PLA-5748, Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report

ML041380375
Person / Time
Site:	Susquehanna
Issue date:	05/07/2004
From:	Shriver B Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5748
Download: ML041380375 (181)

Text

x TI Bryce L. Shriver PPL Susquehanna, LLC Senior Vice President and 769 Salem Boulevard Chief Nuclear Officer Berwick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 blshriver@pplweb.com PP'- 3m--

MAY 07 2004 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OPI-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Docket Nos. 50-387 PLA-5748 and 50-388 The Susquehanna SES Annual Radiological Environmental Operating Report is hereby submitted for the calendar year 2003 in accordance with Technical Specification Section 5.6.2.

If you have any questions, please contact Mr. Rocco R. Sgarro at (610) 774-7552.

Sincerely, Shriver Attachments copy: NRC Region I Mr. R. V. Guzman, NRC Project Manager Mr. S. Hansell, NRC Sr. Resident Inspector Mr. R. Janati, DEP/BRP

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Susquehanna Steam Electric Station--

Units 1--&2 2003 ANN-UAL- REPORT . . .

.. -; Annual Radiological Environmental Operating

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SUSQUEHANNA STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT REPORT PERIOD: 12130/02 - 1/30/04 Prepared by:

F. J. Hickey Health Physicist Reviewed by:

i'- £D-ig R.E. Doebler Chemistry Support Supervisor - SSES Approved by:

B.E./Rhoads 72T9 Manager - Plant Chemistry PPL Susquehanna, LLC 769 Salem Boulevard Berwick, Pennsylvania 18603

TABLE OF CONTENTS

SUMMARY

AND CONCLUSIONS .................................................... 1 INTRODUCTION .................................................... 5 AMBIENT RADIATION MONITORING ................................................... 16 AQUATIC PATHWAY MONITORING ................................................... 20 ATMOSPHERIC PATHWAY MONITORING ................................................... 33 TERRESTRIAL PATHWAY MONITORING ................................................... 37 GROUND WATER MONITORING ................................................... 42 REFERENCES ................................................... 44 APPENDICES A. 2003 REMP CHANGES A-I B. 2003 REMP MONITORING SCHEDULE (SAMPLING AND ANALYSIS) B-I C. 2003 REMP MONITORING LOCATION DESCRIPTIONS C-1 D. 2003 LAND USE CENSUS RESULTS D-l E.

SUMMARY

DESCRIPTION OF SSES REMP ANALYTICAL E-1 METHODS F. 2003 EXCEPTIONS TO THE SSES TECHNICAL F-I REQUIREMENTS SAMPLE SCHEDULE, METHODS AND ANALYSIS SENSITIVITIES G. 2003 SSES REMP

SUMMARY

OF DATA G-1 H. COMPARISON OF INDICATOR AND CONTROL 2003 H-1 REMP ANNUAL MEANS FOR SELECTED MEDIA ANALYSIS RESULTS WITH MEANS FROM PREOPERATIONAL AND PRIOR OPERATIONAL PERIODS I. SPECIFIC ANALYSIS RESULTS TABULATED BY MEDIA I-I AND SAMPLING PERIOD J. PERFORMANCE

SUMMARY

FOR THE RADIOANALYSES OF J-1 SPIKED ENVIRONMENTAL SAMPLE MEDIA - 2003 i

LIST OF FIGURES Figure Numbers Title Page

1. Exposure Pathways to Humans 9

2. 2003 TLD Monitoring Locations within One Mile of the SSES 10

3. 2003 TLD Monitoring Locations from One to Five Miles of the 11 SSES

4. 2003 TLD Monitoring Locations Greater than Five Miles from the 12 SSES

5. 2003 Environmental Sampling Locations within One Mile of the 13 SSES

6. 2003 Environmental Sampling Locations from One to Five Miles of 14 the SSES

7. 2003 Environmental Sampling Locations Greater than Five Miles 15 from the SSES

8. Ambient Radiation Levels Based on TLD Data 19

9. Gross Beta Activity in Surface Water 30

10. Tritium Activity in Surface Water 31

11. Gross Beta Activity in Drinking Water 32

12. Gross Beta Activity in Air Particulates 36

13. Iodine-131 Activity in Milk 41 ii

SUMMARY

AND CONCLUSIONS Radiolo2ical Dose Impact The extent of the 2003 Radiological The amounts of the radionuclides Environmental Monitoring Program detected in environmental samples (REMP) sampling met or exceeded the during 2003 were very small, as in past requirements of the Susquehanna Steam years. Based on the radionuclide levels Electric Station (SSES) Technical measured by the REMP, the maximum Requirements. The types of analyses whole body dose or maximum organ that were performed on these samples dose to a member of the public from for the identification and quantification SSES operation is estimated to be less of radioactivity also met or exceeded than one-tenth of one percent of the per the SSES Technical Requirements. The unit dose guidelines established by the result of this effort was the verification Nuclear Regulatory Commission (NRC) of the SSES Effluent Monitoring as stated in 10 CFR 50, Appendix I.

Program data that indicate that the The maximum hypothetical off-site SSES operation has no deleterious whole body and organ doses from effect on the health and safety of the radionuclides detected by the REMP public or the environment. and attributable to the SSES operations were calculated to be approximately 0.0015 mrem/year.

By contrast, potassium-40, a very long-COMPARISON OF PERCENT OFA VERA GE ANNUAL PUBLIC EFFECTIVEDOSE-EQUIVALENT FROM OTHER SOURCES WITH THATFROM THE SSES Natural Background 81%

SSES

'0.0 1% Consumer Products (7 5%

Medical 14%

Sources for the values provided, with the exception of Susquehanna, are the following from NCRP Report #93 (1987): Tables 2.4 (Natural Background), 5.1 (Consumer Products), and 7.4 (Medical).

Report I 2003 Environmental Monitoring Radiological Environmental 2003 Radiological Monitoring Report I

II Summary and Conclusions lived, naturally occurring radionuclide radium-226 were reported in sediment.

found in the human body, is estimated These radionuclides are not related to to deliver an average annual dose to the the operation of the SSES. Doses from blood forming organs of individuals in the presence of these radionuclides were the United States of about 27 millirem. not included in the estimate of the dose While a small portion of the background from SSES attributable radionuclides.

dose from natural radiation sources, the.

potassium40 dose is still 18,000 times Man-made Radionuclides the estimated maximum whole body Although not all due to SSES operation, and organ doses to a hypothetical the following man-made radionuclides member of the public from ingestion of were reported at levels in the radionuclides attributable to the SSES. environment in excess of the MDCs for their respective analyses: tritium, The maximum direct radiation dose iodine-131 and cesium-137. These from SSES operation to a member of radionuclides, with the exception of the public was determined to be cesium-137, were identified in surface, approximately 0.0314 millirem/year. ground and drinking water. Tritium The total whole body dose from both was measured above minimum ingested radionuclides and direct detectable concentrations in some radiation is negligible compared to the surface water, drinking water, and public's exposure from natural ground water samples. Iodine-131 was background radiation, medical identified in surface water and drinking irradiation, and radiation from water. Cesium-137 was observed in consumer products of more than 300 sediment and soil.

millirem/year effective dose-equivalent.

Tritium is the only man-made Identified Radionuclides radionuclide attributed to SSES operation. Tritium in media other than and Their Dose the Susquehanna River water Contributions downstream of the SSES was attributed to both natural production by the Naturally Occurring interaction of cosmic radiation with the Radionuclides upper atmosphere and previous In 2003, the SSES REMP reported the atmospheric testing of nuclear weapons.

naturally occurring radionuclides The presence of cesium-137 was beryllium-7, potassium-40, radium-226, attributed to non-SSES sources.

and thorium-228 in the environment at Cesium-137 was considered to be levels exceeding the minimum present only as residual fallout from detectable concentrations (MDCs) for atmospheric weapons testing. Iodine-their respective gamma spectroscopic 131 was found in the aquatic pathway.

analyses. Beryllium-7 was identified in Evidence indicates that it is there only air and sediment. Potassium40 was as the result of the discharge of medical observed in fish, sediment, surface waste to the Susquehanna or water, ground water, milk, soil, and fruit Lackawanna Rivers through sewage and vegetables. Thorium-228 and treatment plants upstream of the SSES.

22 2003 Radiological Environmental Monitoring Report 2003 Radiological Environmental Monitoring Report

Summary and Conclusions AQUATIC PATHWAY All of the man-made radionuclides mentioned above were not analyzed for PERCENT TOTAL in all media. For example, no analyses GAMMA ACTIVITY were performed in an effort to determine iodine- 13 1 levels in ground SEDIMENT water. When selecting the types of r analyses that would be performed, Natural consideration was given to the potential -- 99.5% -

importance of different radionuclides in the pathways to man and the regulatory analysis requirements for various environmental media.

Marmade: MaMnmade:non-SSES SSES Relative Radionuclide Activity 0.1% 0.4% -

Levels in Selected Media Some media monitored in the _

environment are significant for the -

numbers of gamma-emitting radionuclides routinely measured at TERRESTRIAL PATHWAY _

levels exceeding analysis MDCs. -

=

Sediment in the aquatic pathway and PERCENT TOTAL _

soil in the terrestrial pathway are two GAMMA ACTIVITY _

such media.

SOIL The following pie graphs show the relative activity contributions for the types of gamma-emitting radionuclides _

reported at levels above the analysis MDCs in sediment and soil at indicator locations during 2003.

r

'\ NM ed SKSE ne%

Naturally occurring radionuclides _

accounted for 99.5 % and 99.4 % of the -

gamma-emitting activity in sediment and in soil, respectively, in 2003. Man- _

made radionuclides of SSES origin accounted for 0. 1% of the gamma- _

emitting activity in sediment during _

Monitoring Report 3 -

Radiological Environmental 2003 Radiological 2003 Environmental Monitoring Report =

3 A FEZ

I I Sumnanrv and Conclusions 2003. Man-made radionuclides of non-SSES origin account for the rest of the gamma-emitting activity in sediment and soil during 2003. Generally, the activity for naturally occurring radionuclides reported in sediment and soil dwarfs the activity of the man-made radionuclides also reported.

Radionuclides Contributingto Dosefromn SSES Operation Of the three man-made radionuclides reported in the environment by the SSES REMP, tritium is the only radionuclide attributable to SSES operation.

The dose to members of the public attributable to the identified Tritium was 0.0015 mrem.

Tritium was included in the dose calculation because it was identified in the REMP samples of water being discharged to the river. The concentration of tritium in the water and the volume of water discharged were used to determine the amount of tritium released. The presumed exposure pathways to the public from this radionuclide were drinking water taken from the Susquehanna River at Danville, PA, and eating fish caught near the SSES discharge to the river.

This assumption is based on the fact that tritium does not emit gamma radiation and the beta radiation emitted by tritium is not sufficiently penetrating to reach an individual on the shore.

Environmental Monitoring Report 4 2003 Radiological 2003 Radiological Enivironmental MNonitorin g Report

2 PPL has maintained a Radiological Environmental Monitoring Program Radiological Environmental (REMP) in the vicinity of the existing Monitoring Susquehanna Steam Electric 'Station Units 1 and 2 since April, 1972, prior to The enclosed information is consistent construction of both units and ten years with the objectives outlined in the SSES prior to the initial operation of Unit I in ODCM and in IOCFR50 Appendix I, ' September, 1982. The SSES is located Section IV.B.2, IV.B.3 and IV.C. on an approximately 1500 acre tract' along the Susquehanna River, five miles In addition to the steps taken to control northeast of Berwick in Salem and to monitor radioactive effluents Township, Luzerne County, from the SSES, the SSES Technical Pennsylvania. The area around the site Specifications also require a program is primarily rural, consisting for the radiological monitoring of the predominately of forest and agricultural environment in the vicinity of the SSES.' lands. (More specific information on The objectives of the SSES REMP are the demography, hydrology, as follows: meteorology, and land use characteristics of the area in the vicinity

• Fulfillment of SSES Technical of the SSES can be found in the Requirements' radiological Environmental Report (Reference 1),

environmental surveillance the Final Safety Analysis Report obligations,' (Reference 2), and the Final Environmental Statement (Reference 3)

• Verification of no detrimental for the SSES.) The purpose of the effects on public health and safety preoperational REMP (April, 1972 to and the environment from SSES September, 1982) was to establish a operations, baseline for radioactivity in the local environment that could be compared

• Assessment of dose impacts to the" with the radioactivity levels observed in public, if any, various environmental media throughout the operational lifetime of

• Verification of adequate SSES ' the SSES. This comparison facilitates radiological effluent controls, and assessments of the radiological impact of the SSES operation.

• Identification, measurement,'

'trending, and evaluation' of The SSES REMP was designed on the radionuclides' and their basis of the NRC's Radiological concentrations in critical Assessment Branch Technical Position environmental pathways near the on radiological environmental SSES. monitoring, as described in Revision/1, November 1979.(Reference 4) nirneta oitrn Rpr_

2003 203Rdilgca Radiological Environmental Monitoring Report Is

I I Introduction However, the REMP conducted by PPL the impact of the station operation.

for the SSES exceeds the monitoring Control locations have been situated at suggested by the NRC's branch sites where it is considered unlikely that technical position, as well as the SSES radiation or radioactive material from Technical Requirements in terms of the normal station operation would be number of monitoring locations, the detected. Indicator locations are sited frequency of certain monitoring, the where it is expected that radiation and types of analyses required for the radioactive material that might originate samples, and the achievable analysis from the station would be most readily sensitivities. detectable.

PotentialExposure Pathways Control locations for the atmospheric The three pathways through which and terrestrial pathways are more than radioactive material may reach the 10 miles from the station. Preferably, public from nuclear power plants are the the controls also are in directions from atmospheric, terrestrial, and aquatic the station less likely to be exposed to pathways. (Figure 1 depicts these wind blowing from the station than are pathways for the intake of radioactive the indicator locations. Control materials.) Comprehensive radiological locations for the aquatic pathway, the environmental monitoring must sample Susquehanna River, are upstream of the media from all of these pathways. station's discharge to the river.

Mechanisms by which people may be Indicator locations are selected exposed to radioactivity and radiation in primarily on the basis of proximity to the environment vary with the pathway. the station, although factors such as Three mechanisms by which a member meteorology, topography, and sampling of the public has the potential to be practicality also are considered.

exposed to radioactivity or radiation Indicator locations for the atmospheric from nuclear power plants such as the and terrestrial pathways are typically SSES are as follows: less than 10 miles from the station.

Most often, they are within 5 miles of

• inhalation (breathing) the station. Indicator locations in the Susquehanna River are downstream of

• ingestion (eating and drinking), and the station's discharge. Monitoring results from indicator locations are

• whole body irradiation directly compared with results from control from a plant or from immersion in locations. These comparisons are made the radioactive effluents. to discern any differences in the levels and/or types of radioactive material and/or radiation that might exist REMP Scope between indicators and controls and that During the operational period of the could be attributable to the station.

SSES, it has been important to establish two different categories of monitoring In 2003, the SSES REMP collected locations, called control and indicator more than 850 samples at more than 40 locations, to further assist in assessing 2003 Radiological Environmental Monitoring Report 66 2003 Radiological Environmental Monitoring Report

.- ' ' Introdtiction locations and performed more than supporting the effluent and 1,500 analyses. In addition, the REMP environmental monitoring for the SSES.

monitors ambient radiation levels using.

thermoluminescent dosimeters (TLDs) REMP MonitoringSensitivity at 84 indicator and control locations,.. The sensitivity of the SSES REMP was making as many as 336 radiation level demonstrated in 1986, following the measurements each year. The media problem with the Chernobyl reactor in monitored and analyses performed are the former Soviet Union. When the summarized in the table below. Chernobyl incident occurred, the SSES Figures 2 through 7 display the REMlvP. REMP was able to detect a relatively TLDs and sampling locations in the small increase in the level of gross beta vicinity of the SSES. Appendix C activity in air samples at both control provides directions, distances, and a,' and indicator locations, as well as the brief description of each of the locations presence of some specific radioactive in Figures 2 through 7. materials that are not normally.

observed.

Regulatory agencies also participate in monitoring the SSES environment and, Detection of radiation and radioactive also oversee PPL's monitoring efforts.. - material from the SSES in the The State of Pennsylvania's Department environment is complicated by the of Environmental Protection (PADEP). presence of naturally occurring radiation monitors air for radioactive particulates and radioactive materials from both.

and radioactive iodine. It also monitors terrestrial and cosmic sources. Man-milk, fruits and vegetables, surface and made radiation and radioactive material drinking water, fish, river sediments, from non-SSES sources, such as nuclear, and ambient radiation levels. PADEP fallout from previous nuclear weapons makes this data available to the NRC. tests and medical wastes, also can make Inspectors from the NRC regularly visit identification of SSES radiation and the SSES to review procedures and radioactive material difficult. Together, SSESREMP  :

Tsype of Monitoring Media Monitored.

Gross Alpha Activity Drinking Water. ,

Gross Beta Activity All Waters, except Ground Water, and Air Particulates Gamma-Emitting Radionuclide Activities All Media Tritium Activity All Waters Iodine-13 1 Activity Surface Water. Drinking Water,"Air & Milk' Exposure Rates Ambient Radiation Levels (by TLD) ._-:_._ : _-_,_I records, conduct personnel interviews, this radiation and radioactive material observe activities first-hand, and present background levels from which generally examine the programs an attempt is made to distinguish 200 R.ilo.a Eniomna Moiorn Reor .7........................ .

2003 Radiological Environmental Monitoring Report 7

I'I Introduction relatively small contributions from the PPL's contracted REMP radioanalytical SSES. This effort is further complicated by the natural variations laboratories are capable of meeting the analysis sensitivity requirements found j--

that typically occur from both in the SSES Technical Requirements.

monitoring location to location and with Summary descriptions of the analytical time at the same locations. procedures and the accompanying calculational methods used by the The naturally occurring radionuclides laboratories can be found in Appendix potassium-40, beryllium-7, radium-226, E.

and thorium-228 are routinely observed in certain environmental media. Additional terrestrial and aquatic Potassium-40 has been observed in all environmental monitoring is performed monitored media and is routinely seen independent of the SSES REMP by the at readily detectable levels in such Academy of Natural Sciences of media as milk, fish, fruits and Philadelphia, Pennsylvania. The vegetables. Seasonal variations in monitoring program is titled "Safety beryllium-7 in air samples are regularly Net" and an annual report is provided to observed. Man-made radionuclides, PPL Susquehanna, LLC. Although the such as cesium-137 left over from Safety Net program is not part of the nuclear weapons testing are often SSES REMP, the data has provided observed as well. In addition, the additional information relative to the radionuclide tritium, produced by both environmental impact of the operation cosmic radiation interactions in the of the SSES.

upper atmosphere as well as man-made (nuclear weapons), is another radionuclide typically observed.

Radioactivity levels in environmental media are usually so low that their measurements, even with state-of-the-art measurement methods, typically have significant degrees of uncertainty associated with them.(Refererce 5) As a result, expressions are often used when referring to these measurements that convey information about the levels being measured relative to the measurement sensitivities. Terms such as "minimum detectable concentration" (MDC) are used for this purpose. The formulas used to calculate MDCs may be found in Appendix E.

The methods of measurement for sample radioactivity levels used by JI S 0 3 R doo i a n io m na o ioi g R p r 8 2003 Radiological Environmental Monitoring Report

Exposure Pa)t:hways toSHumans ous"Effluent.;

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_-.p-7!!

C3 A k E~fflun Direct Irradiation

. II

-I I

I Fuel Transport i

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VW-Figure 1

FIGURE 2 2003 TLD MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES a~~~~MILE \x i aLco

FIGURE 3 2003 TLD MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES C-Q4

FIGURE 4 2003 TLD MONITORING LOCATIONS GREATER THAN FIVE MILES FROM THE SSES G-o5

FIGURE 5 2003 ENVIRONMENTAL SAMPLING LOCATIONS WITHIN ONE MILE OF THE SSES coG I

FIGURE 6 .

2003 ENVIRONMENTAL SAMPLING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES o

=

a o

=

a a

con

FIGURE 7 2003 ENVIRONMENTAL SAMPLING LOCATIONS GREATER THAN FIVE MILES FROM THE SSES

Ambient RadiationMonitoring AMBIENT RADIATION MONITORING INTRODUCTION due to locational differences' in such The principal or primary method for the factors as soil characteristics (amounts SSES REMP's measurement of ambient of organic matter, particle size, etc.),

radiation levels is the use of drainage opportunities,, and exposure'to thermoluminescent dosimeters (TLDs).,- sunlight.' Environmental TLDs can also The TLDs are crystals (calcium sulfate).- be affected by direct radiation (shine) capable of detecting and measuring low from the SSES turbine buildings during' levels of radiation by absorbing a operation, radwaste transfer and storagge, portion of the radiation's energy that is and radioactive gaseous effluents from incident upon them and storing the the SSES.

captured energy until the TLDs are processed (read). Processing involves. Unfortunately, TLDs do' not have any heating the TLDs to release their stored inherent ability to indicate the source of energy in the form of light and; the radiation to which'they are exposed.

measuring the intensity of the light that The placement of numerous TLDs in they emit. The intensity of the emitted the environment can facilitate decision-'

light is proportional to the amount of making about the possible radiation radiation to which they were exposed. sources'to which TLDs 'are exposed.'

Calibration of the TLD processors However, a method for evaluating TLD permits a reliable relationship to be ' data is still required. ' The SSES REMP established between the light emitted - relies on a statistically based approach and the amount of radiation dose to simultaneously compare indicator received by the TLDs; the result permits TLD data with control TLD data and accurate measurements of the ambient operational TLD data with'  ;

radiation in the environment.  : preoperational TLD data. This approach permits the flagging of Environmental TLDs are continually. environmental TLD doses that might' exposed to natural radiation from the-. have been produced by both nman-made ground (terrestrial radiation) and fromri sources of radiation, as well as natural the sky (cosmic) radiation. In addition, radiation sources. It also provides a they also may be exposed to man-made . means for attributing a portion of the radiation. Most of the environmental total TLD dose to SSES operation if TLD's natural radiation exposure comes appropriate. Appendix E, pages E-6 from sources in the ground.. These through E-1O, provides a description'of terrestrial sources vary naturally with . the process for evaluating the results of time due to changes in soil moisture, TLD measurements.

snow cover, etc. The natural-radiation, picture is complicated because the factors affecting radiation reaching the TLDs from the ground vary differently with time from one location to another 2003 Environmental Radiological Monitoring Report 16

I I A mbient RadiationiVonitoring Scope shown in the bar graph on the following page. Refer to Figure 8 which trends both indicator and control data quarterly TLDs from 1973 through 2003.

The area around the SSES was divided for monitoring purposes into sixteen The 2003 annual average exposures for sectors radiating outwards. from the indicator and'control locations were plant site, each encompassing an area 20.2 mRlstd. qtr. and 19.0 mR/std. qtr.,

described by an arc of 22.5 degrees.

respectively. The 2003 exposures are TLDs were placed in all 16 sectors at within the ranges of annual averages for varying distances from the plant.

the prior operational periods at each Monitoring locations were chosen type of monitoring location. Refer to according to the criteria presented in the Figure 8 at the end of this section which NRC Branch Technical Position on trends quarterly TLD results for both Radiological Monitoring (Revision 1, preoperational and operational periods November, 1979). The locations for the at the SSES. Refer to Appendix H, TLDs were selected by considering Table H I, page H 3 for a comparison of factors such as local meteorological, the 2003 mean indicator and control topographical, and population TLD results with the means for the distribution characteristics.

preoperational and prior operational periods at the SSES.

During 2003, the SSES REMP, had 76 indicator TLD locations and eight, Indicator environmental TLD results for control TLD locations. This level of 2003 were examined quarterly on an monitoring exceeds that which is individual location basis and compared required by the Nuclear Regulatory.

with both current control location Commission. The indicator TLDs results and preoperational data. Very nearest the SSES are positioned at the small SSES exposure contributions security or perimeter fences surrounding were suggested during 2003 at the the site. This is the closest that a following onsite locations: I S2, 6S4, member of the public would be able to 6S9,7S6,8S2,9S2,10S2,11S3,12S4, approach the station. The control TLDs are the most distant from the SSES, 13S2, 13S4, 13S5, 16S1, and 16S2.

Thus, there were 10 monitored locations ranging from 10 to 20 miles from the in 2003 where a SSES dose contribution site.

is considered to have been discernible.

Refer to Appendix E, page E-6, for'a Monitorin2 Results discussion of "TLD Data Interpretation." TLD results for all TLDs locations for each quarter of 2003 may TLDs were retrieved and processed be found in Appendix 1,Table I-1, quarterly in 2003. Average ambient beginning at page 1-2.

radiation levels measured by environmental TLDs generally remained constant throughout 2003, as 17 17 2003 Environmental Radiological Monitoring Report 2003 Environmental Radiological Monitoring Report

Ambient RadiationMonitoring 2003 REMP Quarterly TLD Averages

. 20.0 fl 15.0 Z 10.0 E 5.0 0.0 1 2 3 4 Calendar Quarters l kdicator U Control [

The estimated quarterly exposure contributions were summed by location for the entire year. The largest dose suggested was approximately 0.0314 mrem at an onsite monitoring location, 9S2, 0.2 mile south of the SSES. This dose was used for determining compliance with SSES Technical Requirement Limit 3.11.3 for annual effluent reporting purposes.

This dose amounts to only 0. 13% of the 25 mrem whole-body dose limit of SSES Technical Requirement 3.11.3.

18 2003 Environmental Monitoring Report Radiological Monitoring Environmental Radiological Report 18

FIGURE 8 - AMBIENT RADIATION LEVELS Exposure Rate (mR/STD Qtr) BASED ON TLD DATA 50 45 40 35 30 25 20 15 10 5

0 tmr tt_ o o 0 0 0 ON *N I- ON N4 N m4 as4 ON as ON ON 00 ON a, a s O C

" _4 " Wm V P.M V "m4 P e

-Indicator -Control

() O

Aquatic Pathwaiy Monitorini

-rAUATICPATHWAYM,,,ONITORING INTRODUCTION data for comparison with downstream The following media were monitored in monitoring results. The potential exists 2003 by the SSES REMP in the aquatic for radioactive material that might be pathway: surface water, drinking water, present in SSES airborne'releases to fish, and sediment. Some of the media enter the Susquehanna River upstream (e.g., drinking water and fish) provide' of the plant through either direct information that can be especially useful deposition (e.g., settling or washout) or to the estimation of possible dose to the by way of runoff from deposition on public from potentially ingested land adjacent to the river. However, radioactivity, if detected. Other media,' direct deposition and runoff are such as'sediment, can be useful for considered to be insignificant as means trending radioactivity levels in the of entry for SSES radioactivity into the aquatic pathway, primarily because of' Susquehanna River when compared to their tendency to assimilate certain liquid discharges under normal materials that might enter the surface conditions.

water to which they are exposed. The results from monitoring all of these Lake Took-a-While (LTAW), which is media provide a picture of the aquatic' located in PPL's Riverlands Recreation pathway that is clearer than that'which' Area adjacent to the Susquehanna could be obtained if one or more were' River, is also considered to be part of not included in the REMP. the aquatic pathway for monitoring purposes. Although it is not in a' Fruits or vegetables that are grown in position to receive water discharged to fields irrigated with surface water would the river from the'SSES, it can receive also be in the aquatic pathway. The storm runoff from the SSES. Storm' land use census (Reference 11) runoff from the SSES site should not conducted in 2003 looked at farms normally contain any measurable within 10 miles downstream of the radioactivity from the plant. However, SSES. Two farm fields were found to the SSES REMP, consistent with other have been irrigated during the 2003 aspects of aquatic monitoring and the growing season. REMP, in general, goes beyond its requirements by monitoring LTAW.

The aquatic pathway in the vicinity of the SSES is the Susquehanna River. Scope Monitoring of all of the aquatic media,'

except drinking water, is conducted' Surface Water both downstream and upstream of the Surface water was routinely sampled location from which occasional SSES - from the Susquehanna River at one low-level radioactive discharges enter indicator location (6S5) and one control' the river. The upstream monitoring location (6S6) at the SSES River Water locations serve as controls to provide Intake during 2003. Sampling also took 2003 Radiological Environmental Monitoring Report 20

I I Aquatic Pathway Monitoring' place at the following additional the Susquehanna River. In addition, indicator locations:' the SSES discharge sediment was also obtained from line to the river (2S7/6S7) and Lake location LTAW.

Took-A-While (LTAW).

Sampling Drinking Water Drinking water samples were collected Surfiace Water at location 12H2, the Danville Weekly grab sampling was performed at Municipal Water Authority's treatment the indicator location 6S5. Weekly grab facility on the Susquehanna River, in samples were composited both monthly 2003. Treated water is collected from and biweekly at this location. Location the end of the processing flowpath, 6S5 was considered a backup for representing finished water that is locations 2S7 and 6S7 in the event that suitable for drinking. This is the nearest water could not be obtained from the point downstream of the SSES automatic samplers at these locations.

discharge to the River at which drinking Nevertheless, 6S5 was sampled water is obtained. No drinking water routinely throughout 2003, since it is control location is sampled.' For all the closest downstream sampling point intents and purposes, control surface to the SSES discharge.

water sampling locations would be suitable for comparison. Indicator locations 2S7 and 6S7, the SSES Cooling Tower Blowdown Fish Discharge (CTBD) line, and control Fish were sampled from the location 6S6, the SSES River Water JH Susquehanna River in the spring and Intake structure, were sampled time fall of 2003 at one indicator location, proportionally using automatic IND, downstream of the SSES liquid continuous samplers. The samplers discharge to the River and one control were typically set to obtain 30-60 ml location, 211, sufficiently upstream to aliquots every 20-25 minutes. Weekly, essentially preclude the likelihood that the water obtained by these samplers the fish caught there would spend any was retrieved for both biweekly and time below the SSES discharge. In monthly compositing.

addition, fish were also sampled in the fall from PPL's Lake Took-a-While, The other surface water monitoring location LTAW. This location is not location, LTAW, was grab sampled downstream of the SSES discharge. It once each month.

is sampled because of its potential for receiving runoff from the SSES. Drinking Water LTAW is considered an indicator Treated water was sampled time location. proportionally by an automatic sampler.

