction Factor (ECF) is generated for each element before a new TLD badge is placed into service to standardize each element to a known exposure. The ECF for each element is updated every two years. Each calcium sulfate element is annealad to a total residual exposure of less than 0.5 mR prior to being issued each time that a badge is used.

Control (transit) badges are issued with every batch of field TLDs and accompany the badges into the field to quantify transit exposure. After the field badges are deployed, the control badgcc are kept in a lead shield with minimum 2" thick lead during the period of field exposure. Additional control badges are kept in a lead shield for the entire quarter, and receive essentially no transit exposure. All control and field badges are read together ret the end of each quarter, and the average field control badge exposure is subtracted from the average shield control badge exposure to generate the transit exposure. The transit exposure (generally less than 1 mR total) is subtracted from the gross exposures on the field badges to yield the net exposures.

Net exposures are then converted to mR per standard month. This method of calculating transit exposure conforms to guidance contained in ANSI N545.

Each station comprises two TLD badges, each of which has two calcium sulfate elements. Outliers are identified using predefined algorithms. If all four elements are available, a given exposure value is judged an outlier if the standard deviation exceeds 5% of the mean exposure based on all four elements, and the exposure for one element is outside three standard deviations of the mean exposure based on the E - 15

Other three elements. If only two elements are available, the relative standard deviation based on the two exposure values must be 12% or less, or else both exposure values are considered outliers and no valid data are reported for that station for that Quarter.

E - 16 I

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APPENDIX F QUALITY CONTROL EPA INTER-LABORATORY COMPARISON PROGRAM i

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l l APPENDIX F: QUALITY CONTROL PROGRAM I i

GPU Nuclear (GPU) and Teledyne Brown Engineering (TBE) participate in the EPA !

Radiological Comparison (cross check) Program. This participation was limited to analyses of water samples due to budget reductions within EPA. To supplement this program both laboratories contracted with an independent vendor Analytics to provide cdditional media for analysis. In addition GPU Nuclear participates in the DOE I l

Radiological Comparison Program. The results of these Inter-laboratory programs )

r;present the various media as found in the Peach Bottom Atemic Power Station's l REMP. As a result of this participation, an objective measurement of analytical precision and accuracy as well as, a bias estimation of the results are obtained.

Examination of the data shows that the vast majority were within the EPA's, DOE's or Analytics's control limits. Each case of exceeding the control limits was investigated. i There was no evidence to suggest systematic errors.

l The results of GPU's and TBE's participation in the EPA, DOE and Analytics cross l- check program can be found in Tables F-1, F-2, F-3 and F-4.

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TABLE F-1 1997 USEPA Cross Check Program Results Teledyne EPA Control GPUN-ERL Br n Eng.

Collection Results Date Media Nuclide Limits (A) (B) (B) 19.67 t 2.52 10.00 i 1.00 Water Sr-89 12.0 i 8.7 01/17/97 2 2.52 25.00 1 1.00 Sr-90 25.0 i 8.7 22.33 5.57 1 1.56 8.10 0.89 Water Alpha 5.2

8.7 01/31/97 3.21 15.00 i 1.00 Beta 14.7

8.7 18.33 i 92.33

5.51 106.00 i 4.36 Water 1-131 86.0 i 15.6 02/07/97 (E)

(C) 86.0 i 15.6 91.67 1 2.08 (D)

H-3 7900.0 i 1370.6 7933.33 i 57.74 7366.67 i 378.59 03/07/97 W ater 20.8 30.00 1 1.00 54.67 i 1.53 04/1:i/97 Water Alpha 48.0 1 26.5 83.00 i 1.73 103.33 i 5.77 Beta 102.1 i 8.7 24.00 i 1.00 22.67 t 0.58 Co-60 21.0 F.7 26.00 i 1.00 23.00 t 1.00 Sr-89 24.0 i 8.7 10.00 i 0.00 12.67 i 1.15 Sr-90 13.0 t 31.0 i 8.7 31.00 i 1.00 28.67 i 0.58 4 Cs-134 Cs-137 22.0 i 8.7 24.67