The sampler was typically set to obtain Sediment three 12-ml aliquots every twenty Sediment sampling was performed in minutes. Weekly, the water obtained by the spring and fall at indicator locations this sampler was retrieved for both 7B and 12F and control location 2B on biweekly and monthly compositing.

2003 Radiological Environmental Nlonitoring Report 21 2003 Radiological Environmental Monitoring Report

1-Aquatic

. Pathvay Monitorinz Fish Monitoring Results Fish were obtained by electrofishing.  !

Electrofishing stuns the fish and allows Surface Water them to float to the surface so that those Results from specific sample analyses of the desired species and sufficient size of surface water may be found in can be sampled. Sampled fish include Tables 1-2 and 1-3 of Appendix I. A recreationally important species, such as summary of the 2003 surface water data smallmouth bass, and also channel may be located in Table G of catfish and shorthead redhorse. The Appendix G. Comparisons of 2003 fish are filleted and the edible portions monitoring results with those of past are kept for analysis. years may be found in Tables H 2 through H 4 of Appendix H.

Sediment Shoreline sediment was collected to The Nuclear Regulatory Commission depths of four feet of water. (NRC) requires that averages of the activity levels for indicator; Sample Preservation environmental monitoring locations and and Analysis'

. I for control environmental monitoring locations of surface water, as well as other monitored media, be reported to Surface andDrinking Water the NRC annually. Data from the Surface and drinking water samples following three surface water .

were analyzed monthly for beta monitoring locations were averaged activities, the activities of gamma- together as indicators for reporting,;

emitting radionuclides, and tritium purposes: one location (6S5) on the activities. Biweekly composite samples. Susquehanna River downstream of the were analyzed for I-131. In addition, SSES, Lake-Took-a While (LTAW) drinking water samples were analyzed . adjacent to the river, and the SSES for gross alpha activity. cooling tower blowdown discharge, (CTBD) line to the river (2S7).

The use of nitric acid and sodium.,.

bisulfite as preservatives in surface and Technically, the CTBD line is not part drinking water samples was of the environment. The CTBD line is a discontinued in 2003 (at the request of below ground pipe to which the public the vendor laboratory). has no access, contrary to the other.

environmental monitoring locations on Sediment andFish the Susquehanna River to which the Fish are frozen until shipment. All public does have access. However;,

samples are analyzed by gamma currently there is no automatic spectroscopy for the activities of any composite sampling of an indicator gamma emitting radionuclides that may location on the Susquehanna River, so be present. the CTBD line from the SSES is included as an indicator monitoring 22 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report 22

I'I Aquatic PathwayMonitoring location in the radiological as the discharged water mixes with the environmental monitoring program. much larger flow of river water. The mean flow rate of the Susquehanna I, Most of the water entering the River in 2003 was approximately Susquehanna River through the SSES 9,910,000 gpm.' This is more than CTBD line is simply water that was 1,900 times the required minimum flow taken from the river upstream of the rate through the CTBD for discharges to SSES, used for cooling purposes be permitted.

without being radioactively!

contaminated by SSES operation, and The amounts of radioactively returned to the river. Nevertheless, contaminated water being discharged batch discharges of relatively small are small. Nevertheless, sensitive volumes of slightly radioactively analyses of the water samples can often contaminated water are made to the detect the low levels of certain types of river through the SSES CTBD at times radioactivity in the CTBD water throughout each year. The water is following dilution. Though the levels released from tanks of radioactively of radioactivity measured in the CTBD contaminated water on site to the CTBD water are generally quite low, they tend and mixes with the noncontaminated to be higher than those in the river water already present in the CTBD. downstream of the SSES. Most Flow rates from the tanks containing radionuclides discharged from the SSES radioactively contaminated water being CTBD are at such low levels in the discharged to the CTBD vary based on downstream river water that, even with the radioactivity level of the batch the sensitive analyses performned, they release. In addition, the minimum flow cannot be detected.

rate for the returning water in the CTBD is maintained at a flow rate of 5,000 When the radioactivity levels from the gpm or higher. These requirements are CTBD samples throughout the year are in place to ensure adequate dilution of averaged with those obtained from radioactively contaminated water by the actual downstream monitoring returning noncontaminated water in the locations, the result is an overall CTBD prior to entering the river. indicator location average that is too high to be'representative' of the actual At the point that CTBD water enters the average radioactivity levels of the river, additional, rapid dilution of the downstream river water. As the discharged water by the river is following discussions are reviewed, promoted by releasing it through a consideration should be given to this diffuser. The diffuser is a large pipe inflation of average radioactivity levels with numerous holes in it that is from the inclusion of CTBD (location positioned near the bottom of the river. 2S7/6S7) results in the indicator data CTBD discharges exit the diffuser that is averaged.

through the many holes, enhancing the mixing of the discharge and river The 2003 data for gross beta activity waters. The concentrations of analyses of surface water indicator contaminants are reduced significantly locations is higher than those of 2002.

Environmental Monitoring Report Radiological Environmental 2003 Radiological 23 23 2003 Monitoring Report

- Aquatic Pathway Monitoring The 2003 !mean gross beta 'activity of periods of the SSES. The 2003 control 6.1 pCiAiter for indicator locations is' mean activity is less than the averages greater than the 2002 indicator mean of the annual means for control gross beta activity of 5.4 pCiAiter. The' locations for the prior operational and 2003 indicator mean activity is within preoperational peiiod of the SSES.

the range of the annual means for the previous operational period of the Throughout the course of a year, iodine-SSES. The 2003 mean gross beta 131 is typically measured at levels in activity of 2.4 pCiAiter for control excess of analysis MDCs in some locations is less than the 2.9 pCilliter samples obtained from control surface for the 2002 control mean gross beta water monitoring locations on the activity. The 2003 control mean Susquehanna River upstream of the' activity is within the range of the annual SSES as well as indicator locations means for previous operational periods. downstream of the SSES. 'As The 2003 control mean is below the" determined by measurements of range of annual means for samples obtained by the SSES REMP, preoperational periods. 'Refer to the mean iodine-131 activity level from Figure 9 which trends gross beta the CTBD for all of 2003 was activities separately for surface water. approximately 0.78 pCi/liter. This may indicator and control locations quarterly be compared to the activity level of from 1975 through 2003. 0.26 pCi/liter for control surface water monitoring locations in 2003.

Comparison of the 2003 indicator mean (6.1 pCi/l) to the 2003 control mean Iodine-131 from the discharge of (2.4 pCi/1) suggests a contribution of medical wastes into the Susquehanna beta activity from the SSES. The 2003 River upstream of the SSES is drawn data is similar in this regard to the into the SSES cooling tower basins" averages of annual means for indicator through the SSES River Water Intake and control locations for the prior Structure. It is reasonable to assume operational period. 'During the pior that concentration of the already operational period, the average of ' . existing io'dine-131 in the cooling tower annual indicator means exceeds the basins occurs as it does for other' average of annual control means for substances found in the river. For gross beta activity. example, the SSES routinely assumes concentration'factors in the basin for The 2003 means for iodine-131'activity' calcium of four to five times the at indicator and control surface water concentrations in the river water moitoring location's monitrn loaton wee0.36 were 03 pCi/liter

~/ie entering the basins, based on past and 0.26 pCi/liter, respectively. The measuremnents. This concentrating:

2003 indicator and control means are effect occurs because of the evaporation' less than the corresponding 2002 means.; of the water in the basins, leaving The 2003 indicator mean activity is behind most dissolved and suspended greater than the averages of the annual' materials in the unevaporated water means for indicator locations for the' remaining in the basins. If a prior operational and preoperational concentration factor of four for iodine-24 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report 24

I I Aquatic Pathway Monitorine 131 were to be applied to the 2003 from the SSES to the Susquehanna mean iodine- 131 activity level for the River during 2003.

control samples from the Susquehanna River, a mean concentration of The 2003 mean tritium activity for 1.04 pCi/liter for iodine-131 in the basin indicator locations is more than the water and the water being discharged corresponding 2002 mean. The 2003 from the basins would be expected. The means for tritium activity at indicator actual 2003 mean of 0.78 pCi/liter for and control locations were the CTBD iodine-131 activity level was 1,567 pCi/liter and 31.8 pCi/liter, less than this. respectively. The 2003 indicator mean is greater than the annual average mean Because iodine-131 is radioactive, for prior operational and preoperational unlike the calcium that has been periods of the SSES. Note that the 2003 measured, iodine-131 is removed from mean tritium activity at indicator the water while it is in the basins locations is higher than the range for through the radioactive decay process. both operational and preoperational Thus, it might be expected that the net periods. The control mean is 'withinthe concentration factor for iodine-131 range of the corresponding annual mean would be somewhat less than that for reported for the prior operational period calcium, considering this additional of the SSES. Refer to Figure 10 which removal process. The extent to which trends tritium activity levels separately the iodine- 131 concentration factor is for surface water indicator and control less than that for calcium would depend locations from 1972 through 2003.

on the mean residence time for the water in the basins compared to iodine- The 2003 indicator mean tritium level 131 's radioactive half-life - the greater for all surface water locations can be the ratio of the mean residence time to misleading for those interested in the the half-life, the smaller the mean tritium level in the Susquehanna concentration factor. A mean residence River downstream of the SSES for time for water in the basins is expected 2003. The much higher levels of tritium to be about two days. This is only about observed in the CTBD line (location one-fourth of the approximately eight- 2S7/6S7), when averaged with the low day half-life of iodine- 131. Thus, levels from the downstream location radioactive decay would not be 6S5 sample analysis results distort the expected to reduce the concentration real environmental picture. The mean factor for iodine-131 by a large amount. tritium activity level from indicator Therefore, the difference between the location 6S5 for 2003 was 140 pCi/liter, 2003 mean iodine-131 activity of about which is greater than the mean tritium 0.78 pCi/liter in the CTBD and the 2003 activity, 31.8 pCi/liter, for the control mean iodine- 131 activity for the control location, but is within the range of prior location of 0.26 pCi/liter should be the operational' and preoperational periods.

result of concentration in the basins.

Iodine-131 was not reported to have In spite of the fact that the tritium been discharged with water released activity levels reported for 2S7/6S7 are from the discharge line prior to dilution Environmental Monitoring Report 25 25 2003 Radiological 2003 Radiological Environmental Monitoring Report

- Aquatic PathiwavMonitorine in the river, the highest quarterly Susquehanna River upstream of the average tritium activity reported at SSES and therefore no drinking water 2S7/6S7 during 2003 was' control monitoring locations. Danville' approximately 6,990 pCi/liter for the drinking water analysis results may be first quarter, well below the NRC non- compared to the results for surface routine reporting levels for quarterly' -" water control monitoring locations.

average activity levels of' 20,000 pCi/liter when a drinking water Results from specific sample analyses pathway exists or 30,000 pCi/liter when of drinking water may be found in no drinking water pathway exists., Table I-4 of Appendix 1. A summary of the 2003 drinking water'data may be The tritium activity reported in the located in Table G of Appendix G.

CTBD line from location 2S7/6S7 is,' Comparisons of 2003 monitoring results attributable to the SSES. Refer to the with those of past years may be found in "Dose from the Aquatic Pathway" Tables H 5 through H 7 of Appendix H.'

discussion at the end of this section for additional information'on the projected Gross alpha activity has been monitored dose to the population from fritiuhiand in' drinking water since 1980. Gross other radionuclides in the aquatic alpha activity has been observed at pathway attributable'to' the SSES. levels above the analysis MDCs in a small minority of the samples during With the following exceptions, no most years since 1980. The 2003 -mean gamma-emitting radionuclides were - gross alpha activity level for.drinking measured in surface water primary water was 0.18 pCi/liter. The 2003 samples at an activity level exceeding mean alpha activity level is within the an analysis MDC in 2003: potassium- range of the corresponding annual 40 and iodine-131. - means for the prior operational years.

No gross alpha activity in drinking Drinking Water - water during 2003 is attributed to liquid Drinking water was monitored during discharges from the SSES to the' 2003 at the' Danville Water Compay's Susquehanna River.

facility 26 miles WSW ofthe SSES on, the Susquehanna River. Fromi 1977- ; Gross beta activity has been monitored' (when drinking water samples were first in drinking water since 1977. '.Gross collected) through 1984, drinking 'vatei beta activity is typically measured at samples were also 'obtaine6d from the"` levels exceeding the MDCs in drinking Berwick Water Company at location"' water samples. The 2003 nmean gross 12F3,' 5.2 miles WSW of the SSES. beta activity level for drinking water The drinking water suoply for the' was 2.13 pCi/liter. The 2003 me'an is Berwick'Water Company is not,, below the 2002 mean gross beta activity however, water from the Susquiehanna " level for drinking water but within the' River; it is actually well waterr.- "e range of the corresponding annual means for prior operational periods.

There are no known drinking water The 2003 mean is below the range of supplies in Pennsylvania on the the'corresponding annual means for 2003 RailgclEvrnetlntrn eot2 2003 Radiological Environmental Monitoring Report 26

I I Aquatic Pathway Afonitoring preoperational periods. Refer to above the analysis MDCs for gamma Figure I1 which trends'gross beta spectroscopic analyses of drinking water activity levels separately for drinking samples during 2003.

water indicator and control locations' from 1977 through 2003. No gross beta Fish activity in drinking water during 2003 is Results from specific sample analyses attributed to liquid discharges from the of fish may be found in Table I 5 of SSES to the Susquehanna River. Appendix 1. A summary of the 2003 fish data may be located in Table G of Iodine-1 31 was measured in excess of Appendix G. A comparison of 2003 analysis MDCs in 2 out of 26 drinking monitoring results with those of past water samples in 2003. This compares years may be found in Table H 8 of with results from 6 samples for which Appendix H.

analysis MDCs were exceeded in 2002.

The 2003 mean iodine-131 activity level Three species of fish were sampled at in drinking water samples was each of one indicator location and one 0.18 pCi/liter. This is less than the control location on the Susquehanna 2002 mean drinking water activity level River in May 2003 and again in October of 0.22 pCi/liter. Also, it is less than 2003. The species included the the 2003 mean of 0.26 pCi/liter for the following: smallmouth bass, channel surface water control location. No catfish, shorthead redhorse,'and white iodine-131 activity in drinking water sucker. In addition, one largemouth during 2003 is attributed to liquid bass was sampled from PPL's LTAW.

discharges from'the SSES to the Susquehanna River.

A total of 13 fish were collected and Ji analyzed.

Tritium was measured in excess of The only gamma-emitting radionuclide analysis MDCs twice in 2003 in reported in excess of analysis MDCs in drinking water.. The 2003 mean tritium fish during 2003 was naturally activity level for drinking water was occurring potassium-40. The 2003 62 pCi/liter. The 2003 mean is equal to indicator and control means for the the averages of the corresponding activity levels of potassium-40 in fish annual means for both the prior were 3.57 pCi/gram and 3.16 pCi/gram, operational and preoperational periods respectively. The 2003 indicator and of the SSES. The 2003 mean tritium control means were less than the 2002 activity level for drinking water is means. Both the 2003 indicator and higher than the 2003 mean tritium control means are within the ranges of activity level for the surface water their corresponding annual means for control location. Tritium activity in prior operational years. The 2003 drinking water can be attributed to indicator mean is greater than the range liquid discharges from the' SSES to the of corresponding annual means for Susquehanna River. preoperational periods. The 2003 control mean is within the range of With the exception of I-13.1, no gamma- corresponding annual means for emitting radionuclides were measured preoperational periods. Naturally Environmental Monitoring Report 27 27 2003 Radiological 2003 Radiological Environmental Monitoring Report

Aquatic Pathway Afonitorinj occurring potassium-40 in fish is not 2002 mean. The 2003 control mean attributable to the liquid discharges radium-226 activity is lower than the from the SSES to the Susquehanna corresponding 2002 means. The 2003 River. radium-226 mean was above the range of corresponding annual means for all Sediment prior operational years. The 2003 Shoreline sediment was sampled in May control mean was within the range of 2003 and again in October 2003. corresponding annual means for all Results from specific sample analyses prior operational years.

of sediment may be found in Table I-6 of Appendix I. A summary of the 2003 The 2003 indicator and control means sediment data is located in Table G of for thorium-228 activity levels in Appendix G. Comparisons of 2003 shoreline sediment were 3.2 and monitoring results with those of past 3.0 pCi/gram, respectively. The 2003 years may be found in Tables H 9 indicator and control means are higher through H 12 of Appendix H. than the corresponding 2002 means.

The 2003 indicator and control means Naturally occurring potassium40, are greater than the range of radium-226, and thorium-228 were corresponding means for prior measured at activity levels above operational years. The naturally analysis MDCs in all shoreline sediment occurring radionuclides in sediment samples in 2003. discussed above are not attributable to the liquid discharges from the SSES to The 2003 indicator and control means the Susquehanna River.

for potassium-40 activity levels in shoreline sediment were 12.3 pCi/gram Cesium-137 was measured at activity and 12.9 pCi/gram, respectively. :The levels in shoreline sediment exceeding 2003 indicator mean for potassium40 analysis MDCs in 5 of 6 analyses during activity is less than the corresponding 2003. The 2003 indicator and control 2002 mean. The 2003 control mean is means for cesium-137 activity levels in greater than the corresponding 2002 sediment were 0.07 pCi/gram and mean. The 2003 indicator and control 0.08 pCi/gram, respectively. The 2003 means were within the ranges of indicator mean is greater than the corresponding annual means for all corresponding 2002 mean. The 2003 prior operational years. The 2003 control mean is less than the indicator and control means were corresponding 2002 mean. The 2003 greater than the ranges of corresponding indicator and control means are less means for preoperational periods. than the average of corresponding annual means for both prior operational The 2003 indicator and control means as well as preoperational years. The for radium-226 activity levels in cesium-137 in sediment is attributed to shoreline sediment were 2.38 pCi/gram residual fallout from past atmospheric and 1.6 pCi/gram, respectively. The nuclear weapons tests.

2003 indicator mean radium-226 activity is higher than the corresponding 28 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report 28

I I Aquatic PathwayMonitorinz Dose from the Aquatic This estimate is 3 curies less than the amount of tritium determined by Pathway effluent monitoring to have been J released to the river by the SSES in Tritium was the only radionuclide 2003. This agreement between the identified in 2003 by the SSES REMP estimate based on environmental in the aquatic pathway that was monitoring and the amount reported by attributable to SSES operation and also effluent monitoring is consistent with included in the pathway to man. previous years comparisons.

The total tritium activity released from Given the total tritium activity released, the SSES for the year was estimated the maximum whole-body and organ based on REMP monitoring results for doses to hypothetical exposed use in projecting maximum doses to the individuals in four age groups (adult, public. This estimate assumed that the teenager, child, and infant) were tritium was present continuously in the determined according to the CTBD line throughout 2003 at a level methodology of the Offsite Dose equivalent to the annual mean activity Calculation manual using the RETDAS level of tritium. It was also assumed computer program. This is in that the annual average activity level of accordance with SSES Technical tritium being contributed to the Requirement 3.11.4.1.3.

Susquehanna River water could be represented by the difference between The maximum dose obtained from the the annual mean activity levels of ingestion of tritium was estimated at the tritium in the CTBD line (without nearest downriver municipal water correction for cooling tower basin supplier via the drinking water pathway reconcentration) and in the river and near the outfall of the SSES upstream of the SSES. discharge to the Susquehanna River via the fish pathway. The maximum whole The annual mean activity level of body and organ doses were each tritium in the CTBD line (monitoring estimated to be approximately location 2S7\6S7) for 2003 was 0.0015 mrem.

4,416 pCi/A. The annual mean activity level for the river upstream of the SSES (monitoring location 6S6) was approximately 32 pCi/l. Thus, the difference in the mean activity levels for these two locations was about 4,384 pCi/A. The annual mean flow rate for the CTBD line was 7,703 gpm.

Using the proper unit conversions and multiplying 7,703 gpm times 4,384 pCiAl yields a value of 67.2 curies for the estimate of tritium released during 2003 based on the results of radiological environmental monitoring. .S Environmental Monitoring Report 29 2003 Radiological 2003 Radiological Environmental MSonitoring Report

FIGURE 9 - GROSS BETA ACTIVITY IN SURFACE WATER pCi/Liter 20 18 16 14 12 10 8

6 4

2 0

-2

-4

-Indicator - Control C})

FIGURE 10 - TRITIUM ACTIVITY IN SURFACE WATER pCi/Liter 3000 2500 2000 1500 1000 500 0

-500

, 49<9 4 ,4' e ,9 e e e f e4 e e ,4 w.f S

- Indicator - Control CV7_t

C C (

FIGURE 11 - GROSS BETA ACTIVITY IN DRINKING WATER 10 pCiLitr 9

PREOPERATIONAL OPERATIONAL 8-7-

6-5 Unit 2 Criticality 4

3 2

I I<~t 1o-_lllllllll 9 49 9 9°°9 ,4

Atmospheric PathwayMonitorinR -

ATMOSPHERIC ATHWAY MONITORING-'".,

C. . 1, - Sampling and Anialysis INTRODUCTION Air Atmospheric monitoring by the SSES The SSES REMP monitored the air at REMP involves the sampling and four indicator locations and two control analysis of air. Because the air is the locations durin'g 2003. The SSES first medium that SSES vent releases { Technical Requirements require enter in the pathway to man, it is monitoring at'only a total of five sites.

fundamental that it be monitored. Monitoring is required at three locations.

Mechanisms do exist for the transport at the SSES site'boundary in different of airborne contaminants to other media sectors with the greatest predicted and their concentration in them. For sensitivities for the'detection of SSES example, airborne contaminants may releases. Monitoring must be performed move to the terrestrial environment and at the community'in the'vicinity of the concentrate in milk. Concentrations of SSES with the greatest predicted radionuclides can make the sampling sensitivity. A control l6cation that is and analysis of media like milk more expected to be u niffected by any routine sensitive approaches for the detection of. SSES releases must be monitored.

radionuclides, such as iodine-131, in the pathway to man than the monitoring of, Airborne particulates were collected on air directly. (PPL also samples milk; glass fiber filters' using low volume.

refer to the Terrestrial Pathway (typically 2.0 to 2.5 cfm sampling rates)

Monitoring section of this report.) air samplers that run continuously. Air Nevertheless, the sensitivity of air iodine samples were collected on' monitoring can be optimized by the charcoal cartridges, placed downstream proper selection of sampling techniques of the particulate filters.

and the choice of the proper types of.,

analyses for the collected samples. Particulate filters and charcoal' cartridges were exchanged weekly at the Scope air monitoring sites. Sampling times were recorded on ' elapsed-tim-e meters.'

Air samples were collected on Air sample volumes for particulate particulate filters and charcoal 2,

. . r 1.

filters and charcoal cartridges were cartridges at indicator locations 3S I measured with dry-gas meters.

12S1, 13S6 and 12E1, and control locations 6G1 and 8G1. -- : Air filters were analyzed weekly for gross beta 'activity, then composited quarterly and analyzed for the activities of g'amma-emitting'radionuclides. The charcoal cartridges were analyzed weekly for iodine-131.

niometlMntrn eot3 2003 203Rdooia.

Radiological Environmental Monitoring Report 33

I I Atmospheric Pathway Monitoring Monitoring Results on the higher mean activity reported for indicator location.

Air Particulates The SSES Technical Requirements Gross beta activity is always measured Manual requires radionuclide analysis if at levels in excess of the analysis MDCs any weekly gross beta result was greater on the fiber filters. The highest gross than ten times the yearly mean of beta activity levels that have been control sample results. This condition measured during the operational period did not occur during 2003.

of the SSES were obtained in 1986 following the Chernobyl accident in the former Soviet Union. Figure 12 trends Quarterly gamma spectroscopic measurements of composited filters the quarterly mean gross beta activities often show the naturally occurring for the indicator and control locations separately from 1974 through 2003. radionuclide beryllium-7. Occasionally, other naturally occurring radionuclides, Note that prior to SSES operation, potassium-40 and radium-226, are also before 1982, the unusually high gross observed. Beryllium-7 is cosmogenic in beta activities were generally attributable to fallout from atmospheric origin, being produced by the nuclear weapons tests. Typical gross interaction of cosmic radiation with the beta activities measured on air earth's atmosphere. The other two particulate filters are the result of gamma-emitting radionuclides originate from soil and rock.

naturally occurring radionuclides associated with dust particles suspended in the sampled air. They are thus Beryllium-7 was measured above analysis MDCs for all quarterly terrestrial in origin.

composite samples in 2003. The 2003 Particulate gross beta activity levels for indicator and control means for each monitoring location and beryllium-7 activity were

9. 1OE-2 pCi/m.3 , and 8.20E-2 pCi/M3, monitoring period in 2003 are presented respectively. The 2003 means are lower in Table I-8 of Appendix I.

than the corresponding 2002 means.

Comparisons of 2003 gross beta The 2003 indicator and control means analysis results with those of previous were lower than the averages of the years may be found in Table H 13 of Appendix H. For 2003, the annual corresponding annual means for the prior operational and preoperational means for the beta activities of the periods. Beryllium-7 activity levels for indicator and control locations are each 2003 calendar quarter at each 1.47E-2 pCi/nm3 and 1.34E-2 pCi/mI3 ,

monitoring location are presented in respectively. These are near the low end Table 1-9 of Appendix I. Comparisons of the corresponding ranges of previous of 2003 beryllium-7 analysis results operational yearly averages. They are with previous years may be found in significantly below the corresponding Table H 14 of Appendix H. Potassium-lower ends of their preoperational yearly averages. A contribution of radioactivity 40 was measured above analysis MDCs for one quarterly composite sample from the SSES may be suggested from during 2003 (control location 6G1).

the 2003 airborne gross beta data based 2003 Radiological Environmental Monitoring Report 34 2003 Radiological Environmental Monitoring Report

Atmospheric Pathway Monitoring No other gamma-emitting radionuclides were reported for air in 2003.

Beryllium-7 and potassium40 are not attributable to SSES operation.

Air Iodine Iodine-131 has been detected infrequently from 1976, when it was first monitored, through 2003. Since operation of the SSES began in 1982, iodine-131 has only been positively detected in air samples in 1986 due to the Chernobyl accident. No iodine-131 was reported for the 2003 air monitoring results.

2003 Radiological Environmental Monitoring Report 35

44 FIGURE 12 - GROSS BETA ACTIVITY IN AIR PARTICULATES E-03 pCi/M3 500 450 400 350 300 250 200 150 100 50 0

41

- Indicator - Control c 3

TerrestrialPathway MonitorinjR - " -

-IN-TERRESTION ;PTT'W-YAT MONITORING-INTROD~UCTION----:

either medium. Sampling is performed The following media were monitored in at different depths near the surface to the Terrestrial Pathway in 2003: soil, help provide information on how milk, fruits and vegetables. recently certain radioactive materials may have entered the soil: Sampling at Soil can be a great accumulator of man- more than one depth also may help made radionuclides that enter it. The' ensure the detection of materials that extent of the accumulation in the soil move relatively quickly through the soil.

depends of course on the amount of the,. Such quick-moving materials may have radionuclides reaching it, but it also already passed through the topmost depends on the chemical nature of those layer of soil at the time of sampling.

radionuclides and the particular characteristics of the soil. For example,'; Milk was sampled at four locations and the element cesium, and, therefore, fruit and vegetable samples were cesium-137 can be bound very tightly to obtained at 2 locations in 2003. SSES clay in soils. The amount of clay in s6il Technical Requirements require that the can vary greatly from' one location to SSES REMP'samnple milk at the three another. In clay soils, cesium-137 may' most sensitive monitoring locations move very slowly and also may be taken' near the SSES and one control location up very slowly in plants as they absorb distant from the SSES. SSES Technical soil moisture. - Requirements only require that fruit and vegetables be sampled at locations Any medium, such as soil, that tends to irrigated by Susquehanna River water accumulate radioactive materials 'can from points downstream of the SSES also provide more sensitivity for discharge to the River. There are only:

radionuclide detection in the three locations withinr 10 miles environment than those media that downstream of the SSES that have been' don't. Such a medium facilitates the known to irrigate with water from the early identification of radionuclides in l! '; Susquehanna River during unusually the environment, as well as awareness' dry periods. These locations do not of changes that subsequently may occur &' irrigate every year. Irrigation was in the environmental levels of the' performed at the Chapin Farms "Drake identified radionuclides. Field" (11F2) and the Lupini Farm "Route 93 Nescopeck Field" (11D2),

The SSES REMP samples'soil near four during 2003 as identified by the 2003 of the six REMP air sampling stations. ' Land Use Census (Reference 11).

The purpose for soil sampling near the'i air sampling sites is to make it easierit'o"" No requirement exists for the SSES correlate air sampling results with soil' REMP to monitor soil. All monitoring sampling results if any SSES related of the terrestrial pathway that is radioactive material were found in conducted by the SSES REMP in 200 R- iloia Eniomna oitrn eot3 2003 Radiological Environmental Monitoring Report 37

I I TerrestrialPathway Monitoring addition to milk and certain fruit and Fruitsand Vegetables vegetables is voluntary and reflects Potatoes were sampled during the I PPL's willingness to exceed regulatory harvest season at 2 locations requirements to ensure that the public surrounding the SSES. A total of 2 and the environment are protected. samples were collected from locations I1D2, and I1F2.

Scope Both locations were identified as having Soil irrigated with Susquehanna River water Soil was sampled in September 2003 in from downstream of the SSES during accordance with its scheduled annual 2003. There are often years with sampling frequency, at the following adequate rainfall when no irrigation is four REMP air sampling locations, 3S2, performed.

12S1, 13S6, and 8G1. Location 8G1 was a control sampling location; the Sample Preservation remaining sampling sites were indicator and Analysis locations.

All media in the terrestrial pathway are Twelve soil plugs were taken at selected analyzed for the activities of gamma-spots at each monitoring location. The emitting radionuclides using gamma plugs were separated into "top" spectroscopy. The other analysis that is (0-2 inches) and "bottom" (2-6 inches) routinely performed is the segments. Each set of top and bottom radiochemical analysis for iodine-131 in segments was composited to'yield 2 soil milk. The use of sodium bisulfite as a samples from each location for analysis. preservative in milk samples was Since there are four monitoring discontinued in 2003 (at the request of locations, a total of 8 soil samples were the vendor laboratory).

analyzed in 2003.

Monitoring Results Milk Milk was sampled at least monthly at The only man-made radionuclides the following four locations in 2003: normally expected at levels in excess of 10D1, 10D2, 12B2 and 10Gi. analysis MDCs in the terrestrial pathway are strontium-90 and cesium-Milk was sampled semi-monthly from 137. Both of these radionuclides are' April through October when cows were present in the environment as a residual more likely to be on pasture. Locations from previous atmospheric nuclear IODI, 10D2, and 12B2 are believed to weapons testing.

be the most sensitive indicator sites available for the detection of Strontium-90 analyses are not now radionuclides released from the SSES. routinely performed for any media Location IOGI is the control location. A samples in the terrestrial pathway.

total of 76 milk samples from both Strontium-90 activity would be indicator and control locations were expected to be found in milk. SSES analyzed in 2003. Technical Requirements do not require 2003 Radiological Environmental Monitoring Report 38

Terrestrial Pathway Monitoinz 2 - " -

that milk be analyzed for strontium-90. results were similar to those for Strontium-90 analyses may be' previous years. No other gamma-performed at any time if the results of emitting radionuclides were reported at other milk analyses would show. levels above analysis MDCs.

detectable levels of fission product activity which might suggest the SSES The 2003 means for indicator and as the source. control location sample potassium40 activity were 14.4 pCi/gram and Cesium-137 normally has been 10.6 pCi/gram, respectively. The measured in excess of analysis MDCs in indicator and control means are within most soil samples.'Although game is_ the range of corresponding means for not currently'being monitored, cesium- both prior operational and 137 has also been'seen often at levels preoperational years. This is not the above the MDCs in game in the past. result of SSES operation because the potassium-40 is naturally occurring. The Certain naturally occurring 2003 indicator and control means for radionuclides are also routinely found potassium-40 were greater than the above analysis MDCs in terrestrial' corresponding 2002 means.

pathway media. Potassium-40, a primordial and very long-lived Ra-226 analysis of soil samples was radionuclide, which is terrestrial in' deleted from the SSES REMP in 2002.

origin, is observed in all terrestrial Ra-226 was not performed on any soil pathway media. Other naturally samples in 2003 and has been occurring'radionuclides often observed discontinued from the SSES REMP soil are thorium-228 and radium-226 in soil,- sample analysis library.

and beryllium-7 in fruits and vegetables.

The 2003 means for indicator and The results of the 2003 terrestrial control location sample thorium-228 pathway monitoring resemble those of activity were both 0.8 pCi/gram. The the past; Results for specific sample 2003 indicator mean is equal to the analyses of terrestrial pathway media ' corresponding 2002 mean. -The 2003 may be found in Tables 1-10 through control mean for thorium-228 is greater I-12 of Appendix I. A summary of the . than the corresponding 2002 mean. The 2003 terrestrial monitoring data may be "' indicator and control means are within located in Appendix G. Comparisons of the ranges of the corresponding means 2003 monitoring results with those of :;! for both the previous operational and past years may be found in Tables H 15.; preoperational periods, as applicable, of.

through H 19 of Appendix H. the SSES. Thorium-228 in soil is not the result of SSES operation because it Soil . - is naturally occurring.

The following gamma-emitting radionuclides are routinely measured in'. The 2003 means for indicator and soil at levels exceeding analysis MDCs: control location sample cesium-137 naturally occurring potassium-40, activity were 0.04 pCi/g and 0.07 pCi/g, radium-226, and thorium-228 and man- respectively. The 2003 indicator mean made cesium-137. The 2003 analysis is within the range of the corresponding 39 2003 Radiological Environmental Monitoring Report 2003 Radiological Environmental Monitoring Report

I I TerrestralPathway Monitorinj annual means for prior operational With the exception of the naturally years. The 2003 indicator mean is below occurring potassium-40, no gamma-the ranges of the corresponding means emitting radionuclides were measured for preoperational years. The 2003 in excess of analysis MDCs in 2003.

control mean is below the ranges of the- The 2003 means for indicator and corresponding annual means for both control location sample potassium40 prior operational and preoperational activity were 1383 pCi/liter and years. Cesium-137 levels in soil 1406 pCi/liter, respectively. The 2003 samples typically vary widely from indicator mean is less than the 2002 sample to sample. Levels of cesium-137 mean. The 2003 control mean is greater activity in 2003 samples varied by a than the corresponding 2002 mean. The factor of four over the entire range. 2003 indicator and control means for Cesium-137 in soil, although man- potassium40 activity are within the made, is not from the operation of the corresponding ranges of annual means SSES. It is residual fallout from for previous operational and previous atmospheric nuclear weapons preoperational years. The potassium-40 testing. activity in milk is not attributable to the SSES operation because it is naturally Milk occurring.

Iodine-131 has been chemically separated in milk samples and counted Fruitsand Vegetables routinely since 1977. Refer to Figure 13 Naturally occurring potassium-40 was which trends iodine-131 activity in milk the only gamma-emitting radionuclide for indicator and control locations measured in fruits and vegetables at an separately from 1977 through 2003. activity level in excess of analysis MDC Typically, iodine-131 is not reported at during 2003.

levels exceeding the MDCs for the analyses in any milk samples during a Due to excessive rainfall during the monitored year. The 2003 monitoring 2003 growing season, fruits and/or year was no exception; no iodine-131 vegetables were only sampled twice, above the analysis MDCs was observed both from indicator locations. The 2003 in either indicator or control samples. indicator location sample potassium-40 activity mean was 4.6 pCi/gram. The The preoperational years 1976, 1978, 2003 indicator mean is higher than its and 1980 were exceptional years in the corresponding 2002 mean. The 2003 sense that iodine-131 activity was indicator mean is above the range of the observed in excess of MDCs due to corresponding annual means for pre-fallout from atmospheric nuclear operational and prior operational years.

weapons testing. Iodine-13 1. activity Potassium-40 in fruits and vegetables is was also measured at levels exceeding not attributable to SSES operation MDCs in milk samples in 1986 in the because it is a naturally occurring vicinity of the SSES as a result of the radionuclide.

Chernobyl incident.

40 2003 Radiological Monitoring Report Environ-mental Monitoring Radiological Environmental Report 40

C C C FIGURE 13 - IODINE-131 ACTIVITY IN MILK 100 pCi/Litr CHINESE WEAPONS TEST 90 - A - 09112177 PRE- B - 03/14/78 80 - OPERATIONAL OPERATIONAL C - 10/15/80 70-60 -

50 -

40 - A CHERNOBYL 30 - 4/26/86 20 -

UNIT 2 10 - CRITICALIT B

0I I I

<,9< <,9^,959,9&^,,9 ,<,9o9

,9 99> 993 99t 98\ 999 Ad 0 Indicator El Control

Ground Water Monitoring - - . .

ae f i4? ,.

,WTER GROUNDD-iAMN1T0RIN.-

INTRODUCTION .. Scope -

Normal operation of the SSES does not Ground water in the SSES vicinity was involve the release of radioactive "-: sampled monthly at 2 indicator material to ground water directly or - locations (2S2 and 4S4) and one control indirectly through' the ground. As a - location (12F.3) during 2003.

result, there are no effluent monitoring, data to compare with REMP ground With the exception of location 4S4, .

water monitoring results. Ground water untreated ground water was sampled.

could conceivably become Untreated means that the water has not contaminated by leakage or spills from undergone any processing such as the plant br by the washout or, filtration, chlorination, or softening. At deposition of radioactive material that location 4S4, the SSES Training Center, might be airborne. If deposited on the well water actually is obtained from on-ground, precipitation/soil moisture site and piped to the Training Center could aid in'the movement of after treatment. This sampling is radioactive materials through the. -:- performed as a check to ensure thai ground to water that could conceivably water has not been radioactively, be pumped for drinking purposes. No".' contaminated. Sampling is performed at use of ground water for irrigation near the Training Center to facilitate the the SSES has been identified. sample collection process.

Because routine SSES operation releases primarily tritium and, to a Sample Preservation &

lesser extent, isotopes of xenon and Analysis krypton to the air, no radionuclides attributable to SSES operation are Ground water samples were analyzed expected to be observed in ground for the'activities of gamma-emitting water. Iodine and particulate releases to radionuclides'and tritium activity.

the air are negligible. Gaseous xenon Gamma spectromnetric'analyses of and krypton tend to remain airborne, ground*w'ater were begunfinm 1979 and deposition or washout of these would be tritium analyses in 1972, both prior to expected to be very minimal. Tritium SSES operation.: The use of nitric'acid would be the most likely radionuclide to as a preservative in ground water' reach the ground with precipitation and, samples was discontinued in 2003'(at if not lost to streams (surface water) by the request of the vendor laboratory).

runoff, move readily through the soil to the ground water.

2003 Radiological Environmental Monitoring Report 42

II Ground Water Monitoring Monitoring Results indicator and control means are lower than those for 2002. Both the 2003 -

indicator and control mean tritium Tritium activity levels in ground water activity levels are within the range of have typically been observed to be corresponding averages of annual lower than in surface water. A means for prior operational years. The noticeable decline occurred between 2003 indicator mean tritium activity is 1992 and 1993. Fewer measurements lower than the corresponding means for were above the analysis sensitivities in preoperational years. The 2003 control 1993 than in 1992. mean is within the range of corresponding means for preoperational Gamma-emitting radionuclides in years.

excess of MDCs have been found in only a few samples in all the years that Naturally occurring potassium-40 was these analyses have been performed.

measured in excess of analysis MDCs in The naturally occurring radionuclides 2 ground water samples during 2003.

potassium-40 and thorium-228 have No man-made gamma-emitting been measured above their MDCs radionuclides were determined to be at occasionally in ground water. levels in excess of analysis MDCs. No Potassium40 was reported in 1979, radioactivity contributions to ground 1981, 1985, 1991, 1992, 1993, and water from the SSES were identifiable 1997. Thorium-228 was found in 1985 in 2003.

and 1986. The man-made radionuclide cesium-137 has been detected only I occasionally since 1979. Its presence has always been attributed to residual fallout from previous atmospheric nuclear weapons tests.

The results of the 2003 REMP ground water surveillance resemble those of the past. Results for specific ground water sample analyses may be found in Table I-7 of Appendix I. A summary of the 2003 ground water monitoring data may be located in Appendix G.

Comparisons of 2003 monitoring results for tritium with those of past years may be found in Table H 20 of Appendix H.

During 2003, tritium was measured in excess of analysis MDCs on 4 occasions. The 2003 mean tritium activity levels for indicator and control monitoring locations were 54 pCi/liter and 17 pCi/liter, respectively. The 43 2003 Radiological Environ~mental Monitoring Report

References a:- :. .. ERE ES

1. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station, Environmental Report, Operating License Stage," May 1978.

2. Pennsylvania Power and Light Company, "Susquehanna Steam Electric Station, Final Safety Analysis Report".

3. United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, "Final Environmental Statement Related to the Operation of Susquehanna Steam Electric Station, Units I and 2," Docket Nos. 50-387 and 50-388, June 1981.

4. United States Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program," Radiological Assessment Branch Technical Position, November 1979, Revision 1.

5. National Council on Radiation Protection and Measurements, "Environmental Radiation Measurement," NCRP Report No. 50, Washington, D.C.,

December 27, 1976.

6. Oakley, D.C., "Natural Radiation Exposure in the United States," ORP/SID 72-1 Office of Radiation Programs, U.S. Environmental Protection Agency, Washington, D.C., June 1972.

7. Denham, D.H., Roberts, M.C., Novitsky, W.M., Testa, E.D., "Investigation of Elevated Cesium-137 Concentrations in Small Game in Luzeme County, Pennsylvania." Proceedings of Papers presented at Health Physics Society Tenth Midyear Topical Symposium, October 11-13, 1976, pgs. 271-279.

8. Currie L.A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements,"

NUREG/CR-4007, September 1984.

9. PPL, "Susquehanna Steam Electric Station, 2002 Annual Radiological Environmental Operating Report," April 2003.

10. PPL, "Susquehanna Steam Electric Station, Radioactive Effluent Release Report,"

Data Period: January - December 2003, April 2004.

11. Ecology III, "Susquehanna Steam Electric Station, 2003 Land Use Census,"

November 2003.

44 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report t 44

e S . . '. _

r- -; , I I ,. 1 -l APPENDIX A

~ 1-'J',

.. 3 . N I 1 -

i. .1 .: , -

A-i 2003 Radiological Environmental Monitoring Report Environmental Monitoring Report A-l

I I Appendix A REMP Sample Analyses

\J)

The following table summarizes the REMP sample analyses for which different laboratories were responsible during 2003. Note that TBE represents Teledyne Brown Engineering and E-LAB represents Framatome ANP.

SOURCE OF REMP DATA FOR MONITORING YEAR 2003 Sample Analysis Sample/Analysis Medium Type Frequency Data Period Lab Air Gross Beta Weekly All Year TBE Air I-131 Weekly All Year TBE Air Gamma Quarterly All year TBE Surface Gross Beta Monthly All Year TBE Water Drinking Gross Beta & Monthly All Year TBE Water Gross Alpha All Water Tritium Monthly All Year TBE Surface & Gamma Monthly All Year E-LAB Drinking Water Surface I-131 Monthly All Year E-LAB Water (LTAW)

Ground Gamma Monthly All Year E-LAB Water Surface & I-131 Bi/weekly All Year E-LAB Drinking Water .

Milk Gamma Monthly/ All Year E-LAB Semi-Monthly Milk I-131 Monthly/ All Year E-LAB Semi-Monthly Fish Gamma Semi-Annually Spring/Fall TBE Sediment Gamma Semi-Annually Spring/Fall TBE Ji A.2 Monitoring Report Environmental Monitoring 2003 Radiological Environmental Report t A-2

Appendix A SOURCE OF REMP DATA FOR MONITORING YEAR 2003 (continued)

Sample Analysis Sample/Analysis Medium Type Frequency Data Period Lab Fruits & Gamma In Season All Year TBE Vegetables (when irritgated)

Soil Gamma Annually All Year E-LAB I

Direct Radiation Monitoring There were no changes to direct radiation monitoring in 2003.

Air Monitoring There were no changes to the air monitoring program during 2003 Milk Monitoring There were no changes to the milk monitoring program in 2003.

Ground Water Monitoring There were no changes to the ground water monitoring program during 2003.

Fruits & Vegetables Because of the milk monitoring that is performed, there is no requirement to sample from gardens that have a potential for the deposition of activity by way of the airborne pathway. Fruits and vegetables are sampled from locations that irrigate with water taken from the Susquehanna River downstream from the SSES diffuser. The only change to the fruit and vegetable monitoring program in 2003 was the addition of Control Location 5S10. Location 5S10 is a farm irrigated with Susquehanna River water upstream of the SSES diffuser. Due to excessive rainfall, no irrigation was performed at Location 5S10 during 2003.

A-3 2003 Radiological 2003 Environmental Monitoring Report Radiological Environmental Monitoring Report

APPENDIX B W~ 203RM:;ts'-'e,.Z03t-EMONITORITNG SCEDUEE 't -rg' tiw.s.+'. s -'-'/";..-9o-'SAL NAL SIS) .; -

B-i 2003 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report B-1

IA Appendix B TABLE 1 (Page 1 of 2)

Annual Analytical Schedule for the PPL Susquehanna Steam Electric Station Radiological Environmental Monitoring Program - 2003 No. of Sample Analysis Media & Code Locations Freq.(a) Analyses Required Freg. (b)

Airborne 6 W Gross Beta (c) W Particulates Gamma Spectrometry QC Airborne Iodine 6 W 1-131 W Sediment 4 SA Gamma Spectrometry SA Fish 2 SA Gamma Spectrometry SA 1 A (on edible portion)

Surface Water (d) 4 MC, M, or Gross Beta M BWC 1-131 BW Gamma Spectroscopy M Tritium M Well (ground) 3 M Gamma Spectroscopy M Water Tritium M iJ Drinking Water (e) I MC, BWC Gross Alpha M Gross Beta M 1-131 BW Gamma Spectrometry M Tritium M Cow Milk 4() M, SM V) 1-131 SM, M Gamma Spectrometry SM, M Food Products 2 A Gamma Spectrometry A (Potatoes)

Soil 4 A Gamma Spectrometry A Direct Radiation 84 Q TLD Q Note: See footnotes at end of table.

J Monitoring Report B-2 2003 Radiological Environmental Monitoring Radiological Environmental Report B-2

Appendix B (a) W = weekly, BW = biweekly, BWC = biweekly composite, M = monthly, SM =

semi-monthly, Q = quarterly, QC =.quarterly composite, SA = semi-annually, A = annually, MC = monthly composite.

(b) Codes are the same as for sample frequency.

(c) If the gross beta activity were greater than 10 times the yearly mean of the control sample, gamma analysis would be performed on the individual filter. Gross beta analysis was performed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more following filter change to allow for radon and thoron daughter decay.

(d) Locations 6S6, 6S7, and 2S7 were checked at least weekly to ensure that the automatic composite samplers were operational. Time proportional sampling was performed at locations 6S6, 6S7 and 2S7 the entire year. Station 6S5 was grab sampled weekly. Individual composites of the weekly samples were made both monthly (MC) and biweekly (BWC) for analysis.

(e) Water from location 12H2 was retrieved weekly. Composite samples of the weekly collections at this location were made both monthly (MC) and biweekly (BWC) for analysis. Sampling at 12112 was performed using an automatic continuous sampler (ACS) that was operated in the time proportional mode.

(f) Locations 10DI, 10D2, IOGI, and 12B2 were sampled semi-monthly from April through October.

B-3 2003 Radiological Environmental Monitoring Report

APPENDIX C 2003.S.

.-. N.

JIEMP -MONITORINGLQ tCATION. DESCRIPTIONS

_ .. . 7 c-I 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report C-1

It Appendix C TABLE C 1 (Page 1 of 5)

J)

TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One Mile from the SSES(a) - See Figure 2 Location Distance Direction Description Code(b) (miles) 1S2 0.2 N Perimeter Fence 2S2 0.9 NNE Energy Information Center 2S3 0.2 NNE Perimeter Fence 3S2 0.5 NE SSES Backup Met Tower 3S3 0.9 NE ANSP Riverlands Garden 3S4 0.3 NE Perimeter Fence 4S3 0.2 ENE Post, West of SSES APF 4S6 0.7 ENE. Riverlands 5S4 0.8 E West of Environmental Laboratory 5S7 0.3 E Perimeter Fence 6S4 0.2 ESE Perimeter Fence (north) J 6S9 0.2 ESE Perimeter Fence (south) 7S6 0.2 SE Perimeter Fence 7S7 0.4 SE End of Kline's Road 8S2 0.2 SSE Perimeter Fence 9S2 0.2 S Security Fence 10Si 0.4 SSW Post - south of switching station 10S2 0.2 SSW Security Fence 10S3 0.6 SSW Confer's Lane - east of Confer's Lane, south of Towers Club 11S3 0.3 SW Security Fence 11S7 0.4 SW SSES Access Road Gate #50 12S1 0.4 WSW SSES West Building 3,

Monitoring Report C-2 Environmental Monitoring 2003 Radiological Environmental Report C-2

Apipendix C -- - . .. .- * . * - . .. I.

TABLE C 1 (Page 2 of 5)

TLD Location's'forthe SSES

,, . ~- ...,, Radiological R . Environmental no Monitoring o i Prograu - 2003 Less Than One Mile from the SSES(a) - S'Figure2 ' . . K ' . . .2 Location Distance* 'Direction "bDescrip'tion

-Code (b) (miles) . .

- .12S3 . ' 0.4' '.'WSW :Peimeter.Fence . .. .'-.

12S4 0.4 WSW PerimeterFence' 12S5 0.4 WSW PerimeterFence '

12S6 ' 0.4 WSW Penimeter Fence .'

A32 04W Priniet&.Fence .

13S4 '0.4 W Perimeter Fence 13S5 0.4 W Perimeter Fence ,

13S6 0.4 !W Former Laydown Area - west of Confer's Lane 14S5 0.5 WNW Beach'Gibve Road/Confer's Lanie; 14S6 0.7 WNW ;Beach Grove Road (pole) 15S5., -- -_0.4 NW TPerimeterFence ' '

16S1 0.3 NNW;-: PerimeterFence (east)  ! i;.

16S2 0.3 NNW Perimeter Fence (west) r 6A4 8A3 15A3 0.6 0.9 0.9 ESE -

SSE NW Restaurant (U.S. Route 11)

PPL Wetlands Sign (U. S. Route 11)

Hosler Residence I

16A2 - 0.8 . NNW -Benkinney Residence' .

From One to Five Miles froifi the 'SSESa SeeFigure 3-'S 12S7 '1.1- WSW' KisnrResidence .'

IBI 1.4 N -Minnglen Road  ;

2B3 1.3 NNE Leggett'&'Platt 2B4 1.4 NNE U.S. Route I1/Mingle Inn Road Intersection 5B3 1.6 E PPL Switchyard 7B2 1.5 SE Heller's Orchard Store 8B2 1.4 SSE Lawall Residence C-3 2003 Radiological Environmental Monitoring Report

I I Appendix C TABLE C 1 (Page 3 of 5)

TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 From One to Five Miles from the SSES(') - See Figure 3 Location Distance Direction Description Code (b) (miles)

'9B1 1.3 S 'Transmission Line -"east of Roude 11 10B2 2.0 SSW ,' -Algatt Re'sidence 10B3 1.7 SSW Castek Inc. '

10B4 1.4 S '- -W

' U. S. Route 11/River Road Intersection 12B4 1.7 ' ' WSW ;Berger Farm 13B1 1.3 IW Walker Run Creek (Tele. Pole #36) 14B3 1.3 WNW, Moskaluk Residence 15B1 .1.7: NW Country Estates Trailer Park 16B2 17, NNW Walton Power Line 1C2 2.0 SW MP Metals (U.S. Route 11) lDS 4.0 N 'Shickshinny/Mocanaqua Sewage Treatment Plt.

6D1 3.5 ESE St. Peters Church - Hobbie 8D3 4.0 ' SSE Mowry Residence' 9D4 3.6 S- Country Folk Store":

1ODI 3.0, SSW '--R. &C.RymanFarr 12D2 3.7 WSW Da'gostin Residence 14D1 3.6 WNW; Moore's Hill/Mingle Inn Roads Intersection 3E1 4.7 NE Webb Residence - Lilly Lake 4E2 4.7 ENE Ruckles HilVP6nd Hill Roads Intersection

.5E2 4.5 E Bloss Farm -

6E1 4.7 ESE St.'Jarmes Church Report Monitoring Report C-4 Environmental Monitoring 2003 Radiological Environmnental C-4

Appendix C . .

TABLE C 1 (Page 4 of 5)

TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 From One to Five Miles from the SSES(a) - See Figure 3 Location Distance Direction Description Code (b) '(miles) --m_,_-_ __,,

7E1 4.2 SE Harwood Transmission Line Pole #2 1 E1 4.7 SW Thomas Residence 12E1 4.7 WSW_ Berwick Hospital 13E4 4.1 W KesslerFarm Greater than Five Miles from the SSES(a) - See Figure 4_

2F1 5.9 NNE St. Adalberts Cemetery 8F2 8.5 SSE Huff Residence 12F2 5.2 WSW -Berwick Substation 15F1 5.4 NW Zawatski Farm 16F1 7.8 NNW HidlayResidence 3G4 17 NE Wilkes Barre Service Center 4G1, 14 ENE. Mountaintop - Crestwood Industrial Park 6G1. 13.5 ESE Freeland Substation 7G1 14 -SE Hazleton'PP&L Complex 7G2 12 SE Hazleton Cemetery - 14th Street 8G1 12 SSE PPLSFC -Humbolt'Industrial Park 12G1 15 WSW PPL Service Center, Bloomsburg 12G4 10 WSW Naus Residence Environmental Monitoring Report c-s C-5 2003 Radiological 2003 Radiological Environmental Monitoring Report

~IIt Appendix C TABLE C 1 (Page 5 of 5)

TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 a) All distances from the SSES to monitoring locations are measured from the standby gas treatment vent at 44200/N34117 (Pa. Grid System). The location codes are based on both distance and direction from the SSES. The letters in the location codes indicate if the monitoring locations are on site (within the site boundary) or, if they are not on site, the approximate distances of the locations from the SSES as described below:

S - on site E- 4-5 miles A- d mile F 10 miles B 2 miles G 20 miles C 3 miles H - >20 miles D 4 miles The numbers preceding the letters in the location codes provide the directions of the monitoring locations from the SSES by indicating the sectors in which they are located. A total of 16 sectors (numbered 1 through 16) equally divide an imaginary circle on a map of the SSES and its vicinity, with the SSES at the center of the circle. The middle of sector I is directed due north (N). Moving clockwise from sector 1, the sector immediately adjacent to sector 1 is sector 2, the middle of which is directed due north, northeast (NNE). Continuing to move clockwise, the sector numbers increase to 16, which is the north, northwest sector.

The numbers following the letters in the location codes are used to differentiate sampling locations found in the same sectors at approximately the same distances from the SSES.

2003 Radiological Environmental Monitoring Report C-6

Avvenir C - . I-TABLE C 2 (Page 1 of 4)

Sampling Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One Mile from the SSES(a) - See Figure 5

Location Code Distance Direction Description (miles)

q-'w3<>'$,'t54;~t;'~'t t3g-o 'SURACEtWATER,;,-  ;,

'-, -4,,<,-, ji'_-;

2S7 0.1_-_. NNE! Cooling Tower Blowdown Line 6S5 0.9 ESE Outfall 'Area 6S6 0 .8 ESE River Water Intake Line 6S7 0.4 ESE Cooling Tower Blowdown Line (alternate for 2S7)

LTAW ._-___. NE - ESE Lake Took-A-While (on site)

LTAW 77NE - ESE Lake Took-A-While (on site)

LTAW NE - ESE Lake Took-A-While (on site) j

'3S2 0.5 NE SSES Backup Meteorological Tower 12S1 0.4 WSW SSES West'Building

13S6'- - 0_4 .. W'. ' 'Forrher Laydown Area, West'of Confers Lane

-B. \ -a . . e. { .~

4. 4* 4 , *

v. r .. . .. 4. ..4S 4 . .* 4 i 4 4 , . * ,.4. 4 . .. -. 4 . ......................

sttE'>*

r,-

3S2 '0.5 I NE .'SSES Backup Meteorological Tower 12S1 ' ' 0.4  ; WSW SSES West Building

13S6 0.4- -W ,Formner Laydown Area, West of Confers Lan'e -

C-7 2003 Radiological Environmental Monitoring Report

I I Appendix C TABLE C 2 .j)

(Page 2 of 4)

Sampling Locations for the SSES Radiological Environmental Monitoring Program - 2003 Less Than One Mile from the SSES(a) - See Figure 5 Location Code 1Distance (miles)

Direction Description 22 J 0.9 NNE. SSES Energy Information Center 4S4___ 0.5 ENE SSES Learning Center From One to Five Miles From the SSES - See Figure 6 IND 0.9 - 1.4, IESE to Below the SSES Discharge Diffuser L -- -. , I, -, , 1, , "! , z- " .- , , ! -1 , z , ,. . .- , ,I i-., I z , ,, 11,

, . -Z I, t.

, )I '. '. -, , , I, I- 4, , , I ..-., . T

, __., , , i. , -

-'j;I,..." .". ;,- -, , --, I , , , , .: , -'. i - - - . .:. - - .

1.2 NNE -IGoudIln 2B1. E I Rell 12E1 4.7 1WSW lBerwickHospital I 3

______ 30.0 SSW. jR.&C.RyinanFanm 10D32 '3.1 SSW S_ Rayrhond Ryman Farm22n.

-I , VIk ;

,"f-:

. r, . , -,

- 11 ,

, I ", -!

- .1-L - -RUITS/VEGETABLES il' z -  !

z: . ) , , 0 .,

-:,", "i 1'.

I 1ID2 1 3.5 1- SW ILupini Field -U.S. Route 93.

ji Report C-S Radiological Environmental 2003 Radiological Environmental Monitoring Monitoring Report C-8

Appendix C TABLE C 2 (Page 3 of 4)

Sampling Locations for the SSES Radiological Environmental Monitoring Program - 2003 Greater than Five Miles from the SSES() - See Figure 7 Location Distance Direction Description Code (miles) ._ __ _ _-,_ _

.. .'DPNKNG

. WATER:--

12H2 26 WSW Danville Water Co. (treated) 2H 30 T NNE Near Falls, Pa.