0.58 24.67 i 1 ;3 18.0 i 8.7 18.67 i 0.58 19.00 t 0.00 06/06/97 Water Co-60 100.0 i 17.3 106.67 i 5.77 99.33 t 1.15 Zn-65 25.0 i 8.7 25.00 1 0.00 22.33 1 2.52 Ba-133 Cs-134 22.0

8.7 20.33 i 1.53 18.67

1.15 Cs-137 49.0 i 8.7 52.33

2.08 48.67 i 0.58 Sr-89 44.0 1 8.7 39.67 1 0.58 38.33 i 1.53 07/11/97 Water Sr-90 16.0 t 8.7 16.67 i 1.53 25.00 1 0.00 (F)

Alpha 3.1 8.7 4.47 i 1.27 1 0.25 07/18/97 Water i Beta 15.1 i 8.7 15.00 1 2.00 14.. t 1.00 08/08/97 Water H-3 11010 i 1910.2 11333.33 i 577.35 12000.00

0.00 Water 1-131 10.0 i 10.4 9.00 i 1.00 11.00 i 0.00 09/19/97 (C) 10.0 1 10.4 10.87 1 2.20 (D)

F-2

TABLE F-1 1997 USEPA Cross Check Program Results Teledyne Collection EPA Control GPUN-ERL Date Media Nuclide Lirnits Results Bro n g.

p (A) (B)

(B)

)

10/21/97 Water Alpha 49.9 1 21.7 49.33 i 0.58 45.67 1 1.15 l Beta 143.4 1 37.3 140.00 1 0.00 136.67 i 5.77 Co-60 10.0 8.7 12.00 i 2.65 10.67 i 0.58 Sr-89 36.0 1 8.7 42.33 1 2.52 36.00 i 1.00 Sr-90 22.0 i 8.7 24.33 1 2.31 21.67 i 2.08 Cs-134 41.0 i 8.7 40.67 i 0.58 41.33 1 0.58 Cs-137 34.0 i 8.7 36.33 i 0.58 36.00 i 1.00 1 1

10/31/97 Water Alpha 14.7 i 8.7 14.33 i 3.21 19.67 i 1.53 Beta 48.9 i 8.7 47.67 1 7.23 50.67 i 3.51 11/7/97 Water Co-60 27.0 i 8.7 30.00 1 1.00 25.00 1 1.00 Zn-65 75.0 i 13.9 80.33 i 6.66 71.00 i 3.61 Ba-133 99.0

17.3 99.67 1 0.58 78.67 1 0.58 !

I (G)

Cs-134 10.0 i 8.7 10.67 i 1.53 10.67 i 0.58 Cs-137 74.0

8.7 78.33 i 3.21 7S.00 t 1.00 ,

(A) EPA Control Limits - Known Value 2 3 sigma (n = 3) Units are pCi/L.

(B) Results Average of three determinations i one standard deviation. Units are pCl/L.

(C) Low Level 1-131 Method.

(D) Gamma Spectroscopy of Water Mwwd.

(E) Erroneously high reading of the stable iodine content by ton specific electrode occurred. causing an erroneously low chemical yield. If the electrode reading is ignored, the average 1-131 result becomes 90 pCi/L, in good agreement with the given value.

An erroneous electrode reading can be caused by certain chemcal species in the sample. such as sulfide. TBE will investigate suspiciously high eiectrode readings by performing a gravimetric yield on the sample without the addition of lodide camer or the I-131 content of active samples can also be verified by performing a gamma spectral analysis.

(F) Error apparently caused by insufreient trainint) A summer employee performed the strontium separation chemistry c'n 7/22/97, Initial results for the three samples did not agree well, so all were re-milked by a senior analyst. This was insuffetent to coirect the problem. In-house QC samples showed satisfactory results at this time. There will be additional qualifcetion of analysts according to performance on in-house blanks and spikes.

(G) An investigation is being conducted. results will be available shortly.