, - . rSEDI1,IEN1~c).'~>-,-

12F 6.9 I- WSW-. OldBerwickTestTrack u '

6G1 13.5 ESE Freeland Substation 8G1 12SSE PPL SFC - Humbolt Industrial Park 8G1 12 SSE PPL SFC - Humbolt Industrial Park 1OGI -14 SSW z-DavisFarm- -

.>...-<> ,\. +-. .4M^RUITSNGETABLES:.-.: .,

11F2 J -;_

5.5

-T l

,i~x SWL.J Chapin (Drake) Field RUND.WATER 12F3 l 5.2 - WSW I Berwick Water Company 3 R doo i a n io m na o ioi g R p r C-90 2003 Radiological Environmental Monitoring Report C-9

I I Appendix C TABLE C 2 J (Page 4 of 4)

Sampling Locations for the SSES Radiological Environmental Monitoring Program - 2003 a) All distances from the SSES to monitoring locations are measured from the standby gas treatment vent at 44200/N34117 (Pa. Grid System. The location codes are based on both distance and direction from the SSES. The letters in the location codes indicate if the monitoring locations are on site (within the site boundary) or, if they are not on site, the approximate distances of the locations from the SSES as described below:

S - on site E 5 miles A- <1 mile F 10 miles B 2 miles G 20 miles C 3 miles H- >20 miles D 4 miles The numbers preceding the letters in the location codes provide the directions of the monitoring locations from the SSES by indicating the sectors in which they are located. A total of 16 sectors (numbered 1 through 16) equally divide an imaginary circle on a map of the SSES and its vicinity, with the SSES at the center of the circle. The middle of sector 1 is directed due north (N). Moving clockwise from sector 1, the sector immediately adjacent to sector 1 is sector 2, the middle of which is directed due north, northeast (NNE). Continuing to move clockwise, the sector numbers increase to 16, which is the north, northwest sector.

The numbers following the letters in the location codes are used to differentiate sampling locations found in the same sectors at approximately the same distances from the SSES.

b) No actual location is indicated since fish are sampled over an area which extends through 3 sectors (5, 6, 7) near the outfall area.

c) No permanent locations exist; samples are taken based on availability.

Consequently, it is not necessary to assign a number following the letter in the location code.

Monitoring Report Environmental Monitoring Radiological Environmental c-iD 2003 Radiological 2003 Report C-10

• . -!J APPENDIX.

i- ,

. 'I I I . I .. . i

';a I . I'  ;  ; ' i II

. . . .i I  ; I .1 i2003 Radiological Environmental Monitoring Report -: . . i II . D-1

II Appendix D 2003 LAND USE CENSUS RESULTS The SSES Technical Requirements require that a census be conducted annually during the growing season to determine the location of the nearest milk animal, residence and garden greater than 50 m2 (approx. 500 ft2 ) producing broad leaf vegetation within a distance of 8 km (approx. 5 miles) in each of the 16 meteorological sectors surrounding the SSES. To comply with this requirement, a land-use census was conducted for the SSES during 2003.

A comparison of the 2002 and 2003 Land Use Census results for the SSES indicates the changes listed in the tables below. Tables 1 display the changes in the nearest gardens and Table 2 displays the changes in sampling of irrigated foods from 2002 to 2003.

Overall, the changes since the 2002 Land Use Census were minimal. In 2003, the nearest garden in sector 5 was revised from 1.4 miles to 1.8 miles from the SSES.

There was no garden identified in sector 14 which met the requirements for sampling in 2003. The farm identified in 2002 (P. Moskaluk, Jr.) in sector 14, did not plant a garden in 2003.

TABLE 1 CHANGE FROM 2002 TO 2003 IN NEAREST GARDENS AS DETERMINED BY THE 2003 LAND USE CENSUS 2002 2003 Distance Distance Sector/ Owner's from SSES Owner's from SSES Direction Name (mi.) Name (mi.)

5/E KozlowskilWitts 1.4 W. Daily 1.8 14/WNW P. Moskaluk, Jr. 1.3 N/A N/A These changes in gardens had no impact on the intended sampling of fruits and vegetables during 2003. Because of the milk monitoring that is performed, there is no requirement to sample from gardens that have a potential for the deposition of activity by way of the airborne pathway.

D.2

-2003 Radiological

-2003 Monitoring Report Environmental Monitoring Radiological Environmental Report D-2

Appendix D______

Irrigated fruits and vegetables were monitored at 2 indicator locations during 2003. The only crop irrigated in 2003 was potatoes. No other fields within 10 miles downriver of the SSES were irrigated in 2003, because wet weather prevailed much of the spring and summer.

TABLE 2 CHANGE FROM 2002 TO 2003 IN VEGETABLES IRRIGATED WITH SUSQUEHANNA RIVER WATER FROM DOWNSTREAM OF THE SSES DISCHARGE DURING 2003 -

-Distance from SSES Sector/Direction Owner. (mi.) 2002 2003 I1F2/SW Chapin (Drake) Farm 5.5 N/A Potatoes 1 ID2/SW Lupini Farm (Rt. 93) 3.5 N/A' Potatoes

- o .

.. .. . ..  ? , .

I . . i.: .

Environmental Monitoring Report

~D-3 D3 2003 Radiological 2003 Radiological Environmental Monitoring Report

lI Appendix D TABLE 3 Nearest residence, garden, and dairy animal in each of the 16 meteorological sectors within a 5-mile radius of the Susquehanna Steam Electric Station, 2003.

NEAREST NEAREST NEAREST SECTOR DIRECTION RESIDENCE GARDEN DAIRY ANIMAL 1 N 1.3 mi 3.2mi >5.0 mi 2 NNE 1.0 mi 2.3 mi >5.0 mi 3 NE 0.9 mi 2.7 mi >5.0 mi 4 ENE 2.1 mi 2.4 mi a,c,d,fl >5.0 mi 5 E 1.4 mi ac 1.8 mi 4.5 mi g 6 ESE 0.5 mi 2.5 mi 2.7 mi 7 SE 0.5 mi 0.6 mi >5.0 mi 8 SSE 0.6 mi 1.5 mi >5.0 mi 9 S 1.0 mi 1.1 mi >5.0 mi 10 SSW 0.9mi 1.2 mi 3.0 mi a,b,c,d.e,g 11 SW 1.5 mi 1.9 mi >5.0 mi 12 WSW 1.1mi 1.1 mi 1.7 mi g'i 13 W 1.2 mi 1.2 mi 5.0 mij 14 WNW 0.8 mi >5.0 mi >5.0 mi 15 NW 0.8 mi 1.8 mi ' >5.0 mi 16 NNW 0.6 mi 4.0 mi 4.2mi a Chickens raised for consumption at this location.

b Ducks raised for consumption at this location.

c Eggs consumed from chickens at this location.

d Geese raised for consumption at this location.

Pigs raised for consumption at this location.

f Turkeys raised for consumption at this location.

g Fruits/vegetables raised for consumption at this location.

h Rabbits raised for consumption at this location.*

Beef cattle raised for consumption at this location.

Goats raised for consumption at this location.*

k Pheasants raised for consumption at this location.*

1 Sheep raised for consumption at this location.

• No locations were identified as raising rabbits, goats, and pheasants during 2003.

Report D-4 2003 Radiological Environmental Monitoring Radiological Environmental Monitoring Report D-4

II I. . , 1 i, .,

APPENDIX E A' .^ 1 YDSrI.TION.OF. SSES REMI-

.. .^

<,t,'4'^ AN:-,lY.TICAL-. METHQDS .;-

i. I..;.

El E-1 2003 Radiological Environmental Monitoring Report -

I '

Appendix E TLD MEASUREMENTS The PPL dosimetry system used for monitoring ambient radiation levels in the environment consists of Panasonic 710A readers and Panasonic UD-814 TLDs. The UD-814 TLD badges each contain four elements. Elements 2, 3, and 4 in each badge are made of calcium sulfate with 800 mg/cm 2 of filtering and element I is composed of lithium tetraborate with filtering of 25 mg/cm2 . Only the calcium sulfate elements are normally used for environmental measurements because of their higher light output per unit of radiation exposure relative to the lithium tetraborate and, consequently, greater sensitivity for the detection and measurement of radiation.

Note: Element I would be of value in the event of an unusually large release of noble gases, especially xenon, that would produce relatively low-energy X-ray or gamma emissions. This is because the lithium tetraborate does not over-respond to such low-energy emissions as does the calcium sulfate.

The TLD element manufacturers' attempt to make each element as similar as possible to each of the other elements in each batch that is produced. Nevertheless, each element ends up somewhat different in its response to radiation. In order to minimize the effect of these inherent differences when comparing actual monitoring results for different elements, Element Correction Factors (ECFs) are determined for each element. The ECFs are used to effectively normalize the readings of the field elements placed at particular monitoring locations for given monitoring periods to the average of the readings that would be expected if so-called reference elements were to be placed simultaneously at those individual locations. Reference elements are elements that have been demonstrated to display superior measurement performance.

The selection process for reference elements involves repeatedly irradiating a large set of elements, processing them, calculating the mean response for each set of elements, and evaluating the deviation of each individual element response from the mean response. After this process has been repeated at least several times, the elements with the least variability in their responses and with mean responses nearest to the mean response of the entire population of elements are chosen as reference elements.

To determine ECFs for individual field elements, the elements are first exposed to known amounts of radiation (100 mR) and processed, a minimum of three times each.

Each element reading is then divided by the mean of the readings obtained from reference elements (typically 30 to 35) that were exposed to the same amounts of radiation as the elements for which the ECFs are being determined and that were processed at the same time as these elements. The mean quotient (ratio) is then calculated for each element by summing the quotients obtained for each processing and then dividing by the total number of the processings performed.

2003 Radiological Environmental Monitoring Report E-2

Appendir E The following equation shows how ECFs are calculated:

where E, an uncorrected exposure reading for the 'element.

n =the total number of individual element exposures averaged.

E,,f = the mean of the ECF-corrected exposure readings of the reference elements.

Irradiated control TIDs are processed (read) with the batches of TLDs from the field to provide both processing calibration information and quality control. Field control TIDs, which accompany the field TLDs when they are being taken to their monitoring locations and subsequently retrieved from these locations, and cave control TIDs, which are stored with the field TLDs for the periods between annealing and field distribution and between retrieval'from the field'and processing, are also read with the field TLDs to provide checks on the exposures that the field TLDs might receive on their way to and from their monitoring locations and while in storage, respectively.

The raw data from the field TLD processings is Run Calibration Factor (RCF) corrected using the irradiated control TLD data. The irradiated control TIDs are exposed to 100 mR from a cesium-137 source at the Battelle Lab in Richland WA. The irradiated TLDs are accompanied enroute to and from the Battelle Lab by transit control TIDs. An estimate of the exposures received by the irradiated TLDs in-transit is obtained by processing the transit controls and determining the transit control mean by the following equation:

in  :

where E= the mean of the elementally corrected exposure readings of all the transit control elements.

E= the uncorrected exposure reading of each individual transit control element;'

E-3 - 2003 Radiological Environmental Monitoring Report

I I Appendix E ECFj = the elemental correction factor of each individual transit control element.

n= the total number of individual element exposures averaged.

The mean of the transit control exposures is then subtracted from each of the elementally corrected exposures of the irradiated elements to obtain the net exposures for each element resulting from the irradiation. The mean of these net exposures is then divided by the known exposure (100 mR) from the irradiation to determine the RCF.

The following equation describes the calculations performed:

RCF=

KEic where RCF = the run correction factor for an individual field monitoring element.

E= the exposure reading of each individual irradiated control element.

ECF = the elemental correction factor of each individual irradiated control element.

n= the total number of individual element exposures averaged.

KE,0 = the known exposure for each of the irradiated control elements.

Exposure readings for individual field monitoring elements are corrected using the appropriate mean transit exposure and the elemental and run correction factors as follows:

CE = UEX-ETC ECFX X RCFx where CET = the corrected exposure reading for field monitoring element x.

UEX = the uncorrected exposure reading for field monitoring element x.

2003 Radiological Environmental Monitoring Report E4

Appendbc E -- -

ECF! = the elemental correction factor for field monitoring element x.

ETC = mean transit exposure RCFX = the run correction factor for field monitoring element x.

NOTE: The mean transit exposure is determined from the elements of the TLDs that accompany the field TLDs during transportation to and from the field locations.'

The exposure representing each environmental monitoring' locatiohn- nd monitoring period is normally the mean of the corrected exposure readings for a total of six calcium sulfate elements, three from each of two different TLDs at ea'ch location. The following equation shows the calculation of this exposure:

n where E= the mean of the corrected exposure readings for a given monitoring location and period.

CE, = the corrected exposure reading of an individual element for a given monitoring location and period.

n = the total number of individual element exposures averaged.

The mean of the corrected exposure readings for a given location and period may be calculated using less than the six calcium sulfate elements if the reading from one of the elements is more than two standard deviations' from' the' mean. In this situation, the mean would be recalculated with only five element readings, excluding the element reading that was more than two standard deviations' from the originally calculated mean.

The mean may be automatically calcuiated by the dosimetry software with as few as four element readings before the data'-is flagged. The following' calculation is used to determine the standard deviation of the 'corrected elemental exposure readings:

, , . \ ,C. .

S..

n-I where 2003 Radiological Environmental Monitoring Report E-5 E-S ' - 2003 Radiological Environmental Monitoring Report

I -

Appendix E S= the standard deviation of the corrected exposure readings from a given monitoring location and period for (n-I) degrees of freedom.

E= the mean of the corrected exposure readings for a given monitoring location and period.

CE, = the corrected exposure reading of an individual element for a given monitoring location and period.

n = the total number of individual element exposures averaged.

The standard monitoring period for the reporting of TLD exposures is the calendar quarter. The calendar quarter is defined as a period of 91.25 days. The actual monitoring periods for TLDs in the field are often for times other than 91.25 days. The means of the corrected exposures for these nonstandard periods must be normalized to the standard calendar quarter. The following equation shows how the normalization is performed:

NE-= Ex91.25 MP where NE = mean corrected exposure normalized to a standard calendar quarter of 91.25 days.

Ec = the mean of the corrected exposure readings for a given monitoring location and period.

MP = the actual TLD monitoring period (time in the field) in days.

TLD DATA INTERPRETATION Pre-operational and operational data are compared for the purpose of determining whether or not TLD data may indicate a dose contribution from SSES operation.

Between 1979 and 1994, both TLD types and TLD processing systems changed more than once. In order to avoid possible confusion in data interpretation as a result of these changes, ratios of TLD doses for specific indicator locations to the average of the TLD doses for control locations from operational periods compared to their counterparts from the preoperational period. Comparison of these ratios is performed in lieu of comparing the actual operational and preoperational doses. The following equation shows how these ratios are calculated:

r, =di, dc 2003 Radiological Environmental Monitoring Report E-6

AppendixE where ri = the indicator-to-control-average dose ratio for a particular location and calendar quarter, di = the quarterly dose for a particular indicator location, and dc = the average quarterly dose for certain control locations.

Note:

The ri are the quotients of the'indicator doses to the average doses of the following control locations: 3G4, 4G 1 7G1, 12G1, and 12G4. Only these control locations are used because they were the only ones existing during the preoperational period.

Operational r, for indicator locations that do not have preoperational histories are compared with the range of preoperational control-to-co'ntrol-average'dose ratios (rc) experienced at control locations. 'It canfbe'safely assumed that the preoperational range of these rr at control locations are the result of variations in the levels of background radiation at those locations. Any operational indicator ri for an indicator location without a preoperational history that is above the uppermost range expected at control locations based on preoperational data is assumed to suggest a possible contribution from the SSES operation. The following equation shows how rc is calculated:

r, = d- dc where rc - is the control-to-control-average dose ratio for a particular location and calendar quarter, dc - is the quarterly dose for a particular control location, and dc - is the average quarterly dose for certain control locations.

E-7 E2003 Radiological Environmental Monitoring Report

Appendix E DSSES=(ri-1.22)xDcAxOF where DSSES = the dose attributable to SSES fuel cycle operations, r = the indicator-to-control average ratio for a particular location and calendar quarter, 1.22 = the highest expected rc for control locations due to variations in natural radiation levels based on preoperational data. Refer to location 12G4 in Attachment 1.

DCA = the average quarterly dose for control locations.

OF = the occupancy factor.

Each year, the SSES attributable doses calculated for each calendar quarter are surnmed for all calendar quarters at each location to obtain annual doses by location.

E-I0 2003 Environmental Monitoring 2003 Radiological Environmental Report Monitoring Report t E-10

Appendix E DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA ACTIVITY TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Aliquots of water samples are evaporated to near dryness in beakers. The remaining volumes (approximately five milliliters or less) are transferred to stainless steel planchets and evaporated to dryness.

All planchets are counted in low background gas-flow proportional counters.

Calculations of both gross alpha and beta activities include the use of empirical self-absorption correction curves to account for changes in effective counting efficiency occurring as a result of changes in the masses of residue being counted.

Weekly air particulate-filters are placed into'planchets as received and counted in low background gas-flow proportional counters. No corrections are made for beta self-absorption when calculating the gross beta activities of the air particulate filters because of the impracticality of weighing the deposit and because the penetration depth of the deposit into the filter is unknown.

CALCULATION OF THE SAMPLE ACTIVITY rc 1 + Rb pCi [ItC + 2 unit volume or mass 2.22 (V)(E) 2.22 (V) (E) net activity random uncertainty E-1 1 2003 Radiological Environmental Monitoring Report

I I Appendir E where: C = total counts for sample t = count time for sample/background (minutes)

Rb = background count rate of counter (cpm) 2.22 = dpm pCi V(M) = volume or mass of sample analyzed E = efficiency of the counter (cpm/dpm) 4.66 = sigma level Calculation of the Minimum Detectable Concentration (MDC) Value 4.66f4 MDC2= I(

2.22 (V) (E)

E-1 2 2003 Radiological Environmental Monitoring Report Environmental Monitoring Report E-12

AppendixLE RADIOCHEMICAL . -

DETERMINATION

.1 I . .

OF 1-131 IN CHARCOAL AND VEGETATION SAMPLES i,

• TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Radioiodine is separated from the sample matrix to periodate solution.

Charcoal filters are opened and the exposed'charcoal is emptied into a refluxing flask, iodide carrier is added, and the mixture is refluxed in sodium hydroxide to remove the iodine absorbed on the charcoal and bringing it into' solution. The resulting iodide solution is oxidized with hypochlorite to periodate.

Vegetation samples are chopped, 'iodide 'carier added, the mixture evaporated to dryness, leached with sodium hydroxide, and fused in a muffle furnace. The resulting melt is dissolved in distilled water and filtered. The resulting iodide solution is oxidized with hypochlorite to periodate.

The periodate solution is reduced to 'io'dine with hydroxylamine hydrochloride, and extracted into toluene as free iodine.. The,iodine is back extracted into distilled water through reduction to iodide with aqueous sodium bisulfite and is ultimately precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.

The dried precipitate is beta counted on a low-level counter.

CALCULATION OF THE SAMPLE ACTIVITY C-Bb 2 A I[ ] +/- 2 +

2.22(V)(y)(DF)(E) 2.22(V)(y)(DF)(E) net activity random uncertainty where: A = activity concentration (pCi/1)

C = total counts from sample t = counting time for sample (min)

Rb = background count rate of counter (cpm) 2.22 = dnm pci E-13 2003 Radiological Environmental Monitoring Report

I I Appendix E V = volume of sample analyzed (liters) y = chemical yield of the mount or sample counted DF = decay factor from the collection (milk/vegetables) or midpoint of compositing period (water/charcoal cartridges) to the mid-count time E = efficiency of the counter for the I-l 31 betas.

4.66 = sigma level Note: Efficiency is determined by counting an 1-131 standard.

Calculation of the MDC 4.66J4\i 2.22(V)(y)(DF)(E)

Report Monitoring Report E-1 4 Environmental Monitoring 2003 Radiological Environmental E-14

Appendix E RADIOCHEMICAL DETERMINATION OF 1-131 IN MILK AND WATER SAMPLES FRAMATOME ANP ENVIRONMENTAL LABORATORY L: - -.- <.._....

First, iodide carrier is added to either a two-kilogram sample aliquot of milk or water.

For water, the next step is to add sodium hypochlorite, followed by hydroxylamine hydrochoride, and finally sodium bisulfite to convert all of the iodine in the sample to iodide. After sufficient time for equilibration of the stable iodide carrier, anion exchange resin is added to the sample to extract the iodide from the sample aliquot. The iodide ion is subsequently removed from the resin using sodium hypochliorite. It is then reduced to elemental iodine and transferred from the aqueous phase to the toluene. The iodine is then reduced to iodide using sodium bisulfite and back extracted into the aqueous phase. Once in the aqueous phase, the iodide is precipitated as cuprous iodide following the addition of cuprous chloride.-::

Another aliquot of sample may be used, if activity is detected in the sample, to determine the original stable iodide content of the sample using a specific-ion electrode.

This information would then be used to correct the chemical yield determined from the mass of the dried precipitate.

The dried precipitate is then counted using a beta/gamma coincidence counter.

CALCULATION OF SAMPLE ACTIVITY G t G A it-B 0' t t2  ; t A)e~*2.22 *V *y *D *E -ei e)*2.22 *V *y *D *E Where:

A = activity concentration (pCi/1)

G = gross count at the end of the sample counting interval (t) i= sample counting interval B = background count rate (cpm)

X = decay constant for I-13 1 (5.987E-5 min')

2.22 = dpm/pCi V = volume of sample (1) y = chemical yield (recovery) of the iodide E-15 2003 Radiological Environmental Monitoring Report

Appendix E D = decay factor (eAT) where Xis the decay constant for I-13 1 and T is the decay period from sample collection (milk) or the mid-point of the sample compositing period (water) to the mid-point of the counting interval E = is the I-131 beta/gamma counting efficiency (cpm/dpm)

CALCULATION OF MDC 4.66 *a *t *t MDC (ie )*2.22 *V *y *D *E Where:

ADC = minimum detectable activity concentration (pCi/1)

Report E-1 6 2003 Radiological Environmental Monitoring Radiological Environmental Monitoring Report t E-16

Appendix E DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION COUNTING TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES Ten' milliliters of water is mixed with" liquid scintillation material and counted for typically 200 minutes to determine its activity.

CALCULATION OF THE SAMPLE ACTIVITY FOR TRITIUM

[C -~

RbR

,pCi [ ] + 2 t 2.22(V)(E) -2.22(V)(E) net activity random uncertainty where: C = total counts from sample t = count time for sample (minutes)

Rb background count rate of counter (cpm) 2.22 = dpm pCi V = initial volume before enrichment (liters)

E = efficiency of the counter for tritium (cpm/dpm)

Calculation of the MDC

--Rb-MDC

- -466 i 'ii (2.22)(V)(E)

E-17 --- 2003 Radiological Environmental Monitoring Report

l -

Appendix E Calculation of SSES Attributable Direct Radiation Dose based on Onsite Indicator TLD Measurements For TLD locations where direct radiation dose contributions from the SSES are indicated, these calendar quarter doses are estimated based on the amounts referred to as the excess ratios. Excess ratio for each location's ri for a particular calendar quarter is the amount by which that r1 exceeds the high end of its range of preoperational r1 . The excess ratio at a specific location is multiplied times both the average dose for control locations measured during that calendar quarter and an occupancy factor based on a reasonable estimate of the portion of the calendar quarter that a MEMBER OF THE PUBLIC might spend near an onsite TLD location. The following is a table of occupancy factors that are used:

Environmental TLD Monitoring Locations Occupancy Factors Onsite 4.56E-4 Offsite (other than Private Residences) 3.65E-3 Private Residences I The following equation is used for obtaining direct radiation doses attributable to the SSES at indicator TLD locations when preoperational data exists for those locations:

DsSES=(ri-ru)xDCAXOF where DSSES = the dose attributable to SSES fuel cycle operations, r; = the indicator-to-control average ratio for a particular location and calendar quarter, ru = the indicator-to-control average ratio corresponding to the upper end of the 95% confidence range for a particular location for the preoperational period, and DCA = the average quarterly dose for control locations.

OF = the occupancy factor.

The equation below is used for obtaining direct radiation doses attributable to the SSES at indicator locations when preoperational data does not exist for those locations:

2003 Radiological Environmental Monitoring Report E-9 2003 Radiological Environmental Monitoring Report

Ap endix E Flagging Environmental TLD Measurements for Possible Non-Natural Dose Contributions Confidence ranges, within which 95% of'environmental TLD doses resulting from natural, background radiation are expected to be; have been derived for each location with a preoperational history by multiplyingthe' standard deviation (S) of the ri for the location by the appropriate t score (t) based on the applicable degrees of freedom for each location. (Degrees of freedom (df) are .equal to the number of ratios that were averaged less one.) The product of the t score and the standard deviation (tS) was then subtracted from the mean (x ) to determine the lower end of the 95% confidence range (R) and added to the mean to obtain the upper end of the range (R) as indicated by the following equation:

R= ti ('J The following t scores were used in the range calculations:

tSCORES,

df to.o5 1 . 12.706 2 4.303 3 '3.182 4 2.776 5 2.571 6 2.447 7 2.365 For indicator locations with no preoperational history, TLD results are flagged for potential non-natural dose contributions to TLD measurements based on comparisons to the maximum expected variation. in control-to-control-average dose ratios (re) for control locations. The expected ranges of rc for each control location for each calendar quarter during the 1980-81 preoperational period have been calculated. The highest expected r, for all the preoperational control locations is 1.22.

Ratios for indicator locations greater than 1.22 are flagged for possible SSES direct radiation dose contributions.

E-8 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report E-8

I n Appendix E DETERMINATION OF GAMMA EMITTING RADIOISOTOPES TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES &

FRAMATOME ANP ENVIRONMENTAL LABORATORY Gamma emitting radionuclides are determined with the use of a lithium-drifted germanium (Ge(Li)) and high purity germanium detectors with high resolution spectrometry in specific media, such as, air particulate filters, charcoal filters, milk, water, vegetation, soil/sediments, biological media, etc. Each sample is prepared and counted in standard geometries such as one liter or four liter wrap-around Marinelli containers, 300 ml or 150 ml bottles, two-inch filter paper source geometries, etc.

The analysis of each sample consists of calculating the specific activities of all detected radionuclides as well as the minimum detectable concentration for a standard list of nuclides. The germanium detection systems are calibrated for each standard geometry using certified radionuclide standards traceable to the National Institute of Standards and Technology.

CALCULATION OF THE SAMPLE ACTIVITY Net pCi/ vol or mass = [C-B] + 2V5C7i 2.22(V)(E)(GA)DF)(t) 2.22(V)(E)(GA)(DF)(t) net activity random uncertainty where: C = area, in counts, of a spectral region containing a gamma emission of the nuclide of interest Note (1): If the detector exhibits a peak in this region when counting a blank, the counts from that peak are subtracted from C before using the above equation.

Note (2): If no peaks are exhibited, the counts in the channels where the predominant peaks for gammas from selected radionuclides would be expected are summed for C and used in the calculation of "net" activity.

B = background counts in the region of interest, calculated by fitting a straight line across the region connecting the two adjacent regions.

Monitoring Report E-18 Environmental Monitoring 2003 Radiological Environmental Report E-18

Appendix E Note: If no peak exists in a region from which a "net" activity is being calculated, background is represented by the average of the counts in one channel from each side of that region.

t = counting interval of sample (minutes) 2.22 dpm/pCi V = volume or mass of sample analyzed E = efficiency of counter at the energy region of interest GA = gamma abundance of the nuclide at the gamma emission energy under consideration DF = decay factor from sample collection time or midpoint of sample collection (air I-13 1) to midpoint of the counting interval Calculation of the MDC MDC( pCi/vol or mass - 4.66 JB 2.22(V)(E)(GA)(DF)(t)

The width of the region around the energy where an emission is expected is calculated differently for MDCs than it is for the width of a peak that is actually identified.

Consequently, the value of B used in the two equations may differ.

Environmental Monitoring Report E-19 2003 Radiological 2003 Radiological Environmental Monitoring Report

,APPENDIX F i'2003'.EM EFTIQ0 S-.T. "H'.-SS Et. E -'!

.UREQIREMENITRS SAMPLE

ISSENSITIVITES 11 .- I I

• .;i '  :.! ;

I ,,I.~, -,;,I  :, .-'. . -

. z., . I I . . . ........

F-i 2003 Radiological Environmental Monitoring Report

,F -2003 Radiological Environmental Monitoring Report

I I Appendix F Exceptions to the SSES Technical Requirements occurred in the monitoring of the following media: drinking water, surface water, air, and ambient radiation monitoring.

These exceptions involved sample collections that did not take place for the required periods due to sampling equipment problems and various environmental conditions (rain) that impacted sample collection or analysis.

These exceptions are discussed in this appendix and specifically documented in the tables of Appendix I.

Drinking Water Sampling at the Danville Municipal Water Facility, monitoring location 12H2, proceeded flawlessly during most of 2003, with only one exception. The only exception during 2003 occurred when the sample collectors incorrectly mixed the drinking water sample for week 1 of the April monthly composite period with the week 1 sample of the April monthly composite period from Surface Water monitoring location 0S5. The April monthly composite for monitoring location 12H2 sent for analysis contained only weeks 24 for April 2003.

There were no malfunctions of the ACS at monitoring location 12H2 during 2003.

Sampling at this location was routine (as expected) for 100% of the year.

Surface Water Monitoring at. control location 6S6,. the SSES River Water Intake Structure, and indicator location 2S7 or its alternate location 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) to the Susquehanna River, are the only environmental surveillance's of surface water required by SSES Technical Specifications. The other SSES REMP routine indicator surface water monitoring location on the Susquehanna River, which is downstream from the SSES discharge to the river, and the monitoring location at LTAW are not required. They have been monitored to provide added assurance that the environment is not being compromised by radiological releases resulting from the SSES operation.

Sampling at locations 6S6 and 2S7 or 6S7 is required to be performed by the collection of aliquots at time intervals that are small compared to the compositing period.

Composite samples from these locations are required to be analyzed monthly and are expected to be representative of the streams from which they are collected.

Problems occurred in 2003 with the automatic composite sampler (ACS) at sampling location 6S6 during portions of the following collection periods: March 17, through March 24, 2003 and June 23, through June 26, 2003. Sample collectors discovered low flow through the ACS due to rising river level causing debris and silt build-up on intake screens. Initially, the ACS sample flow rate was adjusted to insure sufficient volume was collected. Preventive maintenance was performed on the ACS (cleaned lines) and the sample flow rates were reset to 1.5 gpm.

2003 Radiological Environmental Monitoring Report F-2

... - Appendix F The ACS at monitoring location 6S6 operated routinely. (as expected) for approximately 97% of 2003. No malfunctions of the ACS at monitoring location 6S6 required the collection of grab samples during 2003.'.,'

Surface water samples could not be taken 'at ACS location 2S7 from October 3 at 1011 through October 4 at 0541 due to power failure. Power was restored to the sampler on October 4, 2003 at 0541. There was adequate volume for sample requirements. The ACS at monitoring location 2S7 operated routinely (as expected) for approximately 99% of 2003.

Air Reasons for exceptions to REMP air sampling during 2003 included the following: loss of electrical power to air sampling stations and air sample equipment problems (pump malfunctions).

Electrical power to the air sampling stations at monitoring locations 3S2, 13S6, 13S6Q, 12S1, and 12E1 was interrupted for about 3-4 hours on September 19, 2003, during the monitoring period from September 17 through September 24, 2003. There was a wide area power outage during the referenced time period due to Tropical Storm Isabel.

Power was restored to the air sampling equipment and adequate sample volume was achieved for the monitoring period.

The sample pump at monitoring station 12E1 experienced a pump motor failure during the monitoring period from October 1 through October 8, 2003. Low sample volume was obtained during the sample period due to the pump motor failure. The Air Sample Pump was replaced.

The sample pump failed at monitoring station 6G1 during the monitoring period from June 4 through June 11, 2003. Low sample volume was obtained during the sample period due to the pump motor failure. The Air Sample Pump was replaced.

Collectively, the air sampling equipment at the six air monitoring locations operated routinely (as expected) for more than 99% of 2003 in spite of the exceptions noted above.

F.3 Monitoring Report Environmental Monitoring 2003 Radiological Environmental Report  : F-3

I I AppendiX F Ambient Radiation Monitorini Exceptions occurred to the monitoring of ambient radiation during the second and fourth quarterly monitoring periods of 2003. The second quarterly monitoring period was April 29 through July 24, 2003. The TLD's at location 3S4 were wet and unable to process for the referenced monitoring period. The fourth quarterly monitoring period was October 21, 2003 through January 30, 2004. The TID's at location 14B3 were wet and unable to process.

F-4 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report  :~F*4

... - -... I., .- . - -

.,.;, . I' . I-

. ; . .1 , I ,

I-- - 1: "

. . .  : , I 7

. . . I  ! rI

. f. , -

APPENDIX G.

• 0 . . RE DP T- .

-K;ji . .

. .D4  ; .. . OF I *

-'I..

2003 Radiological Environmental Monitoring Report --- -- I I G-1 1

II Appendix G The averages for indicator and control locations reported in the Summary of Data Table, which summarizes the entire year's results for the SSES REMP, were calculated using all measured values, when available, whether or not they were reported in Appendix I tables. Values below the MDCs, even zeroes and negatives, were part of the averaging process for these analysis results. When no measured results are available in these cases, "LLD" is reported.

Preferably, the averages reported in the Summary of Data table for sample media that are normally collected continuously are determined using only results from continuously collected samples. Occasionally, grab samples are taken for these media when equipment malfunctions or other anomalies preclude or otherwise perturb routine continuous sampling. These grab samples are taken to minimize the time periods when no sampling is being performed, or, in some instances, when continuous sampling is considered to be nonrepresentative.

Because grab samples are snapshots of the media over brief periods, it is preferable not to average the analysis results of these samples with those for continuously collected composite samples. However, when equipment malfunctions are protracted, relatively large periods of time could be entirely unrepresented by averages if the results from grab sample analyses are not considered.

Allowing analysis results for grab samples to be weighted equally with those representing relatively large periods of time would tend to bias the resulting averages unjustifiably towards the conditions at the times that the grabs are obtained. Averages obtained in this way might less accurately reflect the conditions for the combined period Mali of continuous sampling and grab sampling than if only the results from continuous sampling were used. On the other hand, using weighting factors for the analysis results of grab samples derived from the actual time it takes to collect those samples would lead to the grab sample analysis results having a negligible effect on the overall average and not justifying the effort involved.

Grab samples collected in lieu of normal continuous sampling are typically obtained at regular intervals corresponding to the intervals (weekly) at which the continuously collected samples would usually be retrieved for eventual compositing. For example, grab samples are collected once a week but may be composited monthly in place of continuously collected samples that would normally be retrieved weekly and composited monthly. Since each grab sample is used to represent an entire week, albeit imperfect, it is reasonable to weight the analysis results the same. Thus, the results of one weekly grab are given approximately one-fourth the weight of the results for a monthly composite sample collected continuously for each of the four weeks in a month. Similarly, the analysis results of a composite of four weekly grab samples would carry the same weight as the analysis results for a composite of four weeks of continuously collected sample.

.J 2003 Radiological Environmental Monitoring Report G-2

(C (7 TABLE G

(

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30,2002 to January 30, 2004 Page I of 3 ANALYSIS AND LOWER LIMIT NUMBER OP MEDIUMORPATIIWAY TOTALNUMBER OP ALLINDICATORLOCATIONS LOCATIONWrITHIBIG1ESTMEAN CONTROLLOCATION NONROUII SAMPLED OP ANALYSES DETECTION MEAN(3) NAME MEAN(3) MEAN (3) REPORTED (UNI OF MEASUREMENr) PERFORMED (I) (LLD) (2) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS(4)

Ambient Radiation TLD 333 2.02E+01 (301 / 301) 9S2 4.061E+01 (4 / 4) 1.90E+01 (32 / 32) 0 (rnRfstdl. qtr.) (1.27E1+01 - 4.4713+01) 0.2 nd S (3.17E+01 - 4.471E+01) (1.41E+01 - 2.361E+01)

Surface Water aOn Beta 48 4 6.06E+00 (36 / 36) 2S7 1.10E+01 (12 / 12) 2.37E+00 (12 /12) 0 (pan) (2.42E+00 - 1.5913+01) 0.1 mi NNE (7.0813+00 - 1.5913+01) (6.08E-01 - 4.321E+00)

Tritium 48 2000 1.5713+03 (36 / 36) 2S7 4.42E+03 (12 /12) 3.181+01 (12 /12) 0

(-3.54E+01 - 1.66E+04) 0.1 mi NNE3 (1.13E+02 - 1.66E+04) (4.98E+01 - 1.37E+02)

Iodine-131 90 1 3.65E-01 (64 / 64) 2S7 7.77E-01 (26 / 26) 2.S813-01 (26 /26) 0

(.1.10-OI - 1.91B+00) 0.1 iniNNE (.1.10-OI - 1.911E+00) (-1.00E302 - 7.201E-01)

Gamma Spec 48 3.58E+00 (36 / 36) 6S5 4.75E+00 (12 / 12) 2.301E-01 (12 /12) 0

(-3.0013+01 - 5.0013+01) - 0.9- mH '1SE13 (-2.40E+013O - 4.1013+01) (-1.70E+01 - 2.4013+01)

Mn-54' 48 15 -8.37E-.02 (36 / 36) 6S6 2.55E-02 (12 / 12) 2.55E-02 (12 / 12) 0

(.1.90E+00 - I.50E+00) 0.8 ml- ESE (.1.00E+00 - 2.1013+00) (-.0013+00 - 2.1013+00)

Co-58 48 I -.2.053-01 (36 /36) 6S5 1.8313-01 (12 / 12) -8.0913-01 (12 / 12) 0

(-3.30E+00 - 3.60E+00) 0.9 Ini ESE1 (.2.40E+00 - 2.50E+00) (2.101+00 - 2.00Z-01)

Fe-59 48 30 1A9E-01 (36 /36) 6S5 1.23E+00 (12 / 12) 4.85E-01 (12 / 12) 0

(-6.00E+00 - 4.70E+00) 0.9 mi ESil (.2.10E+00 - 4.7013+00) (-1.40E+00- - 5.8013+00)

Co-60 48 15 2.961E-01 (36 / 36) 2S7 3.90E-01 (12 / 12) 2.6313-01 (12 /12) 0

(.1.10+00 - 1.9013+00) 0.1 mi NNE (-8.00E-01 - 1.90E+00) (-8.0013-01 - 3.00E+00)

Zn-65 48 30 4.81-01 (36 / 36) 6S5 7.9213-01 (12 / 12j -2.911E-01 (12 /12) 0

- (-1.073E+01 7.70E+00) 0.9 IniESE (.5.50E+00. - 6.00E+00) (4.40E+00 - 7.00E+00)

'A

.. 7 . .

0-3

TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 _

NAME OF FACILITY: SUSQUEILANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30, 2002 to Januay 30,2004 Page 2 of 13 ANALYSIS AND LOWER LIMIT NUMBEROF MEDIUM OR PATIWAY TOTAL NumBER OF ALLINDICATORLOCATIONS LOCATIONWITIIIJIGBESTMEAN CONTROLLOCATION NONROUllNE SAMPLED OF ANALYSES DBTECrION MEAN (3) NAME MEAN (3) MBAN (3) REPORTED (UNITOPMEASURMNT) VEPFORED(l) (lID) (2) RANGE DISTANCE AND DIRF.CION RANGE RANGE MHASUREMENTS(4)

Surface W4ter (conL) Zr-95 48 30 -6.20E-01 (36 / 36) 6S5 -2.92E-OI (12 1 12) -4.02E-01 (12 / 12) 0 (pCi/) (-5.80E+o0 - 3.70E+00) (9.00E-01 mi ESE (-2.90Et00

• 1.70EtO0) .(3.00EtOO - 150E+O0)

Nb-95 48 15 -8.60E-02 (36 ( 36) 6S6 2.96E-01 (12 / 12) 2.9611-01 (12 / 12) 0

(-3.80E+oo - 3.40E+00) (8.OOE-01 mi ESE (-2.20E+00 - 4A.E+00) -(2.20E+00 - 4AOE+00)

Cs-134 48 15 3.83E-01 (36 / 36) 2S7 4.73E-0O (12 / 12) 3.73E-01 (12 1 12) 0

(-1.70E+O0 - 2.80E+0O) (1.00-01 ml NNE (-9.00E-O - IAOE+00) -(2.70E 150E+00)

Cs-137 48 18 5.97E-02 (36 / 36) LTAW 6.08E-01 (12 / 12) -4.50-OI (12 / 12) 0

(-IAOE+00 - 3.70E+00) on site NE-ESE (-1.20E+00 - 3.70E+00) -(1.60E+00 . 4.7011-01)

Ba-140 48 60 8.97E-O1 (36 / 36) LTAW 1.36E+00 (12 / 12) -2.5411-01 (12 1 12) 0

(-3AOE+o0 - 5.70E+00) on site NE-ESE (1.501E+00 - 5.70E+O0) -(5.00E+00 - 2.70E+00)

La-140 48 15 1.03E+O0 (36 / 36) LTAW 1.57E+00 (12 / 12) -2.87E-01 (12 / 12) 0

(-3.90E+O0 - 6.50E+00) on site NEESE (-1.80E+00 . 6.50E+00) .(5.80E+00 - 3.10E+00)

(. I1 C-0-4

( C, TABLE G C

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30, 2002 to January 30, 2004 Page 3 of 13 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUMORPAT1WAY TOTALNUMBER OF ALLINDICATORLOCATIONS LOCATIONWIT11UGIIESTMEAN CONROLLOCATION NONROUTINE SAMPLeD OF ANALYSES DETECTION MEAN (3) NAME MEAN (3) MEAN (3) REPORTED (UNIT OFMEASUREMMMR PERP(RMED (1) (LLD) (2) RANGE DISTANCE AND DIRECON RANGE RANGe MEASUREMENTS(4)

Potable Water Omss Alpha 12 1.69E-01 (12 / 12) 12112 1.69E-01 (12 / 12) Only indicator 0 (pCin) (.6.54E 1.37E+00) 26 ml WSW (-6.54E 1.37E+00) stations sampled for this medium.

Gross Beta 12 4 2.26E+00 (12 / 12) 12112 2.26E+00 (12 / 12) 0 (8.98E 4.26E+00) 26 ml WSW (8.98E 4.26E+00)

Iodine-131 26 1 1.781:-01 (26 1 26) 12H2 1.781-01 (26 / 26) 0

(.1.60E-01

• 5.80E-01) 26 mi WSW (-1.60E-01

• 5.80E-01)

Tuitium 12 2000 6.43E+01 (12 / 12) 12H2 6.43E+01 (12 / 12) 0

(.7.67E+00 - 1.93E+02) 26 mi WSW (-7.67E+00 - 1.93E+02)

Gamma Spec K40 12 4.04E+00. (12 / 12) 12H2 4.04E+00 (12 / 12) . ; 0

(-2.00E+01 - 4.10E+01) 26- mi WSW (-2.00E+01 -; -, 4.10E+01)

Mn-54 12 15 -5.36E-02 (12 / 12) -, 12112 -5.36E-02 (12/12). 0

(-1.40E+00 - 9.00E-01) 26 mi WSW (-1.40E+00 - 9.00E-01)

Co-58 12 15 -4.26E-01 (12 / 12) 12112 -4.26E-01 (12/12) 0

(-1.20E+00 - 6.00E-01) 26 mi WSW (-1.20E+00 - 6.0013-01)

Fe-.59 12 30 -3.69E-01 (12 / 12) 12112 -3.69E-01 (12/12) 0

• (-3.60E+00 - 3.00E+00) 26 mi WSW (-3.60E+00 - 3.00E+00)

Co-60 12 15 1.55E-01 (12 / 12) 12112 1.55E-01 (12 / 12) 0

(-7.00E-01 - 8.00E-01) 26 mi WSW (-7.002 8.00E-01)

-Z .65 12 30 -1.21E+00 (12 / 12) 12H2 -1.21E+00 (12 / 12) 0

(.9.80E+00 - 6.10E+00) 26 mi WSW (-9.80E+00 - 6.102+00)

Zr-95 12 30 -5.11E-01. (12 / 12) 12112 -5.112-01 (12 / 12) 0

(-2.60E+00 - 4.00E-01) 26 mi WSW (-2.60E+00 - 4.00E-01) 0-5

TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30, 2002 to January 30, 2004 Page 4 of 13 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM OR PATHWAY TOrAL NUMBER OF ALLINDICATORLOCATIONS LOCATION VW1T`HIGHESIMEAN CONTROLLOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN(3) NAME MEAN (3) MEAN (3) REPORTED (UNITOFMEAStRPMENI) PERFORMED(I) (LLD) (2) RANGE DISTANCE AND DIRECTON RANGB RANGE MEASUREMENTS(4)

Potable Water (coit) Nb-95 12 15 1.8513-01 (12/ 12) 12H2 1.8513-01 (12 / 12) Only indicator 0 (PCU1) (-1.1013+00 - 1.1013+00) 26 mi WSW (-I.1013+00 1.103E+00) stations sampled for dts mcdiu.

Cs-134 12 15 9.2313-02 (12 / 12) 12112 9.2313-02 (12 /12) 0

(-5.7013 1.20E+00) 26 ni WSW (-5.70E 1.20E+00)

Cs-137 12 18 -1A4E-01 (12 / 12) 12112 -1.411E-01 (12 /12) 0

(-2.40E+00 - 1.60E+00) 26 mi WSW (-2.40E+00 - 1.6013+00)

Ba-140 12 60 3.051E-01 (12/ 12) 12H2 3.051E-01 (12 / 12) 0

(-2.80E+00 - 7.20Et00) 26 mi WSW (-2.80E+00 - 7.2013+00)

La-140 12 15 3.72E-01 (12 / 12) 12112 3.72E-01 (12 / 12) 0

(-3.201E+00 - 8.30E1+00) 26 mi WSW (-3.20E+00 - 8.30E+00)

( ( C- 04

C C TABLE G

(

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period:, December 30, 2002 to Januar 30,2004 I-age oalila ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM ORPATIIWAY TOTAL NUMBER OF ALLINDICATORLOCATIONS ., LOCATIONWIT1H JUGITESTMEAN CONTROLLOCATION NONROunINE SAMPLED OP ANALYSES DETECION MEAN(3) NAME MEAN (3) MEAN (3) REPORTED (UNIT OF MEASUREMEN PERFORMED (1) (llD) (2) RANGE DISTANCE AND DIRECTION . RANGE RANGE MEASURE1S(4)

Fkh. I Ojmm K-jl40 Opec (pCitkg wet) K-40 13 3.58E+03 (7 / 7) LTAW 3.672+03 (I/ 1) .- 3.162+03 (6 / 6)

(1.30E+03 - 4.39E+03) on site NE-ESE (3.672+03 - 3.672+03) (1.30E+03 - 3.922+03)

Mn-54 13 130 1.95s+00 (7/ 7) LTAW 5.742+00 (I / 1) 3.152+00. (6 / 6)

(-9.19E+00 - 9.692+00) on site NE-ESE (5.742+00 - 5.74E+00) (-6.18E+00 - 1.34E+01)

Co-58 13 130 -1.67E+00 (7 7) LTAW -9.80E-01 (I / 1) -2.532+00 (6 6)

(.09ss+00o - .6.351+0^) on site NE-ESE (-9.802-01 - -.9.80E-01) (-6.14E+00- - 1.211+00)

Fe-59 13 60 -9.SIB3+u0 (7 / LTAW . . 1.0613+01 (I 1) .  ; -1.69e+00 (616)_;

(-4A0E+i"'- 1.57-E+001) on site NE-ESE (1.062+01 -  ; 1.062+01) (-2.84E+01,. - 1.88E+01)

CO-60 13 130 -1.593+00 (7 7). 2H 1.312-01 (6 6), 1.311-01 (6 /6)

(-7.972+00 - 4.40E+00)' 30 ml NNE (-8.69E+00 - 9.992+00) (.8.69E+00 - t 9.99E+00)

Zn-65 13 260 -3.992+01 (7 7) 211 -3.262+00 (6 /6) . . -3.261+00 (6 /6)-,

(8.642E+01 - 2.852+00) 30 ,mn NNE (.2.952+01 .- 9.28E+00) (-2.95E+01 * - 9.28E+00)

Zr-95 13 1.682-01 (7I7) 211 3.84E+00 (6 / 6) 3.841+00 (6 / 6)

(.1.501+01 - 1.362+01) 30 mn NNe (-3.25E+00 - 1.382+01) (-3.25E+00 - 1.38E+01)

Nb-95 13 0.00E+00 (7 7) 2H 0.002+00 (6 / 6) 0.00E+00 (6 /6)

(0.00^E+00 - 0.002+00) 30 mi NNe (0.00E+00 - 0.002+00) (0.00E+00 - 0.00E+00)

Cs- 134 13 130 -1.862+01 (7 7) LTAW 3.391+00 (I / 1) -1.47E+01 (6 / 6).

(4.351+01 - 3.39E+00) on site NE-ESE (3.391+00 - 3.392+00) (-6.6E2+01 - . 1.19E+00)

Cs-137 13 150 4.532+00 (7 /7) IND 5.192+00 (6 / 6) -1.782+00 (6 / 6)

(07.782-01 - -1.22e+01) 0.9-1.4 mi ESE (-7.78E-01 - 1.22E+01) (-8.29E+00 - 3.142+00)

I .. Ba-140 13 4.852+01 (7 /7) LTAW 1.5023+02 '( / 1) -3.49E+01 (6 / 6) -

,(-8.44E+01 - 1.85E+02) on site NE-ESE (1.50E+02 - 1.502+02) (-2.26E+02 - 4.392+01)

La-140 13 .6.57e+00 (7 / 7) IND. -6.252+00 (6 / 6) -7.25E+00 (6 / 6)

(.5.2.5+01 . - 3.312+01). 0.9-1.4 mi ESE (-5.25E+01 - 3.312+01) (-1.94E+01 - 7.42E-01) t I . I  ; ., . . , . -

. . ., 1 -

I .

.1 I I .. .

0-7

TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEIIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30,2002 to January 30, 2004 Page 6 of 13 ANALYSIS AND LOWER LIMIT NUMBEROP MEDIUM ORPATHWAY TOTALNUMBER OP ALL INDICATOR LOCATIONS LOCATION WVIT1HHIGHEST MEAN CONTROL LOCATION NONRO LINB SAMPLED OP ANALYSES DECRITION MEAN (3) NAME MEAN (3) MEAN (3) REPORTED (UNIT OFMEASUREMEIM PERFORMED(I) (LLD) (2) RANGE DISTANCEANDDIRECTION RANGE RANGE MEASUREMENTS(4) btdUtntn GJanuna Spcc (pCi/kg dry) IBe-7 3.30E+02 (6 16) 12P 6.99E+02 (2 / 2) 2.91E+02 (2/ 2)

(-2.53E+01 - 7.26E+02) 6.9 mid WSW (6.71E+02 - 7.26E+02) (2.58E+02 - 3.25E+02)

K-40 1.37E+04 (6 / 6) LTAW 1.52E+04 (2 2) 1.23E+04 (2 /2)

(1.04E+04 - 1.58E+04) on site NE-ESE (1.47E+04 - 1.58E+04) (7.23E+03 - 1.73E+04)

Mn-.54 9.58E+00 (6 / 6) LTAW 1.36E+01 (2/2) 3.11E+00 (2 /2)

(1.78E+00 - 2.55E+01) on sitc NE-ESE (1.78E+00 - 2.55E+01) (-3.54E+00 - 9.75E+00)

Co-58 .1.07E+01 (6 16) 12F -7.79E-01 (2 /2) -1.94E+01 (2 /2)

(-2.57E+01 - 2.41E+00) 6.9 mi WSW (1.78E+00 - 2.41E+00) (-2.82E+01 - -1.05E+01)

Fe-59 -6.29E+00 (6 / 6) 2B 2.58E+01 (2 2) 2.58E+01 (2 /2)

(-2.98E+01 - 4.92E+01) 1.6 nii NNE (2.31E+00 - 4.92E+01) (2.31E+00 - 4.92E+01)

Co-60 4.57E+00 (6 / 6) 7B 7.79E+00 (2/2) -2.50E+00 (2 /2)

(-9.06E+00 - 1.12E+01) 1.2 nl SE (4.42E+00 - 1.12E+01) (-1.20E+01 - 7.04E+00)

Znr65 7.53E+00 (6 / 6) LTAW 2.57E+01 (212) -3.32E+01 (2 / 2)

(-2.05E+01 - 4.05E+01) on siLte (1.08E+01 4.05E+01) (-6.23E+01 - 4.07E+00) 7.r-95 1.95E+01 (6 / 6) 7B 3.60E+01 (2 2) 1.38E+01 (2 /2)

(1.20E+00 - 4.37E+01) 1.2 ml SE (2.83E+01 - 4.37E+01) (5.34E+00 - 2.22E+01)

Nb-95 0.00E+00 (6 / 6) 2B 0.00E+00 (2 /2) 0.00E+00 (2 /2)

(0.OOE+00 - 0.00E+00) 1.6 mn NNE (0.00E+oo - 0.OOE+00) (0.OOE+00 - Q.OOE+00)

Cs-134 150 -2.28E+00 (6 / 6) LTAW 4.96E+00 (2/2) -6.59E+00 (2 / 2)

(-8.52E+00 - 7.96E+00) on silw NE-ESE (1.97E+00 - 7.96E+00) (-1.07E+01 - .2.53E+00)

Cs. 137 180 5.20E+01 (6 /6) 71B 8.92E+01 (212) 7.56E+01 (2 /2)

(6.91E+00 - 1.00E+02) 1.2 mi SE (7.81E+01 - 1.00E+02) (4.14E+01 - 1.10E+02)

Ba-140 8 -2.30E+01 (6 /6) 12P -4.68E+00 (2 /2) -4.79E+01 (2 / 2) 0

(-9.92E+01 - 7.40E+01) 6.9 nii WSW (-7.11E+00 - -2.25E+00) (-l.lOE+02 - 1.42E+01)

-4 L a-4 N

C C' TABLE G

(

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30, 2002 to January 30, 2004 Page 7 or 13 ANALYSIS AND LOWER UMlT NUMBER OF MEDIUM ORPATHIWAY TOTALNUMBER OF ALLINDICATOR LOCAIIONS LOCATION wrm TlUGHEST MEAN CONTROL LOCATION NONRfUTINE SAMPLED OF ANALYSES DETECTON MEAN(3) NAME MEAN(3) MEAN (3) REPORTED (UNrr OP MEASUREMENT PERFORMED (1) (Ufl) (2) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS(4)

Sediment (cord) La-140 8 -9.832+00 (6 I 6) 7B 2.81E+01 (2 / 2) 1.91E+01 (2 / 2)

(pCi/kg dry) (-9.79E+01 - 4.89E+01) 1.2 mi SE (7.352+00 - 4.89E+01) (1.78E+01 - 2.05E+01)

Ra-226 8 2.27E+03 (6 /6) 7B 2.61E+03 (2 / 2) 1.60E+03 (2 / 2)

(1.96E+03 - 2.86E+03) 1.2 mi SE (2.362+03 - 2.862+03) (7.502+02, - 2.45E+03)

Th-228 8 3.21E+03 (6 6) 7B 3.51E+03 (2 /2) 3.01E+03 (2 2)

(2.462+03 - 3.56E+03) 1.2 nii SE (3.47E+03 - 3.56E+03) (1.28E+03 - 4.74E+03)

Ground Water 'almuma Spec I/1) K-40 36 -1.552+00 (24 124) 2S2 2.492+00 (12 / 12) 2.332+00 (12 / 12)

(-5.102+01? - 2.70E+01) 0.9 mrdn' NNE-' (-1.90E+01 ;- 2.702+01) '-(-3.30E+i01 5.30E+01)>

,;154 '36 -1.18E-01 (24/ 24) 12F3 1.922-01 (12 / 12) 1.92E-01 (12/ 12)

(-2.90E+00 - 2.102+00)' 5.2 ffd WSW' (-1.402+00 . - '2.00+00) (-1.402+00 -' 2.00+00)

Co-58 36 15 -7.57E-01 (24 1 24) 12F3 -5.00E-02 (12 / 12) -5.002-02 (12 / 12)

(-2.70E+00 - 1.70E+00) 5.2, mil WSW; (-1.70E+00, - 1.20E+00) (-1.70E+00 - 1.202+00)

Fe-59 36 30 5.832-01 (24'/ 24)' 2S2 6.422-01 (12 / 12) 3.752-01 (12 / 12)

(-5.30E+00 - 6.102+00) 0.9, mi NNE (-5.30E+00 - 6.10E+00) (-4.20E+00 - 8.50E+00)

Co-6O 36 is -1;282-01 (24 / 24) 4S4 3.332-02 (12 / 12) -1.081E-01 (12 /12)

(-2.402+00 - 2.002+00) 0.5 ml ENE (-1.502+00 - 2.002+00) (-2.80E+00 - 1.902+00)

Zn-65 36 30 -1.32E+00 (24 / 24) 4S4 -1.202+00 (12 / 12) 4.432+00 (12 / 12)

(-9.40E+00 - 8.502+00) 0.5 mi ENE (-9.40E+00 - 8.502+00) (-2.80E+00 . - 2.80E+00)

Zr-95 36 30 -6.542-01 (24 / 24) 12F3 1.152+00 (12 / 12) 1.152+00 (12 / 12)

(-5.70E+00 - 3.302+00) 5.2 ml WSW (-2.70E+00 - 5.40E+00) (-2.70E+00 - 5.40E+00)

Nb-95 36 i5 -2.462-02 (24 1 24) 4S4 3.83E-01 (12 / 12) -2.422-01 (12 / 12)

(-2.902+00 - 3.0012+00) 0.5 ml ENR (-2.70E+00 - 3.002+00) (-2.40E+00 - 2.10E+00)

Cs-134 36 15 1.742-01 (24 1 24) 4S4. 4.422-01 (12 / 12) -3.672-01 (12 / 12)

(-2.40E+00 - 2.80E+00) 0.5, mi ENE (-9.002-01 - 2.802+00) (-1.70E+00 - 1.20E+00) 0-9

TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEIIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30,2002 to January 30, 2004 Page 8 of 13 ANALYSIS AND LOWER LIMIT MEDIUM OR PAThWAY NUMBER OF TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITII IIGiHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN (3) NAME MEAN (3)

(UNITOFMEASUREMENT) MEAN (3) REPORTED PERFORMED(I) (LLD) (2) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS(4)

Ground Water (coat) Cs-137 36 18 -1.28E-01 (24 / 24) 2S2 -1.14E-01 (12 / 12) -3.75E1-01 (12 / 12) 0 (pCi/l) (-1.70E+00 - 1AOE+00) 0.9 mi NNE (-1.70E+00 - 1.40E+00) (-2.20E+00 - 1.20E+00)

Ba-140 36 60 -2.67E-01 (24 / 24) 4S4 6.08E-01 (12 / 12) 1.08E-01 (12 / 12) 0

(-5.20E+00 - 3.OOE+00) 0.5 mi ENE (-1.80E+00 - 2.60E+00) (-4.80E+00 - 5.10E+00)

La-140 36 15 -2.96E-01 (24 / 24) 4S4 7.00E-01 (12/ 12) 1.25E-01 (12 / 12) 0

(-6.00E+00 - 3AOE+00) 0.5 mi ENE (-2.10E+00 - 3.00E+00) (-5.50E+00 - 5.80E+00)

H-3 36 2000 5.44E+01 (24 / 24) 4S4 8.43E+01 (12 / 12) 1.74E+01 (12 / 12) 0

(-6.74E+01 - 1.93E+02) 0.5 mi ENE (-2.46E+00 - 1.93E+02) (-8.84E+01 - 8.86E+01)

Air Partlculates Gross Bcta 312 10 1.46E+01 (208 / 208) 3S2 1.51E+01 (52 / 53) 1.34E+01 (104 / 104) 0 (E-03 pCi/m3) (3.59E+00 - 3.17E+01) 0.5 mi NE (5.30E+01 - 4.91E+00) (3.16E+00 - 3.10E+01)

Air Iodine 1-131 312 70 6.01E-04 (208 / 208) 3S2 8.29E-04 (52 / 52) -6.44E-05 (104 / 104) 0 (E-03 pCi/m3) (-5.27E 5.97E-03) 0.5 mi NE (5.20E+01 - -2.79E-03) (-3.74E 6.30E-03)

Air Particulates Gamma Spec Quarterly Composite Be-7 24 9.06E+01 (16 / 16) 12SI 9.10E+0I (4 / 4) 8.21E+01 (8 / 8) 0 (E-03 pCi/m3) (6.70E+01 - 1.1IE+02) 0.4 mi WSW (7.65E+01 - 1.06E+02) (6.63E+01 - 9.34E+01)

K-40 24 1.29E+00 (16 / 16) 3S2 2.21E1+00 (4 / 4) 9.20E-01 (8 / 8) 0

(-4.94E+00 - 4.04E+00) 0.5 mi NE (2.27E-01 - 4.04E+00) (-5.79E+00 - 4.66E+00)

Mn-54 24 3.63E-02 (16 / 16) 6GI 1.10E-01 (4 / 4) 9.23E-02 (8 / 8) 0

(-6.98E 2.23E-01) 13.5 mi ESE (-5.75E-02 - 3.29E-01) (-5.75E-02 - 3.29E-01)

( C- G-10

C ( C TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 _

NAME OF FACILITY: SUSQUEHIANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA-Reporting Period: December 30, 2002 to., Januaq 30,2004 ,

Page 9 of13 1.