Critena are listed in EPA 600/4-81-004 F-3

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TABLE F-4 1997 ANALYTICS Environmental Cross Check Program Results Teledyne Brown Engineering Collection ANALYTICS Results Ratio Date Media Nuclide Value (a) (b) 3/20/97 Milk l-131 20 i 1 18 i 1 0.90 Ce-141 232 i 12 L.T.1. See Cr-51 3871 19 381 i 38 Footnote Cs-134 1431 7 132 i 13 0.98 Cs-137 114i 6 128 1 13 0.92 Co-58 79 i 4 89 i 9 1.12 Mn-54 176i 9 195 i 20 1.13 Fe-59 1441 7 161 i 16 1.11 i Zn-65 165 t 8 171 i 17 1.12 l Co-60 176 t 9 179

18 1.04 l 1.02 l 3/20/97 Milk Sr-89 25 i 1 13 i 3 0.52 (c) ,

Sr-90 19 i 1 16 i 1 0.84 l 143

6/19/97 Filter Ce-141 132 i 7 8 1.08 l Cr-51 1981 10 229 1 17 1.16 C&134 81 i 4 74

4 0.91 Cs-137 115i 6 143 i 8 1.24

, Co-58 77 i 4 89 i 5 1.16 Mn-54 84 i 4 102 6 1.21 Fe-59 75 i 4 98 i 6 1.31 Zn-65 139i 7 188 i 11 1.35

! Co-60 1041 5 113 1 7 1.09 6/19/97 Cartridge 1-131 88 i 4 106 i 6 1.20 6/19/97 Filter Sr-90 96 i 5 88 1 5 0.92 6/19/97 Filter Alpha 93

5 103 i 6 1.11 Beta 193i 10 210 1 6 1.09 9/18/97 Milk l-131 87 1 4 97 1 10 1.11 Ce-141 77 i 4 83 i 8 1.08 Cr-51 304i 15 323 i 40 1.06 Cs-134 1021 5 98

10 0.96 Cs-137 107 i 5 117 1 12 1.09 Co-58 60 1 3 64 1 6 1.07 Mn-54 88 2 4 99 i 10 1.13 Fe-59 119 t 6 132 1 13 1.11 Zn-65 196i 10 218 i 22 1.11 Co-60 197i 10 209 i 21 1.06 9/18/97 Milk Sr-89 15 i 1 14 1 1 0.93 Sr-90 14 i 1 10 i 1 1.29 F-9

Footnotes:

(a)

Teledyne Results - counting error is two standard deviations. Units are pCi/ liter for water and milk. F gamma results, if two standard deviations are less than 10% , then a 10% error is reported. Units are total pCi for air particulate filters and l 131 cartndges.

(b)

Ratio of Teledyne Brown Engineering to Analytics results.

(c)

Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted on 9/5/97 and was documented in the analyst's training file. Subsequent tests on two milk samples spiked with Sr-89 produced good results.

Note: Ce-141 was identified by gamma spectrometry system for the 3/20/97 milk sample, but was not reported to Analytics.

F - 10

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6 1

1 l

. APPENDIX G I

- PBAPS SURVEY l

L 4 f

I

APPENDIX G: PBAPS SURVEYS 4

A Land Use Census around the Peach Bottom Atomic Power Station (PBAPS) was conducted by Normandeau Associates, RMC Environmental Services Division for PECO Nuclear to comply with Section 3.8.E.2 of PBAPS's Offsite Dose Calculation Manual Specifications (ODCMS) and Bases. The survey was ,

conducted during the May to October 1997 growing season. The distance and !

direction of all locations were positioned from the barn to the PBAPS vents using !

I Global Positioning System (GPS) technology. The results of this survey are summarized in Table G-1.

i No char.ges were required to the PBAPS REMP as a result of this survey.

t l

G-1 l-b_ __ _

l .

TABLE G-1 LOCATION OF THE NEAREST MILK PRODUCING ANIMAL WITHIN A FIVE MILE RADIUS OF PBAPS,1997 Distance (ft.)

Sector from Vents N 14,650 NNE 11,078 NE 11,211 ENE 10,978 E 15,163 ESE 20,149 SE 19,085 SSE -

S SSW 7,855 SW 12,241 WSW 4,694 W 5,119 WNW 9,040 -

NW 17,570 NNW -

- INDICATES NO MILK ANIMALS LOCATED G-2

_ _

ML20248E180

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