ANALYSIS AND LOWER IIMIT NUMBEROF MEDIUMORPATHWAY TOTALNUMBER OP ALLINDICATORLOCATIONS LOCATIONWITIH!IGIMESTiMEAN CONTROLLOCATION NONROUIINE SAMPLED OPANALYSES DETECTION MEAN(3) NAME MEAN(3) MEAN (3) REPORTED (UNITOF MEASUREMET PERFORMED (1) LD) (2) RANGE DISTANCE AND DIRECTION RANGE RANGE MEAS'REMENTS(4)

Air Particulates (colt)

Quartery Composite Co-58 24 .1.76E-02 (16 / 16) 3S2 1.35E-01 (4 1 4) -9.012-02 (8 / 8) 0 (2-03 pCihn3) (-3.02E 4.75E-01) 0.5 ml NE ' (-6.89E-02 4.75E-01) (-3.55E-01 - 4.8tSE-02)

Fe-59 24 .9.55-02 (16 / 16) 12S1 5.03E-01 (4 1 4) 4.052-01 (8 / 8) 0

(-1.15+00 - 1.082+00) 0.4 mr WSW (I.OSE-01 - ) (-8.34E-01 - 1.2, 72+00)

Co-60 24 2.38E-02 (161 16) 801 8.38E-02 (4 1 4) 5.702-02, (8 / 8) 0

(-1.481-01 - 1.76E-01) 12 mi SSE (-3.44E-Q3 - 2.13E-01) (-3.17E-02, - 2.1: 32-01)

Zn:65 24 -2.882-01 (16 16) 12SI -7.97E-03 (4 1 4) -2.46E-01 (8 / 8) 0

(.1.34E+00' - 6.25E-01) 0.4 ' ' WSW (-5.66E01 . 6.25E-01) (..012+00, - -2.9 323-0 .. ..

1) .

Zr-95' 24' 1.78E-02 (16 116) 13S6 8.622-02 (4 4) -7.31E-02 (8 8) 0

(.5.132-01'-' 4.7iE-01j' 0.4 mi' W (.3.07E-01', 4.77E-01) (-2.42E-01 - 9.6 9E-02)

N-95 24 0.00E+00 (16 /16) 601 0.00,Q+00 (4 4) 0.00E+00, (8 18) 0 (0.00+00 ' - 0.00E+00) 13.5 mni ESE (0.00+00 -0.0023+00) (0.00+00 - 0.000E+00)

Cs.134 24 50 0.00E+00 (16 /16) 12S I -3.46E-02 (4 1 4) -3.002-01 (8 / 8) 0

(-8.96E 8.91E-02) 0.4 mi WSW (-9.70E-02 . 4.42E-02) (-8.09E201 - 2.4 9E-02)

Cs-137 24 60 4.152-02 (16 /16) 13S6 1.192-01 (4 14) 2.072-02 (8 / 8) 0

(-9.462-02 - 1.61E-01) 0.4 mi W (6.292-02 - 1.61E201) (-6.52E-02 - 1.CQ3E-01)

Ba-140 24 -4.59E+00 (16 /16) 12E1 5.54E+00 (4 4) 2.122-01 (t I 8) 0

(-2.38E+01 - 1.74E+01) 4.7 mi. WSW (4.032+00 - *1.74E+01) (.1.19E+01 - - 8.17E+00)

La-140 24 .2.94E+00 (16 / 16) 12S1 1.972+00 (4 14) 4.772-01 (8 /8) 0

_(-2.42E+01 - - 4.81E+00) 0.4 ml WSW (-4.43r-01 - *4.81E+00) I (-5.49E+00 :- 1.25E+01)

. .I 1 : I.. .

. j I . . I . I  ;. ..

- I  : . - -, -

a-i1

TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30, 2002 to January 30, 2004 Page 10 of 13 ANALYSIS AND LOWERuLlM NUMBERROF MEDIUMORPATIfWAY TOTALNUMBER OF ALLINDICATORLOCATIONS LOCATIONWITh 1IIESTMEAN CONTROLLOCATION NONROUMI SAMPLED OF ANALYSES DETECTION MEAN (3) NAME MEAN (3) MEAN (3) REPORTED (UNIT OF MEASUREMENT) PERFORMED (I) (LID) (2) RANGE DISTANCE AND DIRECION RANGE RANGE MEASUREMENTS(4)

Milk 1-131 76 1 5.32E-02 (57 / 57) 1001 9.08E-02 (19 / 19) 9.082-02 (19 / 19) 0 KCiA) (-1.70E 4.40E-01) 14 nii SSW (-8.00E 4.50E-01) (-8.00E 4.50E-01)

Gamnum Spec K-40 76 1.38E+03 (57 / 57) 1001 1.41E+03 (19 / 19) 1.41E+03 (19 / 19)

(9.40E+02 - 1.55E+03) 14 mi SSW (8.19E+02 - 1.53E+03) (8.19E+02 - 1.53E+03)

M&,54 76 -1.88E-01 (57 / 57) 10D2 -5.26E-02 (19 / 19) 4.42E-01 (19 /19)

(-4.30E+00 - 2.50E+00) 3.1 mn SSW (-2.60E+00 - 2.50E+00) (-3.10E+00 - 1.60E+OO)

Co-58 76 -4.00E-01 (57 /57) 10SI -7.89E-02 (19 /19) -7.892-02 (19 / 19)

(-4.10E+00 - 3.30E+00) 14 mi SSW (-3.70E+00 - 2.30E+00) (-3.70E+00 - 2.30E+00)

Fe-59 76 4.60E-01 (57 / 57) 10D2 8.32E-01 (19 / 19) 1.42E-01 (19 / 19)

(-1.20E+01 - 1.22E+01) 3.1 mn SSW (-4.00E+00 - 8.00E+00) (4.60E+00 - 7.30E+00)

Co-60 76 2.47E-01 (57 /57) 10DI 6.11E-01 (19 I 19) 2.21E-01 (19 / 19)

(-4.70E+00 - 5.40E+00) 3 ni SSW (-3.002+00 - 3.30E+00) (-2.90B+00 - 2.90E+00)

Zn-65 76 -2.77E+00 (57 / 57) 10D2 -9.212-01 (19 / 19) -2.92E+00 (19 / 19)

(-1.60E+01 - 7.00E+00) 3.1 mi SSW (-1.602+01 - 7.00E+00) (-1.34E+01 - 4.20E+00)

Zr.95 76 -2.63E-02 (57 /57) 12B2 3.58E-01 (19 1 19) -2.58E-01 (19 / 19)

(-7.20E+00 - 3.60E+00) 1.7 mi WSW (-4.30E+00 - 3.60E+00) (4.30E+00 - 7.50E+00)

Nb-95 76 2.56E-01 (57 / 57) 1I00 4.37E-01 (19 1 19) 4.37E-01 (19 / 19)

(-2.80E+00 - 4.70E+00) 14 mi SSW (-2.00E+00 - 2.70E+00) (-2.00E+00 - 2.70E+00)

Cs-134 76 15 .8.77E-03 (57 / 57) 10D2 4.11E-01 (19 / 19) -2.212-01 (19 / 19)

(-4.00E+00 - 4.10E+00) 3.1 mi SSW (-1.70E+00 - 2.80E+00) (-2.80E+00 - 2.60E+00)

Cs-137 76 18 -8.77E-03 (57 /57) 1001 5.58E-01 (19 /19) 5.582-01 (19 / 19)

(-3.20E+00 - 3.50E+00) 14 Imi SSW (-1.202+00 - 2.60E+00) (-1.20E+00 - 2.60E+00)

Ba-140 76 60 -2.49E-01 (57 / 57) 1001 1.89E-01 (19 / 19) 1.89E-01 (19 / 19)

(-4.80E+00 - 5.00E+00) 14 mi SSW (-2.701+00 - 3.90E+00) (-2.70E+00 - 3.90E+00)

La-140 76 15 -2.88E-01 . (57 / 57) 1001 2.16E-01 (19 / 19) 2.16E-01 (19 / 19)

(-5.50E+00 - .5.80E+00) 14 Im SSW (-3.10E+00 - 4.40E+00) (-3.10E+00 - 4.40E+00)

C-012

( I

( C TABLE G (C

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30,2002 to Janiiay 30, 2004!

- Page 11 of 13 ANALYSIS AND LOWER LIMIT MEDIUM ORPATIIWAY TOTALNUMER NUMBER OF OF ALLINDICATORLOCATIONS LOCATIONWT IIGGEST MEAN CONTROLLOCATION NONROLINE SAMPLED OP ANALYSES DETECTION MEAN (3) NAME MEAN (3) MEAN(3) REPORTED (UNIT OF MEASUREMENT) PERFORMED (l) (LLD) (2) RANGE DISTANCE AND DIRECTION - RANGE RANGE MEASUREMENTS(4)

Soil Gamma Spec (pCi/kg dry) K-40 8 1.44E+04 (6 / 6) 13S6 1.6213+04 (2 /2) , 1.0613+04 (2/ 2) 0 (1.0313+04 1.82E1+04) 0.4 mi W (1.43E+04 - 1.82E+04) (1.02E+04 - 1.1013+04)

Mn-54 8 -1.5013+00 (6 / 6) 13S6 -5.0013-01 (2 / 2) .1.2013+01 (2/ 2) 0

(-9.0013+00 - 4.0013+00) 0.4 mn W (.5.0013+00 - 4.0013+00) (.1.90E+01 - -5.0013+00)

CO-58 8 -6.3313+00 (6 /6) 3S2 1.0013+00 (2 / 2) O.O0E+00 (2/2) 0

(-.18013+01 - 9.OOE+00) 0.5 nil NE (-7.0013+00 - 9.0013+00) (.5.0013+00

• 5.00E+00)

Fe-59 8 -6.17E+00 (6 /6) 13S6 4.OOE+00 (2/2)-,. . 4.0513+01 (2 2) 0

(-2.80E+01 - 3.6013+01) 0.4 al W (-2.8013+01 - 3.6013+01) (.7.20E+01 - -9.0013+00)

Co:60 8 .4.0013+00 (6 / 6) , 3S2 7.0013+00 (2/ 2) -1.0013+01 (2 / 2) 0

- 1.2013+01) 0.5 mi NE (2.0013+00 - 1.2013+01) (-1.8013+01 - -2.0013+00)

Zn--65 8 -1.8713+01 (6 / 6) 12SI 9.O0E+00 (2 / 2) 5.0013+00 0

- (2 2)

(-1.10E+02 - 6.00E+01) 0.4 mld WSW (-3.2013+01 - 5.00E+01) (.3.0013+01 - 4.00E+01)

Zr-95 8 -1.15E+03 (6 / 6) 8C1 4.8013+01 (2 / 2), . 4.8013+01 (2 2) 0

(-6.70E+03 - 3.0E+01) 12 nii SSE (4.70E+01 . 4.9013+01) (4.7013+01 - 4.9013+01)

. I I. ~. .. Nb-95 8 -4.6713+00 (6 / 6) 8GI 1.7013+01 (2 / 2) 1.7013+01 (2/ 2) 0 8 (-4.30E+01 - 1.6013+01) 12 mi SSE (-5.OOE+00 - 3.9013+01) (-5.0013+00 - 3.90E+01)

Cs-134 3.83E+00 (6 / 6) 801 3.30E+01 (2 12) 3.30E+01 (2/ 2) 0 8 (-7.00E+00 - 2.4013+01) 12 nii SSE (1.4013+01 - 5.20E+01) (1.40E+01 - 5.20E+01)

,Cs- 137 4.2813+01 (6 / 6) 12SI 8.6013+01 (2 / 2) 7.4513+01 (2/ 2) 0 8 (-2.1013+01 -, 9.60E+01) 0.4 mi. WSW (7.6013+01, - 9.60E+01) (5.2013+01 - 9.7013+01)

. Ba- 40 6.6713-01 (6 / 6) 3S2 2.5013+01, (2 / 2) -1.8013+01 (2 / 2) 0 Ba-140 8 (.5.00E+01  : 8.00E+01) 0.5 mi NE '(1.0013+01 - 4.0013+01) (.2.50E+01 - -1.1013+01)

-1.1313+01 (6 /6) 3S2 1.0513+01 (2 / 2) -2.0513+01 (2 / 2) 0

-(4.90E+01 - 1.4013+01) 0.5 nu NE (7.00E+0 -*- 1.4013+01) -(2.80E+01 - -1.30E+01)

I . . , 1, 1 I ,, ., . . . . .

. . .  : I . . , -

" :-o. , , , I " I ,0 I.,

I I . I I I-I II

. I I  :-

o-13

TABLE G

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . 2003 _

NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30,2002 to January 30, 2004 Page 12 of 13 ANALYSIS AND LOWER LIMIT MEDIUM ORPATIlWAY TOTALNUMBER OF NUMBER OF ALLINDICATORLOCATIlONS LOCATION WIT111GI]EST MEAN CONTROLLOCATION SAMPIED OF ANALYSES NONROUTINE DETECTION MEAN(3) NAME MEAN(3) MEAN(3)

(UNITOPMEASUREMEbBT PERFORMED(1) REPORTED (LLD) (2) RANGE DISTANCE AND DIRECTION RANGE RANGE MBASUREMENTS(4)

Soil (colt) Ra-226 0 (pCi/kg dry) 0 nh-228 7.891E+02 (6 6) 3S2 1.02E+03 (2 2) 8.15E+02 (2 /2)

(-2.00E+00 - 1.04E+03) 0.5 mi NE (1.00E+03 - 1.04B+03) (7.30E+02 - 9.00E+02)

Food/Garden Crops Gammn Spcc (pCi/kg wet) Bc-7 8.431E+00 (2 / 2) 11F 2 1.391E+01 (1 1)

(2.95E+00 - 1.39E+01) 5.5 mi SW (1.39B+01 - 1.39E+01)

K-40 4.56E+03 (2 1 2) IID:2 4.66E+03 (1/ 1)

(4.47E+03 . 4.66E+03) 3.5 mi SW (4.66E+03 . 4.66E+03)

Mn-54 -4.75E-01 (2 2) IID:2 1.36E+00 (1 1)

(-2.31E+00 - 1.36E+00) 3.5 mi SW (1.36E+00 - 1.3613+00)

Co-58 -1.281E+00 (2 2) 1ID:2 -1.07E+00 (1/1)

(-1.48E+00 - -1.07E+00) 3.5 mi SW (-1.07E+00 - -1.07E+00)

Fe-59 -3.75E-01 (2 / 2) llF; 1.97E+00 (1 /1)

(-2.72E+00 - 1.97E+00) 5.5 mi SW (1.97E+00 - 1.9713+00)

Co-60 3.481E+00 (2 1 2) lip, 2 5.53E+00 (1/ 1)

(1.42E+00 - 5.53E+00) 5.5 mi SW (5.53E+00

• 5.531E+00)

Z&-65 -2.01E+01 (2/2) 11F 2 -1.691E+01 (1/ 1)

(-2.33E+01 - .1.69E+01) 5.5 mi SW (-1.69E+01 - -1.69E+01)

Zr-95 7.40E-01 (2 1 2) lF 2 5.73E+00 (I I 1)

(4.25E3+00 - 5.73E+00) 5.5 mi SW (5.7313+00

• 5.73E+00)

Nb-95 0.00E+00 (212) IID)2 0.00E+00 (1/1)

(0.OOE+00 0.001E+00) 3.5 mi SW (0.OOE+00

• 0.0013+00) 1-131 2 -6.3213+00 (2 / 2) liF2 2 -6.01E+00 (I / 1) 0

(-6.631E+00 - -6.01E+00) 5.5 'mi SW (-6.01E+00 - -6.0113+00)

I 0-14 c

(. C.

TABLE G

(

SUMMARY

OF DATA FOR SSES OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM - 2003 NAME OF FACILITY: SUSQUEHANNA STEAM ELECTRIC STATION LOCATION OF FACILITY: LUZERNE COUNTY, PENNSYLVANIA Reporting Period: December 30,2002 to January 30,2004 Page 13 of 13 ANALYSIS AND LOWER LIMIT NUMBER OF MEDI OR PATHWAY TOTAL NUNMER OF ALINDTCATOR LOCATIONS LOCATIONWITHHIGHEST MEAN CONTROLLOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN (3) NAME MEAN (3) MEAN (3) REPORTED (lUNIT OFMEASUREMPM PERFORMED (I) (lLD) (2) RANGE DISTANCE AND DIRECION RANGE RANGE M 4ASURMEM(4)

Food/Garden Crops (cont)

(pCi/kg wet) Cs-134 2 -1.9113+01 (2 / 2) 11F2 -1.8213+01 (I / I) 0

(-2.0013+01 - -1.82E+01) 5.5 mi SW (-1.82E+01 - -1.8213+01)

Cs-137 2 -3.5413+00 (2 / 2) 1ID2 -1.07E+00 ( I /1) 0

(-6.0013+00 - -1.07E+00) 3.5 ml SW (-1.07E+00 - -1.07E+00)

Ba-140 2 1.8913+01 (2 / V 11F2 4.4113+01 (I / 1) 0

(-6.32E+00 - 4.4113+01) 5.5 ml SW (4.41E+01 - 4.41E+01)

La-140 2 -1.8413+00 (2 / 2) 1ID2 5.5813-01 (I / 1) 0

(-4.24E+00 - 5.5813-01) 3.5 mni SW (5.58E-01 - 5.58E-01)

1. The total number of analysis does not include duplicates, splits, or repeated analyses.

2. The Technical Requirement LLD's are shown when applicable.

3. The means are based on all available measured resultsV When possible, this includes those below the MDCs as well as those above them.

4. USNRC reponling levels are specified in the Technical Requirements.

0-15

APPENDIX H I*i -. :TI -I -V -

6M QNOY.PNDICATORA1I 'CONTROL 2003MEANS -FOR SE LETEDt MEDL I IRIc 'S TWIT-H NiEANSSULT S

t;; os ttt;',it^r't.stA' ~'tt

.VR 1f:;.i;!;?

^;;:-tt~,st>.

,','~

'ii;~~~ ~ b ~

E~;E R I Nf4 TFRI ji;~f H-I 2003 Radiological Monitoring Report Radiological Environmental Monitoring Report H-1

I I Appendix H J3 The data presented in the following tables were included if specific analysis results routinely exceeded the applicable MDCs in 2003'and/or routinely may have done so in previous years. The comparisons may be useful for observing any step changes that may occur in the environment over a wide area. However, the importance attached to these comparisons should' be tempered by the understanding 'that changes- in methods, of analysis, typical MDCs achieved by the analyses, and averaging methods over the years may tend to blur the picture in some cases.

H-2 2003 Radiological

-2003 Monitoring Report Environmental Monitoring Radiological Environmental Report H-2

Appendix H AMBIENT RADIATION MONITORING TABLE HI AMBIENT RADIATION LEVELS AS MEASURED BY TLDS (rnR/STD OTR)

--Location -- 7 Indicato '-'-- l- '.Control.

Period Pre-Op Operational l Pre-Op l Operational '

. _._. 1978-81 1982-02 2003 1978-81 ' 1982-02 '2003 I Range 18.5-19.2 14.7-20.8 -- 1 15.0-17.9 14.8-20.8 --

Mean 18.9 . 18.2 l 20.2 16.3 l 17.9 19.0 AOUATIC PATHWAY MONITORING

TABLEH2.,

'___ _'SURFACE WATER GROSS BETA ACTIVITIES (pCi/l)

Location l''__ Indicator' ' Control Period Pre-Op Operatidnal Pre-Op Operational

_ 1978-81 1982-02 2003 1978-81 1982-02 2003 Range 3.2-4.9 3.07.7 2.9-5.2 2.8-6.7

• Mean 3.8 l 56. 61; 4.0 3.8 2.4 TABLE H 3

.. - SURFACE WATER IODINE-131 ACTIVITIES (pCi/1)

Location Period, Pre-Op 1979-81 Indicator Operational 1982-02 2003 J. =

Pre-Op 1979-81 Control Operational 1982-02 I 2003 Range 0.24-0.37 J 00.61 lI -- 0.29-0.43 0.03-1.0 l --

Mean 1 0.29 0.32 0.36 0.36 J 0.32 0.26

-TABLEH4

.SURFACE WATER TRITIUM ACTIVITIES (pCi/I)

Location Indicator I i.us Control Period Pre-Op l - ertiojial Pre-Op- O0erational

.... 1978-81 1982 02* -2003 ... 1978-81 1-'1982-02* 2003

-Range 101-122 126-1363 119-319 -239-+212 Mean J 109 573 1,576 171 52 32

• 1990 results were not averaged with 1982-01 data because the validity of the 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the 1990 Annual Report.

H- 200 Ra ilo ia En ioma o ioi g R p r

.H-3 -2003 Radiological Environmental Monitoring Report

I I Appendix H TABLE HS, Period DRINKING WATER GROSS ALPHA ACTIVITIES (pCi/I)

Preoperational [ Operational

J)

_________ 1980 -81 - 1982 -02 I 2003.

Range 0.1 -10.0-Mean 1.3 1.4 0.18 TABLEH6 DRINKING WATER GROSS 13ETA ACTIVITIES (pCi/l)

Period Preoperational L Operational

________ 1977 -81 1 1982 -02. 2003 Range 2.2 -3.2 2.1-5.4 I --

Mean 2.7. '3.1 2.1 TABLE H 7 DRINKING WATER TRITIUM ACTIVITIES (pCi/l)

Period Preoperational [ Operational

. 1977 - 81 1982 - 02 2003 Range 101 -194 -247 '- +220 --

Mean - 132 L 62 62 TABLE H 8 _

FISH POTASSIUM-40 ACTIVITIES (pCi/g wet)

Location Control Period Pre-Op Operational Pre-Op Operational 1977-81 1982-02: 2003- 1977-81 2003 Range 2.7-3.5 3.1 - 5.3 -- 2.8 - 3.6 3.1-4.2 --

Mean l 3.2 3.8 3.6 3.2 3.5 3.2 Monitoring Report H-4 Radiological Enyironmental 2003 Radiological Environmental Monitoring Report H4

AopenduicH

,TABLE H 9.

i_ SEDIMENT POTASSIU-M40 ACTIVITIES (pCig dry)

Location Indicator - Control Period . Pre-Op 0 erationa Pre-Op 'Operational

_ . 1978-81 19 2003  :'1978-81 1982-02 [. 2003 Range' l'Mean' 8.6-10.4

`9.3 7.4-13.6 10.8 12.3 J 7.5-110 7.7

.6.2-13.0

.10.5 12.9 TABLEHIO SEDIMENT RADIUM-226 ACTIVITIES (pCi/g dry)

Location l Indicator l Control Period Pre-Op Operational .Pre-Op Operational

_ _ 1978-811 1982-02 2003 -1978-81 -1982-02 2003 Range 0.5-0.7 0.5-2.0 _ .0.6-1.9 0.4-2.1 I -

Mean . 0.6. . 1.5 .2.4_. 0.7 . .1.5 1.6

- . .. ..-- TABLEHJ1.

SEDIMENT THORIUM-228 ACTIVITIES (pCi/g dry)

Location .. Indicator . Control Period .' 1984 -02* .. - T-2003 1984-02* 2003 Range l 0.9-1.7 l '- 0.8-2.1 .

Mean 1.1 3.2 j 1.1 3.0

• Th-232 was reported instead of Th-228 in'-1990. -; -'

TABLE H 12

.__.__._ SEDIMENT CESIUM-137 ACTIVITIES (pCi/g dry)

Location'. . Indicator- 'Control Period 'Pre-Op' ' Pre-Op Operational

- -_1978-81.8 .1978-81 -:1982-02.. -2003 1 1982-02 2003 Range j 0.08-0.15 0.04-0.17 - 0.08-0.21 0.06-0.21 -

Mean 0.10 0.09 0.07 0.11 0.1l 0.08 H- 200 Railoia EniomnaoioigRp H-5 . 2003 Radiological Environmental Monitoring Report

I I A ppendix H ATMOSPHERIC PATHWAY MONITORING TABLEH13 AIR PARTICULATE GROSS BETA ACTIVITIES (E-3 pCiin 3 )

Location -_:_

.Indicator ._:._l_._;_. Control Period Pre-Op Operational l Pre-O Operational L1978-81 1982-02 2003 l 1978-81 1982-02 l2003 Range 24 - 97 13 - 29 -- [ 24 - 102 12 - 28 --

Mean 61 16 1 62 16 13

. .TABLE H14 AIR PARTICULATE BERYLLIUM-7 ACTIVITIES (E-3 pCi/m3 ,

. Location .l_._. _Indicator l_--: _Control Period .Pre-Op Operational. Pre-O.l Operational

_ 1978-81 1982-02* 2003 1978-81l 1982-02* 2003 Range l 69 - 81 0 - 137 -- 59 - 85 49 - 126 --

Mean 76 - 95 91 72 88 82

• 1990 results were not averaged with 1982-01 data because the validity of the _-Ji 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the 1990 Annual Report.

TERRESTRIAL PATHWAY MONITORING TABLE H 15 SOIL POTASSIUM-40 ACTIVITIES (pCilg dry)

Location Indicator Control Period Pre-Op Operational Pre-Op. Operational.;

. 1979&81 j.1984-02 2003 1979&81 1984-02 l 2003 Range l 9.2-9.7 9.4-15.3 9.1-11.0 [' 7.4-14.1 --

Mean 9.5 11.7 14.4 10.1 10.5 10.6 H-6 Ji 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report -.H-6

Appendix H

.TABLE H 16

.., --. SOIL RADIUM-226-.4-CTIVITIES '(Ci/g ., Iry)

Location I '_ ' Indicator I Control Period . Pre-Op: I

' Operational .I . .Pre-Op

Operational 1979&81. 1; 1984-02* 12003*' 1979&81 .-.. 1984-02 1 2003 Range Mean

'0.8- 1.3 l0.8-2.5 1.1 1.6 4

'0 J - 0.8- 1.2 10

1.0-2.2 l' _ _1.7 _ ' 0

• Radium-226 was not measured in 2002 or 2003.

TABLE H 17

-_'_'_._- SOIL TIIORIUM-228 ACTIVITIES (pCiig dry)

Location l Indicator T Control Period Pre-Op 1Operational Pre-Op 4Operati nal 1979&81 198402 l2003 1979&81 1984-02 ei2003al Range 0.9 -1.3 0.8 - 2.0 -- 0.7 -2.4 Mean 1.1 1.0 0.8 1.0 1.0 0.8 TABLE H 18

__-_._._: :SOIL CESIUM-137 ACTIVI'rIES (pCilg'clry)

Location Indicator Control Period Pre-Op Operational Pre-Op Operational 1979&81 1982-02 2003 1979&81 1982-02 2003 Range 0.5 -0.7 l.0.52 l 0.2- 1.2 l 0.09- 1.2 l --

Mean 0.6 0.2 0.04 0.7 0.4 0.07 TABLE H 19 MILK POTASSIUM-40 ACTIVITIES (pCill)

Location Period 1 Pre-Op Indicator Operational l _Control_7 Pre-Op l Operational

_ 1978-81 1985-02 2003 1978-81 1 1985-02 2003 Range 1222-1500 1241-1422 -- 1273-1500 1247-1472 --

Mean 1 1325 1333 1383 1390 1331 1406 1H-7 `2003

' Radiological Environmental Monitoring Report

.1a Appendbc H TABLE H 20 GROUND WATER TRITIUM ACTIVITIES (pCi/1)

Location Indicator Control Period Pre-O Operational' Pre-Op. Operational 1980-81 1982-02 2003 1980-81 1982-02 2003' Raige 94-109 206: 180- 17 -119 -l-206-

+260 Mean 101 l 59 54 118 67 17 H-S

-2003 Radiological Environmental 2003 Radiological Monitoring Report Environmental Monitoring Report H-8

I  : . ,l. . , . 'l. I' 1, .

I .; . , i w

. I I . .. l X . . APPENDIX I

• VIDz -

'AVP14t ANf ' ' 'Q{; :

'ttii~u ., LY3.V. 3 JU+/-'..L rr'n J t SS

s

~

I~ i, .. ..  ;

I . -

I ;I

• I 1. .

.. . . . . ... I .

I . -1 2003 Radiological Environmental Monitoring Report .I-1

I I Appendby I Results of analyses are generally reported in the following tables to two significant figures. Random uncertainties of counting are reported to the same decimal place as the result.

Calculated values for analysis results are reported with the random uncertainty of counting at two standard deviations (2S), determined by considering both the sample and background count rates. The uncertainty of an activity is influenced by the volume or mass of the sample, the background count rate, the count times, the method used to round off the value obtained to reflect its degree of significance, and other factors. The uncertainties of activities determined by gamma spectrometric analyses are also influenced by the relative concentrations of the radionuclides in the sample, the energies and intensities of the gammas emitted by those radionuclides, and the assumptions used in selecting the radionuclides to be quantitatively determined.

Results reported as less than (<) in these tables are below the minimum detectable concentrations (MDCs). The MDC is an estimate of the detection capabilities of the overall measurement method, taking into account not only the counting system, but also the characteristics of the sample being counted. When the MDC is used as the level to decide whether or not to enter a measured value into a table, there is a 50% chance that the value will be entered when the actual sample activity is equivalent to the MDC.

There is only a five percent chance that a value representing a fluctuation in background activity will be entered as sample activity in such an instance.

Measured values for the activities of specific radionuclides, such as the man-made gamma-emitting radionuclides beryllium-7 and cesium-137, only appear in the following tables for each specific medium when the levels that are measured exceed the MDC values for those measurements and those radionuclides are actually identified as present in the samples. Measured values for the analyses that are not radionuclide specific, such as gross alpha and beta analyses, also are presented in the tables for specific media only when the levels that are measured actually exceed the MDCs.

2003 Radiological Environmental Monitoring Report I-2

( -TABLE C. I-1

(

ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003. a Results (I) are in mR/std. qtr (2) +/- 2S (3)

First Quarter Second Quarter Third Quarter Fourth Quarter 01129/03 to 05101103 04129/03 to 07/24/03 07/22103 to 10123/03 10/21/03 to 01/30104 Location ONSITE IS2 23.6 I 1.4 24.3 +/-: 1.9 23.6 +/- 1.2 26.5 +/- 2.1 2S2 17.5 +/- 1.8 15.8 + 1.3 20.5 +/- 0.8 17.9 +/- 1.1 2S3 20.4 +/- 0.8 20.5 + 1.5 23.6 +/- 0.4 23.2 +/- 2.3 3S2 17.6 +/- 1.4 16.0 +/- 1.1 19.5 +/- 1.2 18.4 4 1.5 3S3 17.0 +/- 1.6 15.0 + 1.3 19.1 +/- 2.6 18.1 4 0.9 3S4 17.2 +/- 1.4 (4) 19.4 + 1.8 18.3 +/- 1.1 4S3 22.0 : 1.2 21.0 + 1.1 24.2 + 1.0 23.5 +/- 1.9 4S6,,,,; 17.8 +/- 1.6 16.9 + 1.3 20.8 +/- 1.2 18.4 I 1.3

- 5S4§4 16.1+-1.0 14.9 k- 1.3 ---18.4 +/- 1.6- -17.2 0.9-5S7 17.8 +/- 1.8- 16.6 > 1.1- 19.6 +/- 1.4 18.3 +/- 1.5' 6S4'; 23.8-+/- 1. 24i.3+/- 2.1 27.9 + 1.2 26.8 +/- 0.9~

6S9 22.6 b0.6 23.2 :+/- 1.1 27.6 +/- 1.8 25.7 +/- 0.8 7S6 22.9 +/--1.8 23.3 1.3 26.7 +/- 1.2 25.8 +/- 1.3 7S7 17.3 + 1.0' 15.9 +/-!1.5 19.9+/- 1.2 19.1 +/- 0.9 8S2 22.9 +/- 1.4 22.5 +/- 1.7 2i.'4 4+/- 3.0' 25.5 +/- 0.9 9S2 31.7 4- 1.8 41.9 +/- 6.4 44.7 4 2.6 44.1 +/- 3.0 10S 17.1 b 1.8 15.96 1.7 19.1 +/- 2.4 18.1 +/- 1.1 10S2 26.6 +/- 1.2 29.2 +/- 1.1 33.3 +/- 2.4 31.6 +/- 1.9 10S3 16.3 +'0.6 15.1 +/- 1.3 18.6 +/- 1.4 16.8'+ 0.9 I1S3 24.8 +/- 1.6 24.6 +/- 1.1 28.1 +/- 1.4 27.4 +/- 0.9 IiS7 18.0 +/- 1.2 16.9'+/- 1.1 20.8 +/- 2.4 20.1' + 1.3 1-3

TABLE 1-1 ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results (1) arc in mR/std. qtr (2) +/- 2S (3)

First Quarter Second Quarter Third Quarter Fourth Quarter 01/29/03 to 05/01/03 04/29/03 to 07/24/03 07/22/03 to 10/23/03 10/21/03 to 01/30/04 Location 12S1 19.0 + 1.2 17.4 +/- 1.1 21.5 +/- 1.4 19.6 +/- 1.3 12S3 24.2 +/- 1.2 22.8 +/- 1.5 25.9 +/- 0.8 24.3 +/- 1.7 12S4 24.9 +/- 1.0 23.0 i 2.1 26.5 +/- 2.0 24.9 +/- 0.9 12S5 21.0 +/- 0.6 20.3 +/- 1.3 22.6 +/- 1.6 21.8 +/- 0.9 12S6 21.4 +/- 1.0 19.9 +/- 1.7 23.6 +/- 1.4 21.8 +/- 1.7 12S7 16.8 +/- 1.2 14.9 +/- 0.9 17.7 +/- 1.8 17.2 +/- 0.6 13S2 23.4 +/- 1.2 21.7 +/- 1.7 26.1 +/- 1.4 24.3 +/- 0.8 13S4 22.9 +/- 1.6 20.7 +/- 1.1 25.9 +/- 1.6 22.8 +/- 0.6 13S5 24.5  : 2.4 22.4 +/- 2.6 27.1 +/- 1.4 25.4 +/- 1.7 13S6 22.5 +/- 2.0 21.1 +/- 1.3 24.2 +/- 1.8 23.0 +/- 1.5 14S5 21.4 +/- 1.2 20.6 +/- 1.7 23.5 +/- 1.4 21.2 +/- 1.5 14S6 19.9 +/- 1.0 19.1 +/- 1.5 22.7 +/- 0.4 20.3 +/- 1.5 15S5 19.5 +/- 1.0 17.8 +/- 0.6 21.8 +/- 1.0 21.2 +/- 4.5 16S1 22.3 +/- 1.8 22.2 +/- 1.1 24.4 +/- 1.0 23.8 +/- 1.3 16S2 23.3 +/- 1.2 21.1 +/- 1.5 25.3 +/- 1.4 23.9 +/- 1.5 See the conuments at the end of this table.

14 L U

( (

TABLE 1-1

(

• ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results (1) are in mR/std. qtr (2) +/- 2S (3)

First Quarter Second Quarter Third Quarter Fourth Quarter 01/29/03 -to 05/01/03 04129/03 to . 07/24/03 07/22/03 to- 10/23103 10121/03 to 01/30/04 Location 0-1 MILE OFFSITE 6A4 . 20.7 -4 1.6' 18.7 -: 1.3 22.7 +/- 1.2 ' 21.1 4- 0.9 8A3- 17.5 4 0.8 15.4 + 1.7 19.2 +/- 1.6 18.3 4 0.7 15A3 18.9'+ 2.0 17.7 + 1.9 20.9 +/- 1.4 19.4 i 1.7 16A2 16.4 + 1.6 14.3 : 1.3 18.6 - 1.2 17.1 : 0.9 1-2 MILES OFFSITE 1B13 17.7 +/- 1.8 16.1 : 1.1 21.3 +/- 1.4 19.0 1.1 2B3 18.9 +/- 0.8 16.6 4f 0.9 20.8 +/- 0.4 18.8 + 0.6 2B4 17.5 ' 0.2 16.4 4 0.9' 21A.4 1.8 19.1 4 1.1 5B33 16.2 , 1.4 14.6 +1.1 17.5 1.2'2 16.5 4 2.2 7]2 17.3;l:i0.8 15.7 +/- 0.9 18.7 + 1.0 17.4i'- 0.'6 8132 16.94-'1.2 15.1 4. 1.1' 18.1 41.4' 1i.3 + 0.7-9B1- 16.7 4'0.6 15.6 4 1.3 18.9 1:1.6 17.8 l: 1.5 1OB2 - 14.8 + 1.6 12.7 + 1.3 16.7 + 0.8 14.9 + 1.5 0133 17.5 + 1.2 15.2 +/- 0.4 19.2 +/- 1.0 (4) 1OB4, 18.0 +/- 1.6 18.0 +/- 1.5 20.4 +/- 1.0 20.4 1.1 1284 18.3 4 1.0 17.0 + 1.5 20.1 + 1.0 18.6 4 0.7 13B1 18.4 1.6 16.4 + 1.5 19.1 +/- 1.6 18.3 + 1.7 14B3 18.7 +/- 1.8 16.4 +/- 1.5 19.9 +/- 1.0 (4) lSBI 17.1 -1.8 16.0 +/- 1.1 18.9 +/- 1.4 18.0 + 2.4 1682 16.1 +/- 0.8 15.4 + 1.9 19.2 +/- 0.4 17.3 I 0.7 2-3 MILES OFFSITE iC , 21.2 + 1.6 19.4 +/- 0.9 22.4 +/- 1.0 21.7 + 0.7 See the comments at the end of this table.

1-5

TABLE 1-1 ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Rcsults (1) are in mRlstd. qtr (2) +/- 2S (3)

First Quarter Second Quarter Third Quarter Fourth Quarter 01129/03 to 05/01103 042l9/03 to 07/24/03 07/22/03 to 10/23/03 10121/03 to 01/30104 Location 34 MILES OFFSITE ID5 19.9 +/- 0.8 18.6 +/- 0.9 22.5 + 0.0 20.3 +/- 1.1 6D1 18.9 1 1.4 17.9 +/- 1.3 21.3 +/- 1.2 19.8 +/- 0.6 8D3 18.6 +/- 1.2 17.3 +/- 0.6 19.1 +/- 0.8 18.1 +/- 1.1 9D4 18.4 +/- 1.6 17.7 +/- 1.1 20.4 +/- 2.6 18.8 +/- 1.3 IODI 18.5 +/- 1.2 16.7 +/- 1.3 19.9 +/- 1.2 18.3 I 2.4 12D2 21.2 +/- 1.8 19.9 +/- 1.1 22.0 +/- 2.4 21.5 +/- 0.9 14D1 19.9+/- 1.2 17.9 +/- 1.5 20.7 1 2.4 20.3 - 1.7 4-5 MILES OFFSITE 3E1 15.7 +/- 0.6 14.9 + 1.7 18.6 +/- 1.5 16.2 +/- 0.6 4E2 19.2 +/- 1.6 18.8 +/- 0.6 21.7 +/- 1.4 19.6 +/- 0.7 5E2 18.0 +/- 1.4 16.3 +/- 1.5 20.9 +/- 2.0 18.9 +/- 0.7 6E1 20.5 +/- 2.2 20.1 +/- 0.6 21.6 +/- 1.0 20.7 +/- 1.7 7E1 18.7 +/- 2.0 17.5 +/- 0.6 20.5 +/- 1.0 18.9 +/- 1.3 lIEl 16.0 +/- 0.8 14.3 i 0.9 17.4 +/- 1.0 16.1 +/- 0.7 12E1 17.4 +/- 1.8 16.1 +/- 1.3 18.6 + 0.6 17.8 1.1 13E4 20.5 +/- 1.6 20.1 +/- 1.1 22.9 +/- 1.6 22.3 +/- 1.1 5-10 MILES OFFSITE 2F1 17.0 +/- 1.6 17.0 4 1.5 20.2 I 0.4 18.4 +/- 1.7 8F2 17.4 +/- 0.8 16.4 +/- 1.1 18.6 4- 1.0 17.5 +/- 0.7 12F2 19.1 +/- 1.2 17.9 +/- 1.1 20.8 +/- 1.2 20.4 +/- 0.7 15Fi 19.1 +/- 1.2 18.7 +/- 1.3 21.9 +/- 2.0 20.9 +/- 1.7 16F1 20.8 +/- 0.6 19.8 +/- 1.5 22.2 +/- 1.8 20.9 +/- 1.9 Sec the commcnts at thc end of this table.

1-6 (7

( TABLE 1-1

(

ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEIIANNA STEAM ELECTRIC STATION - 2003i Results (1) are in mR/std. qtr (2) +/- 2S (3)

First Quarter Second Quarter Third Quarter I Fourth Quarter ,

01/29103 to 05/01/03 04/29/03 to 07124103 07/22103 to 10/23/03 10/21/03 to 01/30/04 Location 10-20 MILES 3G4 - 19.9 4-1.2 19.7 + 1.7 21.2 + 0.6 21.2 + 0.0 4GI ' 20.0 1 1.4 19.9 +/- 0.6 21.7 +/- 1.8 21.3 + 0.6 6GI 19.5 + 2.0 20.2 + 1.7 23.6 + 1.0 21.9 + 0.6 7GI... I I 17.1 + 1.2 16.5 + 0.9 19.1 + 1.0 18.5 + 0.6 7G2 17.3 1, 1.0 16.9 + 0.4 20.2 4: 0.7 18.8 + 1.9 8GI 15.9 +/- 1.0 14.1 + 1.1 17.3 + 1.8 16.9 1:0.7 12G1 17.2 + 2.0 15.2 + 1.1 17.8 +/- 0.8 18.0 + 0.7

" 12G4 20.3 i- 1.4 17.8 :4 0.9 21.3 4- 1.4 20.4 -1 0.4

,.1, 4.. I , -, :;

. See the comments at the end of this table.,. t, ,  ;, .

i . , ")

3! ! 2. X7- A' ....-

Location Indicator Average (5) 19.6 + 11.8 ' 18.6 i1 12.9 21.9 4: 12.9 20.7 + 12.2 I ., :1* . , ;:

Control Average (5) .,

, I 2 18.4 +/- 4.1 17.5 +/- 3.2 20.3 +/- 3.5 19.6 +/- 2.4 COMMENTS (I) Individual monitor location results are normally the average of the elemental doses of six calcium elements from the two TLDs assigned to each monitoring location.

(2) A standard (std.) quarter (qtr.) is considered to be 91.25 days. Results obtained for monitoring periods of other durations are normalized by multiplying them by 91.25/x, where x is the actual duration in days of the period.

(3) Uncertainties for individual m'onoitoring location results are two standard deviations of the elemental doses of six calcium elements from the two TLDs assigned to each monitoring location, representing the variability between the elemental doses of each of the six TLD elements.

(4) No measurement could be made becuse the TLDs were lost, stolen or damaged. .

(5) Uncertainties associated with quarterly indicator and control averages are two standard deviations, representing the variability between the results of

- the individual monitoring locations. - - -

. I-

, iI I, ' - -. ,  : .'

,i .

l-7

TABLE 1-2 GROSS BETA, TRITIUM, AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/litcr +/- 2S LOCATION COLLECTION DATE TRITIUM GR-BETA OTHER ACTIVITY COMMENTS 6S6 12/30/02 01/27/03 <129 1.9 +/- 1.2 2S7 12/30/02 01/27/03 170

• 87.3 15.9 + 2.9 6S5 01/06/03 01/27/03 <126 3.2

• 1.4 LTAW 01/20/03 <149 4.6

• 1.6 ,

6S6 01/27/03 03/03/03 <135 <2.01 2S7 01/27/03 03/03/03 4770

• 177 8.3 + 2.4 6S5 02/03/03 03/03/03 1310 +/- 114 4.5 + 1.8 LTAW, 02/18/03 246* 90.1 3.7 + 1.6 6S6 03/03/03 03/31/03 <146 4.3

• 1.5

• 2S7 03/03/03 03/31/03 16600 + 307 9.9 + 2.2 6S5 03/10/03 03/31/03 < 149 3.2

• 1.4 LTAW 03/17/03 <147 4.0 + 1.4 6S6 03/31/03 04/28/03 <134 <1.87 6S7 03/31/03 04/28/03 293

• 91.7 7.2

• 2.1 6S5 04/07/03 04/28/03 <123 2.6

• 1.4 LTAW 04/14/03 244 +/- 87.5 2.6 + 1.4 6S6 04/28/03 06/02/03 <141 <1.76 2S7 04/28/03 06/02/03 261

• 95.3 10.9 + 2.4 6S5 05/05/03 06/02/03 <142 3.9 + 1.4 LTAW 05/12/03 225 +/- 92.7 3.7

• 1.6 6S6 06/02/03 06/30/03 <134 <1.88 4.

2S7 06/02/03 06/30/03 3790

• 166 7.1 + 2.1 6S5 06/09/03 06/30/03 <140 3.1

• 1.4 LTAW 06/09/03 192 +/- 95.7 3.6 + 1.6 Comments:

• R-f- '- Appendix F of this report for additional details regarding except(' to SSES Technical Requirements for sampling and analyses. 1-8

TABLE 1-2 GROSS BETA, TRITIUM, AND GAMMA SPECTROSCOPIC ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCifliter + 2S LOCATION COLLECTION DATE TRITIUM GR-BETA OTHER ACTIVITY COMMENTS 6S6 06/30/03 07/28/03 <146 3.0 + 1.5 2S7 06/30/03 07/28/03 182 + 97.6 11.8 + 2.5 6S5 07/07/03 '07/28/03 '<150 2.8 + 1.5 LTAW . 07/14/03 <129 2.8 + 1.3 6S6 07/28/03 08/25/03 <132 4.2 + 1.6 2S7 07/28/03 08/25/03, 9800 + 257 11.8 +/- 2.5 6S5 08/04/03 08/25/03 <128 4.2 + 1.6 LTAW 08/11/03 - ,163 +/-94.2 4.1.+ 1.6 6S6 08/25/03 09/29/03' " 137 +/-71.2 2.8 +/- 1.3 2S7 08/25/03 09/29/03 -135 4 72.2 11.9 +/- 2.3 6S5 09/02/03 .T09/29/03 ' '<114 3.8 +/- 1.4 LTAW,. 09/08/03 ,13 ' 94.2 4.7 '1.5 6S6 09/29/03 11/03/03 <122 3.2 + 1.4 2S7 09/29/03 11/03/03 15800 + 268 13.7 & 2.6 6S5 10/06/03 11/03/03 <114 4.2 1.5 LTAW 10/13/03 ' 147b82.8 3.9 4 1.5 6S6 11/03/03 12/01/03 <124 2.7 + 1.3 2S7 11/03/03 12/01/03 231 +/- 89.3 11.8 + 2.4 6S5 11/10/03 12/01/03 <123 3.1 + 1.3 LTAW. 11/10/03 - 293+86.7 3.9 1 1.3 6S6 12/01/03 12/29/03 <132 2.2 +/- 1.2 2S7 - 12/01/03 12/29/03 <128 12.2 +/- 2.4 6S5 12/08/03 12/29/03 <134 2.4 +/- 1.3 LTAW 12/15/03 <120 3.3 +/- 1.4 Comments:

• Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses. 1_9

TABLE 1-3 IODINE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Rcsults in pCi/liter +/- 2S LOCATION COLLECTION DATE 1-131 COMMENTS '

6S6 12/30/02 - 01/13/03 .01 4 .15 2S7 12/30/02 - 01/13/03 .21 +.29 6S5 01/06/03 & 01/13/03 .24 +.25 6S6 01/13/03-01/27/03 .33 +/-.31 2S7 01/13/03-01/27/03 .21+/-.29 6S5 01/20/03 & 01/27/03 .25 +.23 LTAW 1/20/2003 -.01 .11 6S6 01/27/03-02V10/03 .11*.21 2S7 01/27/03 - 02V10/03 1.33 .58 6S5 02103/03 & 02110/03 .39 *.33 LTAW 2V18/2003 .10+.12 6S6 02110/03 -02/24/03 .72 +/-.30 2S7 02V10/03 - 02124/03 1.61 *.46 6S5 02118/03 & 02124/03 .31 *.29 6S6 02V24/03 - 03/10/03 .64 +/-.41 2S7 02/24/03 - 03/10/03 1.24 *.53 6S5 03/03/03 & 03/10/03 .80 +/-.39 LTAW 3/17/2003 <0.18 6S6 03/10/03 - 03/24/03 .16 +.21 2S7 03/10/03 - 03/24/03 .77 +.42 6S5 03/17/03 & 03/24/03 .30 +.29 6S6 03/24/03 - 04/07/03 .05+/-.12 6S7 03/24/03 -04/07/03 .52 *.32 6S5 - 03/31/03. & 04/07/03 <0.43 LTAW 4/14/2003 .05 +/-.15 Comments:

'n Appendix F of this report for additional details regarding exceptiy- to SSES Technical Requirements for sampling and analyses. 1-10 i(1

TABLE 1-3 IODINE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Rcsults in pCi/liter +2S LOCATION COLLECTION DATE 1-131 COMMENTS 6S6 04/07/03 - 04/21/03 .06 1.17 2S7' 04/07/03-04/21/03' .59 4.36 6S5 04/14/03 & 04/21/03. .10+/-.21 6S6 04/21/03 - 05/05/03 .32 +/-.32 2S7 04/21/03 - 05/05/03 .53 4 .41 -

6S5 04/28/03 & 05/05/03 .14+/-.20 LTAW - 5/12/2003 0.00 .11 6S6 05/05/03 - 05/19/03 .50 +/-.39 2S7 05/05/03 - 05/19/03 1.19+/-.60 6S5 . 05/12/03 &:05/19/03 .06 +/-.20 6S6 05/19/03 - 06/02/03 .61 '.38 2S7 05/19/03 06/02/03 '.50 1.01 6S5 05/27/03 & 06/02/03 .30 +/-.24 6S6 06/02/03 - 06/16/03; .18 +/-.26 6S7 06/02/03- 06/16/03 .48 .38 6S5 06/09/03 & 06/16/03 .28 +/-.28 LTAW 6/9/2003 .16 +/-.25 6S6 06/16/03 - 06/30/03 .47 +/-.36 2S7' 06/16/03- 06/30/03 1.18 4.53 6S5 06/23/03 &-06/30/03 .15 +/-.19 6S6 06/30/03- 07/14/03 .39 +/-.33 2S7 06/30/03 - 07/14/03 .91 .50 6S5 07/07/03 & 07/14/03 .16 .23 LTAW 7/14/2003 .10+/-.22 Comments:

• Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses. I-1l

TABLE 1-3 IODINE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/liter +2S LOCATION COLLECTION DATE 1-131 COMMENTS 6S6 07/14/03 - 07/28/03 .27 +.26 2S7 07/14/03 - 07/28/03 1.15 +.51 6S5 07/21/03 & 07/28/03 .98 +/-.52 6S6 07/28/03-08/11/03 .19L.23 2S7 07/28/03 - 08/11/03 .40+/-.32 6S5 08/04/03 & 08/11/03 .19*.19 LTAW 8/11/2003 .12+/-.23 6S6 08/11/03-08/25/03 .04+/-.19 2S7 08/11/03 -08/25/03 .63 .38 6S5 08/18/03 & 08/25/03 .09 +/-.23 6S6 08/25/03 - 09/08/03 .26 +.29 2S7 08/25/03 - 09/08/03 1.42 +/-.62 6S5 09/02/03 & 09/08/03 .24 +.24 LTAW 9/8/2003 <0.24 6S6 09/08/03 - 09/22/03 .31 *.29 2S7 09/08/03 - 09/22/03 .13 E.25 6S5" 09/15/03 & 09/22/03 .07 +/-.18 6S6 09/22/03 - 10/06/03 .15 +/-.25 2S7 09/22/03 - 10/06/03 <0.45 6S5 09/29/03 & 10/06/03 .02 +/-.16 6S6 10/6/03 - 10/20/03 <0.34 2S7 10/06/03 - 10/20/03 .05 +/-.22 6S5 10/13/03 & 10/20/03 <0.40 LTAW 10/13/2003 .19 .. 27 Comments:

• Ref o Appendix F of this report for additional details regarding exceptiopq to SSES Technical Requirements for sampling and analyses. 1-12

.. j

( (. (D TABLE 1-3 IODINE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 I Rcsults in pCi/liter +2S 1 LOCATION COLLECTION DATE 1-131 COMMENTS 6S6 10/20/03 - 11/03/03 .15 4 .27 2S7 10/20/03 - 11/03/03 1.91 +/-.70 6S5 10/27/03 & 11/03/03 .26 .23 LTAW 11/10/2003 <0.41 6S6 11/03/03 - 11/17/03 .31 4 .51 2S7 11/03/03 - 11/17/03 .68b.60 6S5 11/10/03 & 11/17/03 .24 +/-.44 6S6 11/17/03-12/01/03 .14 +/-.26 2S7 11/17/03-12/01/03 .23 4-.29 6S5 11/24/03'& 12/01/03 .01 +.15 6S6 - 12/01/03-12/15/03 .21 +/-.50 2S7 12/01/03 - 12/15/03 1.02 +/-.64 6S5 12/08/03 & 12/15/03 .32 .45 LTAW 12/15/2003 .33 +/-.45 6S6 12/15/03 - 12/29/03 .15 .46 2S7 12/15/03 - 12/29/03 .92 +/-.78 6S5 12/22/03 & 12/29/03 .27 .45 Comments:

• Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses. 1-13

TABLE 1-4 GROSS ALPHA, GROSS BETA, TRITIUM, IODINE-131 GAMMA* SPECTROSCOPIC ANALYSES OF qRINKING WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/liter +/- 2S LOCATION COLLECTION DATE GR-ALPIIA GR-BETA TRITIUM OTHER ACTIVITY " COMMENTS 12H2 12/30/02 - 01/27/03 <1.24 1.86+/-.9 <127 12H2 01/27/03-03/03/03 <1.62 2.7+/-1.4 <135 12112 03/03/03 -03/31/03 <1.30 2.19+/- 1.3 <142 12112 04/07/03 - 04/28/03 <1.74 <1.87 <130

• 12H2 04/28/03 - 06/02/03 <1.87 <1.90 <141 12112 06/02/03 - 06/30/03 <1.53 2.04 +/- 1.3 <134 12112 06/30/03 - 07/28/03 <1.90 <2.01 <133 12H2 07/28/03 - 08/28/03 <1.06 3.54+/- 1.4 <146 12H2 08/25/03 - 09/29/03 <1.07 2.29 1.3 193 +/- 72 12H2 09/29/03 - 11/03/03 <1.78 4.26 1.4 <119 12H2 11/03/03 - 12/01/03 <1.55 <1.57 149 +/-76 12H2 12/01/03 - 12/29/03 <1.68 2.01 +/- 1.2 <128 Comments:

• Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses.

1-14 a

C (.

TABLE 1-5 GROSS BETA AND GAMMA* SPECTROSCOPIC ANALYSES OF FISH SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (wet) + 2S LOCATION SAMPLE TYPE COLLECTION DATE K40 COMMENTS ND Smallmouth Bass 04/28/03 - 04/28/03 4.15 + .37 ND Shorthead Redhorse 04/28/03 - 04/28/03 4.39 + .43 IND Channel Catfish 04/29/03 - 04/30/03 3.89 4 .33 2H Smallmouth Bass 05/12/03 - 05/12/03 3.92 +.28 2H Shorthead Redhorse 05/12/03 - 05/12/03 3.20 + .26 2H Channel Catfish 05/12/03 - 05/13/03 3.49 4 .25 IND Channel Catfish 10/07/03 - 10/08/03 3.69 +.33 IND Smallmouth Bass 10/08/03 - 10/08/03 3.99 4-.37 ND White Sucker. 10/08/03 - 10/08/03 1.30 4 .14 2H Channel Catfish 10/15/03 - 10/16/03 3.44 1 .37 2H Smallmouth Bass 10/16/03 - 10/16/03 1.30k .24 2H White Sucker 10/16/03 - 10/16/03 3.58 - .24 LTAW Largemouth Bass 10/20/03 - 10/20/03 3.671 .30 -

1-15

TABLE 1-6 GAMMA* SPECTROSCOPIC ANALYSES OF SHORELINE SEDIMENT SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Rcsults in pCi/gm (dry) + 2S LOCATION COLLECTION DATE K-40 Cs-137 Ra-226 TH-228 OTHER ACTIVITY 2B 5/20/2003 17.3 I .8 .11 +/-.03 2.45 4 .65 4.74 +.67 7B 5/20/2003 15.8 +/-.5 .10 +/- .02 2.86 +/- .59 3.56 + .54 12F 5/20/2003 11.8 +/- .8 .09 + .04 2.12 4 .85 3.34 + .82 LTAW 5/20/2003 15.8 4 .8 <.03 1.96 +/-.61 3.21 +/-.60 2B 10/27/2003 7.22 +/- .24 .04 +/- .01 .75 +/-.16 1.28 + .18 7B 10/27/2003 13.6 +/-.5 .07 +/- .02 2.36 :.46 3.47 +/-.43 12F 10/27/2003 10.4 +/- .4 <.02 2.17 +/-.40 2.46 + .38 LTAW 10/27/2003 14.7 +/-.4 <.01 2.18 +/-.37 3.23 4 .41 I-16 c- c-U

C C TABLE 1-7

(

TRITIUM AND GAMMA* SPECTROSCOPIC ANALYSES OF GROUND WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/liter + 2S LOCATION COLLECTION DATE TRITIUM OTHER ACTIVITY _

12F3 1/20/2003 <145 2S2 1/20/2003 <149 4S4 Treated 1/20/2003 <140 12F3 2/18/2003 <135 2S2 2/18/2003 <137 4S4 Treated 2/18/2003 178 + 87.3 12F3 3/17/2003 <143 2S2 3/17/2003 <141 4S4 Treated 3/17/2003 <143 12F3 4/14/2003 <131 2S2 4/14/2003 167 83.1 4S4 Treated 4/14/2003 142 + 83.2 5/12i2003 <136 2S2 - 5/12/2003 <136' 4S4 Treated 5/12/2003 <137 12F3 6/9/2003 <146 2S2 6/9/2003 <145 4S4 Treated 6/9/2003 <146 12F3 7/14/2003 <147 2S2 7/14/2003 <137 4S4 Treated 7/14/2003 <143 12F3 8/11/2003 <138 2S2 8/11/2003 <140 4S4. I Treated - 8/11/2003 <139 I .

1-17

TABLE 1-7 TRITIUM AND GAMMA* SPECTROSCOPIC ANALYSES OF GROUND WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/litcr +/- 2S LOCATION COLLECTION DATE TRITIUM OTHER ACTIVITY 12F3 9/8/2003 <139 2S2 9/8/2003 <138 4S4 Treated 9/8/2003 193 +/- 89.6 12F3 10/13/2003 <125 2S2 10/13/2003 <124 4S4 Treated 10/13/2003 <122 12F3 11/10/2003 <127 2S2 11/10/2003 <122 4S4 Treated 11/10/2003 <125 12F3 12/15/2003 <121 2S2 12/15/2003 <120 4S4 Treated 12/15/2003 <126 1-18 c C (__

C )

TABLE 1-8 -

GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION - 20031 Results in E-03 pCi/Cu. M. + 2S I COLLECTION ' I MONTH DATE 6G1 '- 8G1 3S2 12E1 12S1 - 13S6 ' COMMENTS JAN 1/2/03 - 1/8/03 12.8 + 2.2 11.1' 2.3 14.6 + 2.8 13.6 +2.5 13.1 I 2.6 10.8 I 2.3 1/8/03- 1/15/03 14.3 + 2.1 14.2 + 2.2 13.8 + 2.3 15.9 4 2.2 13.7 4 2.2 16.0 + 2.3 1/1503'- 1/22/03 14 +/- 2.2 18.6 + 2.5 20.6 + 2.8 18.7 + 2.5 17.6 + 2.5 16.3 I 2.4 1/22/03 1/29/03 ' 14.1 +/- 2.3 14.6 + 2.3 17.3 I2.6 15.7 + 2.3 18.2 ' 2.5 17.1 + 2.4

. . i.

FEB 1/29/03 '-215i03 13.8 b2.3 16.2 2.4 15.7 + 2.3 15.2 I 2.4 16.7 + 2.6 15.2 + 2.3 215/03 - 2/12iO3 14.8 ' 2.2 16.2 + 2.4 17.89 2.4 17.5 4 2.3 17.8 4 2.4 18.1 + 2.4 2/12/03 - 2/19/03 9.9 b 2.0 12.2 + 2.1 14.2 + 2.2 14.2 + 2.2 14.9 4 2.2 14.1 + 2.2 2/19/03 - 2/26/03 12.6 + 2.3 17.7 ': 2.5 19.2 +2.3 16.0 I 2.4 14.9 + 2.4 16.1 I 2.4 MAR 2/26/03 - 3/5/03 - 14.5 ' 2.3 18.89 2.6 19.7 + 2.6 17..9 +/- 2.! 5 18.1 *2.5 19.5 +/- 2.6 3/5/03 - 3/12/03 216 I: 2.7 19.4- 2.5 25.9 1 2.8 18.2 4 2.' 5 23.6 + 2.8 18.6 4 2.5 3/12/03 - 3/19/03 18.3 2.5 17.8 2.4 17.6 2.4 17.9 4 il 4 18.4 *2.6 18.4 + 2.5 3/19/03'- 3/26/03' 10.4 + 2.1 10.5 ' 2.0 12.6 2.5 9.8 ' - 2.( 11.82.2 I- 11.7 *2.1 3/26/03 -4/2/03 9.5 ' 2.0 11.6 ' 2.0 10.5 . 10.4 *2.t 0 10.7 *2.0 12.6

• 2.1 F .:

APR' 4/2/03 - 4/9/03: 7.6 " 1.9 9;6 2.0- 9.5 + 2.0 10.0 ' + 2.( 9.9 2.1 9.6

• 2.0 4/9/03 - 4/16/03 13.0 + 2.2 15.9 + 2.3 14.3 + 2.1 14.7 +/- 2.,2 12.7 *2.1 14.3 : 2.2 4/16/03 - 4/23/03 10.5 b2.0 13.6 2.1 15.0 + 2.3 12.8 + 2. 1 14.3 2.2 13.3 +/- 2.1 4/23/03 - 4/30/03 11.3 42.0 14.7 2.2 15.3 +/-2.3 11.4 +2.4 D 13.3 + 2.2 12.8 +/- 2.1 MAY 4/30/03 5/7j03 9.4 ' 2.1 -' 10.5 4- 2.1 13.5 ' 2.4 10.5 + 2.:2 11.1 + 2.3 11.2 + 2.2 5/7/03 - 5/14/03' 9.3 2.1 7.3 + -1.9 11.2 +2.2 8.9 I 2.1, 9.3 *2.1 7.5 + 1.9 5/14/03 - 5/21/03 7.9 4f 2.0 9.1 + 2.0 6.6 + 1.9 6.7 + 1.'9 7.0 *2.0 8.4

• 2.0 5/21/03 - 5/28/03 3.2 +/- 1.5' 4.1 4- 1.5 4.9 + 1.7 3.6 i 1.I5 5.2 *1.7 4.9

• 1.6 JUN 5/28/03 - 6/4/i03 7.0 d 2.1 8.5 b2.3 10.6 + 2.3 8.7 4 2. 1 9.2 *2.2 8.5

• 2.1' 6/4/03 - 6/11/03 5.8 +/- 2.2 10.5 *2.2 10.0 4 2.1 7.1 + 1.I8 8.5 *2.0.! 7.9 +/- 1.9 6/11/03 - 6/18/03 7.0 42.1 9.4 42.1 12.5 +/- 2.2 9.3 + 2.'0 11.0 *2.2 10.3 +/- 2.0

- 6/18/03 - 6/25/03 10.5 42.1 11.4 +/-2.2 9.7- + 2.1 -10.6 + 2. 1 10.4 *2;1 11.7 +/-2.2 6/25/03 - 7/2/03 16.9 + 2.6 23.5 + 3.0 17.3 + 2.6 18.1 + 2. 8 21.9 *2.8 21.9 +/- 2.8 Comments:

• Refer to Appendix F of this report for additional details regarding exceptions to SSES Technical Requirements for sampling and analyses. 1-19

TABLE 1-8 GROSS BETA ANALYSES OF AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in E-03 pCi/Cu. M. +/- 2S COLLECTION MONTH DATE 6G1 8G1 3S2 12E1 12S1 13S6 COMMENTS JUL 7/2/03 - 7/9/03 17.4

• 2.6 17.7 +/- 2.6 21.4 + 2.7 20.8

• 2.7 23.1 +/- 2.9 20.4 I 2.7 7/9/03-7/16/03 9.2 *2.0 11.6 + 2.1 11.5 +/- 2.1 12.0 *2.1 10.1

• 2.0 10.4 + 2.0 7/16/03 - 7/23/03 13.3

• 2.5 8.4 + 2.0 12.0 +/- 2.3 13.6 *2.4 12.1 +/- 2.5 11.5 I 2.3 7/23/03 - 7/30/03 12.4 *2.4. 12.1 + 2.2 14.9 +/- 2.4 14.5 *2.4 14.9 +/- 2.5 13.5 I 2.4 AUG 7/30/03-8/6/03 9.3 *2.1 8.9 +2.0 11.7 +/- 2.2 9.4 *2.1 12.4 *2.3 11.3 *2.2 8/6/03 - 8/13/03 10.8

• 2.3 11.8 + 2.3 12.4 + 2.3 13.2 + 2.3 11.2 *2.6 11.2 +/- 2.3 8/13/03 - 8/20/03 15.3 +/- 2.4 19.4 +/- 2.6 16.7 I 2.4 17.9 + 2.5 16.8

• 2.5 16.4 +/- 2.5 8/20/03 - 8/27/03 19.9 +/- 2.7 20.7 +/- 2.8 22.8 +/- 2.8 21.9 +/- 2.7 20.4 *2.9 20.4 + 2.8 8/27103-9/3/03 10.2 +/-2.1 11.4 +/-2.2 11.9 +/-2.1 10.9 *2.1 10.7 *2.1 11.7 +/- 2.2 SEP 9/3/03 - 9/10/03 13.4 +/- 2.2 12.6 +/- 2.2 12.8 +/- 2.1 13.5 +/- 2.2 15.2 +/- 2.3 13.4 +/- 2.2 9/10103-9/17/03 11.9 *2.20 11.0 +/-2.1 15.4 *2.2 11.8 *2.1 12.5 *2.2 13.2 *2.2 9/17/03 - 9/24/03 16.7 +/- 2.8 16.7 +/- 2.7 13.2 +/- 2.5 17.4 +/- 2.7 13.4 +/- 2.5 16.0

• 2.7 9/24/03 - 10/1/03 12.2 +/- 2.8 11.2 +/- 2.7 12.3

• 2.7 13.3 +/- 2.7 12.9 +/- 2.7 13.2

• 2.8 OCT 10/1/03 - 10/8/03 13.3 +/- 2.4 12.0 + 2.2 12.1

• 2.3 10.2 +/- 5.4 12.7

• 2.3 12.2 +/- 2.3 10/8/03 - 10/15/03 30.9 + 3.6 31.0 +/- 3.5 30.2

• 3.4 29.9 +/- 3.3 31.7 +/- 3.5 26.6 +/- 3.3 10/15/03 - 10/22/03 16.3 +/- 2.6 16.8 +/- 2.5 18.0

• 2.6 17.3

• 2.5 19.1 +/- 2.6 20.7 4* 2.8 10/22/03 - 10/29/03 12.6

• 2.2 10.0 + 2.0 11.9 *2.1 14.6 *2.5 14.5 +/- 2.2 14.3 +/- 2.3 NOV 10/29/03 - 11/5/03 21.1 +/- 2.8 23.3 +/- 2.8 30.0 +/- 3.1 24.6 +/- 2.8 22.0 +/- 2.7 24.1 +/- 2.9 11/5/03 - 11/12/03 10.7 + 2.2 14.1 +/- 2.4 15.3 +/- 2.2 15.3 +/-2.3 16.3 +/- 2.4 15.1 4 2.4 11/12/03 - 11/19/03 13.2 *2.4 21.1 + 2.7 19.0 *2.5 16.1 +/- 2.4 17.2 4 2.6 17.2

• 2.5 11/19/03 - 11/26/03 19.3 +/-2.8 18.9 +/- 2.7 24.1

• 2.8 23.3 +/- 2.7 25.0 +/- 2.9 22.4 +/- 2.9 11/26/03 - 12/3/03 11.1 + 2.3 12.8 +/- 2.3 13.4

• 2.5 14.3 +/- 2.3 12.8 +/- 2.3 12.8 +/- 2.4 DEC 12/3/03 - 12/10/03 10.1 +/- 2.1 12.1 +/- 2.1 11.3

• 2.1 11.7

• 2.0 12.4 +/- 2.1 10.1 +/- 2.0 12/10/03 - 12/16/03 9.1 +/- 2.3 9.0 +/- 2.1 11.0 +/- 2.3 9.3 *2.1 9.5 +/- 2.3 9.5 +/- 2.2 12/16/03 - 12/23/03 13.7 + 2.3 13.0 i 2.2 13.5 + 2.3 13.6

• 2.2 14.9 +/- 2.3 15.8 +/- 2.4 12/23/03 - 12/30/03 14.1 +/- 2.3 13.4 + 2.1 18.5 +/- 2.5 16.8

• 2.3 16.9 +/- 2.3 18.3 +/- 2.4 Comments:

• Relo Appendix F of this report for addiional details regarding except' to SSES Technical Requirements for sampling and analyses. 1-20

( (.

TABLE 1-9 C

GAMMA* SPECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in E-03 pCi/Cu. M. + 2S LOCATION COLLECTION DATE Be-7 K-40 OTIIER ACTIVITY

. . . .I 6G1 01/02103 - 04/02/03 91.1 + 10.3 <5.01 8G1 01/02/03 - 04/02/03 93.4 +/- 7.03 <1.97 3S2 01/02/03 - 04/02/03 106+/- 8.29 <3.05 12EI 01/02/03 -04i/2/03 109 + 8.69 <1.78 12S1 01/02/03 - 04/02/03 106 + 7.54 <6.66 13S6 01/02/03 - 04/02/03 99.1 +/- 7.15 <6.30 6GI 04/02.03 -07/2/03 74.7 +/- 9.41 4.16 +/- 2.31 8GI 04/02103 - 07/2/03 88.5 +/- 9.42 <1.78 3S2 04/02/03 - 07/2/03 86.6 +/- 10.4 <3.40 12E1 04/02/03 - 07/2/03 91.4 +/- 8.50 <2.03 12S1 l 04/02/03;- 07/2/03 83.2 +/- 12.2 <1.99 13S6 04/02/03 - 0712/03 *111 +/- 11.1 <5.17 I . - . 7 601 07/02/03 - 10/01/03 89.2 +/- 8.23' <2.81 8G1 07/02/03 - 10/01/03 83.8 +/- 7.33 <7.31 3S2 07/02/03 - 10/01/03 101 +/-2.47 <.794 12EI 07/02/03 - 10/01/03 86.7 +/- 9.03 <3.27 12SI 07/02/03 - 10/01/03 97.7 +/- 8.28 <2.22 13S6 07/02/03 - 10/01/03 85.5 +/- 9.95 <8.26 6GI 10/01/03 - 12/30/03 70.3 +/- 6.57 <2.80 8GI 10/01/03 - 12/30/03 66.3 +/- 7.22 <7.83 3S2 10/01/03 - 12/30/03 69.3 +/- 5.85 <2.02 12EI 10/01/03 - 12/30/03 74.9 +/- 7.10 <2.60 12S I 10/01/03 - 12/30/03 76.5 +/- 4.33 <1.38 13S6 10/01/03 - 12/30/03 67.0 +/- 6.96 <1.60 1-21

TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/liter +/- 2S LOCATION COLLECTION DATE K-40 OTHER ACTIVITY COMMENTS IOGI 01/07/03 1480 120 IODI 01/06/03 1470 120 10D2 01/06/03 1410 120 12B2 01/06/03 1390 130 IOGI 02/03/03 1520 110 lODI 02/03/03 1540 4 130 10D2 02/03/03 1280* 140 12B2 02/03/03 1400*150 IOGI 03/03/03 1390X110 IODI 03/03/03 1330 130 10D2 03/03/03 1420 110 12B2 03/03/03 1400 110 IOGI 04107/03 1530* 110 IODI 04/07/03 1360* 130 IOD2 04/07/03 1220* 140 12B2 04/07/03 1330 150 IOGI 04/21/03 1480* 110 IODI 04/21/03 1350* 130 IOD2 04/21/03 1440* 160 12B2 04/21/03 1360* 150 lOGI 05/05/03 1470+ 110 IODI 05/05/03 1430* 160 10D2 05/05/03 1310

• 110 12B2 05/05/03 1530 +/- 140 IOGI 05/19/03 1470

• 130 lODI 05/19/03 1460* 110 c C Q 1-22

( C( C TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCifliter +/- 2S LOCATION COLLECTION DATE K40 OTHER ACTIVITY COMMENTS 10D2 05/19/03 14801 110 12B2 05/19/03 13501: 110 10GI 06/04/03 1340+ 110 10DI 06/04/03 1390 +/- 140 10D2 06/04103 1190b 160 12B2 06/04103 1390 +/- 120 lOGI 06/1 03' 1400+/- 160 10DI 06/19/03 1460 160 10D2 06/19/03 1400 150 12B2 1350 150.

1,, , j 16, "I...

07106/03 13501+/-130 10DI 13401: 130, I0D2 07/06/03) 1420 110.,

12B2 1500 110 lobi 07/21103 1470 110 10DI 07/21/03 1340 150 IOD2 07/21/03 1550 1 160 12B2 07121/03 1520:+ 170

.' . " , ') . I 1-23

TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/liter +/- 2S LOCATION COLLECTION DATE K40 OTHER ACTIVITY COMMENTS IOGI 08/04/03 1360+/-180 IODI 08/04/03 1330+110 10D2 08/04/03 1500+/-120 12B2 08/04/03 14104170 IOGI 08/18/03 1420+/-160 IODI 08/18/03 1340+/-150 10D2 08/18/03 1410 110 12B2 08/18/03 1330+/-110 IOGI 09/03/03 1484+/-94 IODI 09/03/03 1380+/-160 IOD2 09/03/03 1380+110 12B2 09/03/03 1471 +/- 95 IOGI 09/18/03 14904110 lODI 09/18/03 1410+/-140 1OD2 09/18/03 1390+/-110 12B2 09/18/03 1370+/-110 lOGI 10/05/03 1470 110 1ODI 10/05/03 1330 130 IOD2 10/05/03 1350+/- 150 12B2 10/05/03 1200+/- 150 C c Qo 1-24 U

(: (l (7 TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/liter + 2S LOCATION COLLECTION DATE K40 OTHER ACTIVITY COMMENTS IOGI 10/20/03 1420 i 120 10DI 10/20/03 1450 + 140 10D2 10/20/03 1380 + 160 12B2 10/20/03 1250H150 IOGI 11/03/03 1350b 110 10DI 11/03/03 1550+ 160 10D2 11/03/03 1360 4 150 12B2 11/03/03 1380 4 150 IOGI 12/08/03 819 + 86 10DI 12/08/03 1361 +/-58 10D2 12/08/03 1452+62 12B2 12/08/03 940ki94 ii .

1-25

TABLE -llI GAMMA* SPECTROSCOPIC ANALYSES OF SOIL SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/gm (dry) +/- 2S LOCATION COLLECTION DATE K-40 Cs-137 Th-228 8GI TOP 9/15/2003 11.0 4 1.1 0.17 +.05 0.90 +.14 8GI BOT 9/15/2003 10.2 4 1.1 0.097 4f .053 0.73 .13 3S2TOP 9/15/2003 14.7 1.1 0.030k.035 1.04+.13 3S2 BOT 9/15/2003 16.2 1.2 0.049 4 .039 1.001.13 12SI TOP 9/15/2003 10.3k 1.0 0.0961.047 0.824.12 12SI BOT 9/15/2003 12.5 + 0.8 0.076 4 .029 0.84 +.85 13S6 TOP 9/15/2003 18.2 4 0.9 <0.042 1.04*F.95 13S6 BOT 9/15/2003 14.3 L1.0 0.027 +/- .024 0.95 + .11

(_ (_ C 1-26 a

C TABKIE1-12 C GAMMA* SPECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS. AND VEGETABLES)

SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/grn (wet) + 2S LOCA.TION SAMPLE TYPE COLLECTION DATE K-40 OTHER ACTIVITY 1 1D2' Potato 08/21/03 4.66 +.19

.I11F2 Potato 09/04/03 4.47 +.29

1. I .. i

! ,- >i'4 I'- , -

Comments:

• Refer to Appendix F of this report for, additional details regarding exceptions to SSES Technical Requirements for. sampling and analyses.

1-27

TABLE 1-13 TYPICAL

• MINIMUM DETECTABLE CONCENTRATIONS OF NUCLIDES SEARCHED FOR BUT NOT FOUND BY GAMMA SPECTROMETRY IN THE VICINITY OF SUSQUEHANNA STEAM ELECTRIC STATION, 2003

_ . _ _ . , A . . __ .

Fish A _ _ _ . ,

Sediment Surface Water Ground Water Potable Water Nuclide (pCi/g wet) (pCi/g dry) (pCi/I) (pCi/A) (pCi/I)

Mn-54 0.019 0.028 2.9 4.1 1.7 Co-58 0.023 0.035 2.1 4.6 1.8 Fc-59 0.050 0.110 5.1 10.2 8.3 Co-60 0.015 0.028 3.3 5.3 2.5 Zn-65 0.028 0.071 7.8 14.4 6.7 Zr-95 0.020 0.070 6.4 7.8 5.4 Nb-95 N/A N/A 4.3 5.8 3.2 Ru- 103 N/A N/A 4.9 5.3 2.6 1-131 0.100 0.173 15.4 8.1 13.2 Cs-134 0.010 0.032 2.3 5.2 2.6 Cs-137 0.015 0.033 2.4 4.8 2.5 Ba-140 0.300 0.310 7.8 9.0 9.2 La-140 0.040 0.100 12.1 10.1 10.2 Ce-141 N/A N/A 6.8 7.8 6.8 Air Particulate Milk Fruit/Veg. Soil Nuclide (10-3 pCi/m3) (pCi/A) (pCi/g wet) (pCi/g dry)

Mn-54 0.33 5.5 0.008 0.037 Co-58 0.51 5.1 0.008 0.039 Fc-59 2.31 12.4 0.032 0.993 Co-60 0.28 5.7 0.009 0.055 Zn-65 0.75 13.4 0.025 0.176 Zr-95 0.88 7.7 0.016 0.995 Nb-95 N/A 6.1 N/A 0.071 Ru-103 N/A 5.2 N/A 0.051 1-131 70.3 8.2 0.019 0.097 Cs-134 0.27 4.8 0.007 0.057 Cs-137 0.29 4.4 0.008 0.047 Ba-140 - 36.2 6.7 0.055 0.255 La-140 11.5 7.8 0.016 0.11 Ce-141 N/A 8.1 N/A 0.078 1-28 Ci U

APPENDIX J PERFORMNEUMR .& -

FRH I...........

- , ) 'A -.

ENiRoNMETAL SAMPLE-AMEDI 03

.j. -i ' , C F k'a'PW' E~~~~-R NVI'N-ENGINP.-E ANPENV. E -D O0. A LABORATORY

.,-.TELEDYNERto EG't A~

.  :, , -r.,,',i 2003 Radiological Environmental Monitoring Report J- I

II Appendix J The data in the tables that follow show how well Framatome ANP Environmental Laboratory and Teledyne Brown Engineering Environmental Services (TBE) performed in the analysis of radioactively spiked media. Tables J-1 through J-5 provide the performance results for '

Framatome ANP. Tables J-6 through J-10 provide the performance results for TBE. In addition to the Analytics' spikes analyzed as part of PPL's REMP Laboratory Spike Program (Tables J-3 and J-8), Framatome ANP and TBE analyzed spikes procured independently from Analytics as part of their respective Quality Control Spike Programs (Tables J-2 and J-7), as well as spikes prepared as part of the following programs:

1. The Proficiency Testing Program of Environmental Resource Associates (Tables J- Iand J-6)

2. The Quality Assessment Program of DOE's Environmental Measurements Laboratory (EML)

(Tables J-4 and J-9)

3. TheMixedAnalyte-Perforimance Evaluiatioin'Pro-g-ram (MAPEP)-of the DOE (Tables J-5 and - - ---- -

J-10)

It should be noted that program #1 above only provides spiked water for analyses. No other media are included in the spikes provided by this program. Also, it should be noted that the levels of activity in spikes of different media prepared for program #2 tend to be relatively high.

They are relatively high compared to the levels of activity in the spikes prepared by Analytics as part of its Environmental Cross Check Program and for PPL's REMP Laboratory Spike Program.

The following characteristics are important for the spiked environmental media:

1. When practical, the level of activity in, at least, some of the spiked environmental media should be within the range between required analysis sensitivities for the SSES REMP and the Reporting Levels, if applicable, of the NRC.

2. The spikes should be preserved in a manner as similar as possible to the way that actual samples of those media are prepared.

3. The variety of radionuclides with which environmental media are spiked should be as extensive as practical, including as many as of the activation and fission products that could be detected in the vicinity of the SSES as reasonable.

The spiked environmental media prepared by Analytics according to the requirements of PPL's REMP Laboratory Spike Program are intended to incorporate characteristics #1, #2, and #3 to the greatest degree that is practical.

J-2 2003 Radiological Monitoring Report Environmental Monitoring Radiological Environmental Report J-2

Appendix J The criteria for the acceptability of the analyses results for the spikes prepared as part of the PPL REMP Laboratory Spike Program (Tables J-3 & J-8) have been established by PPL. They are based on criteria that were originally developed by the NRC. The NRC bases these criteria on an empirical relationship that combines prior experience and accuracy needs. As the resolution of the measurement process improves (relative measurement uncertainty becomes smaller), the criteria for determining acceptability become tighter. Conversely, as the resolution of the process becomes poorer (relative measurement uncertainty becomes bigger), the criteria are widened.

The criteria for acceptability of DOE programs (EML's and MAPEP's programs - Tables J-4, J-5, J-9 and J-10) are based on control limits based on percentiles of historic data distributions.

Note that comment numbers at the extreme right side of the tables denote unacceptable results in Tables J-1 through J-10. Discussions relevant to these comment numbers follow the presentationssof the-data:,as applicabled.

Radionuclide concentration results not available (due to loss of spectrum by Analytics) and therefore not included in Tables J-3 and J-8 for the following:

Analytics Sample Numbers: E3980-186 and E3976-186 (spiked milk).

2003 Radiological Environmental Monitoring Report J-3 J-3 2003 Radiological Environmental Monitoring Report

( TA J -1 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)l

(

PROFICIENCY TESTING PROGRAM - 2003 1 FRAMATOME ANP ENVIRONMENTAL SERVICES LABORATORY (Page I of 2)

Identification ERA Known Framatome FramatomelERA IERA No. Medium Units Nudide Result (a) Results (a) Ratio Contrl Limits (b) Evaluation Rad-52 Water pai/I Gross Alpha 37.6 28 0.74 21.3-53.9 Acceptable pCi/I Gross Beta 8.55 8.97 1.05 0.00-17.2 Acceptable pCi/i Sr-89 15.9 13 0.82 7.24-24.6 Acceptable pcifl Sr-90 9.03 8.74 0.97 0.37-17.7 Acceptable pCi/I Ba-133 19.5 17.9 0.92 10.8-28.2 Acceptable pCi/I CO60 37.4 36.6 0.98 28.746.1 Acceptable Cs-134 17.8 17.9 1.01 9.14-26.5 Acceptable pci/I Cs-137 44.2 45.4 1.03 35.5-52.9 Acceptable Zn-65 60.3 60 1.00 49.9-70.7 Acceptable pCi/I Nat. Uranium 53.7 56 1.04 4.4-63.0 Acceptable Rad-53 Water pCill H-3 1250.0 1080.0 0.86 678-1820 Acceptable pCi/I 1.131 20.8 21.4 1.03 15.6-26.0 Acceptable Rad-54 Water pCi/I Gross Alpha 65.1 70.4 1.08 36.9-93.3 Acceptable pCi/I Gross Beta 31.6 31.9 1.01 22.940.3 Acceptable pCi/I Sr-89 58.8 55.5 0.94 50.1-67.5 Acceptable Sr-90 20.6 18.7 0.91 11.9-29.3 Acceptable pCi/I . Ba-133 20.7 19.9 0.96 12.0-29.i Acceptable Co-60 I37.4., 37.4 1.00 - 28.746.1 Acceptable Cs-134 32.6 31.0 0.95 23.941.3 Acceptable pCi/I Cs-137 .44.3 47.0 1.06 35.6-53.0 Acceptable pCi/i Zn-65 60.2 61.3 1.02 49.8-70.6 Acceptable Nat. Uranium 11.4 11.5 1.01 6.20-16.6 Acceptable

.O."

Rad-5! Water. pai/I 131 28.2.' 28 0.99 23.0-33.4 Acceptable pCi/I Tritium 14300 14800 1.03 llW0-16800 Acceptable J4 (a) Results are the average of three measurements, reported in units of pCi/. .  :-

(b) Per guidelines of the EPA'S National Standards for Water Proficiency Testing Criteria Document, December 1998.

TABLE J-1 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)

PROFICIENCY TESTING PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL SERVICES LABORATORY (Page 2 of 2)

COMMENTS The equations used to calculate the sample activity were all independently verified to be correct. No problems were identified with sample documentation. The chemists were trained to process strontium samples expeditiously and to utilize the full 15-day yttrium-90 in-growth period.

2 Equipment problem with iodide probe identified. When sample was reanalyzed with new iodide probe, mean result was 14.5 pCi/L, a bias of -1.4%.

3 No problems identifed via test data evaluation using internal calibrations. The grand mean of the RAD-50 test compared favorably (1% bias) with the Frarnatome ANP result yet indicated a significant bias from the ERA stated known. No actions were taken based on the favorable QC history for Cs-137.

l-5

(.. .C(

( TAL.J-2 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 I

FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page I of 4)

Analytics Identifcatlon Calculated Framatome Framator ndAnalytlcs Month/Year No. Medium Units Nucide Results I Results RRatlo March-03 E3600-162 Milk pCi/l I1 31U. 74 72.5 0.98 pCi/I 1-131 74 73 0.99 pCi/I Cc-141 173 170 0.98 pCi/I Cr-51 246 244 0.99 Cs-134 90 86 0.96 Cs-137 200 196 0.98 pCi/I Co-58 47 44 0.94 pCi/I Mn-54 64' 61 0.95 pCi/I Fe-59 47 47' i.00 pCi/I Zn-65 93 96 1.03 pCi/I Co60 162 162 1.00 Wae p7iII March-03 E3597- 62 Gr. Alpha 53 55 1.04 Water pCifl E3597-162 Or. Beta 186 146 0.78 Water pCi/I E3598-162 1-131LL* 70 67.7 0.97 Water pCi/I 1-131 70 68 0.97 pCi/I Ce 141 168 163 0.97 pCi/I Cr-51 238 243 1.02 pCi/I Cs-134 88 83 0.94 pCi~l Cs-137 195 188 0.96 pCi/I Co-58 42 44 1.05 pCi/I Mn-54 63 61 0.97 pCi/i Fe-59 46 48 1.04 pCi/I Zn-65 90 88 0.98 pCi/I Co-60 157 156 0.99

• 1-131 LL= radiochemical separation analysis J-6

TABLE J-2 ANALYTICS ENVIRONMENTAL RADIOACnVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALlTY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 2 of 4)

Analytics Identification Calculated Framatomie Framnatoi De/Analytics MonthtYea r No. Medium Units Nuclide Results I Results RRatio March-03 E3599-162 AP Falter pCi Gr. Alpha 49 52 1.06 pCi Or. Beta 148 157 1.06 March-03 E3601-162 Milk pCi/I Sr-89 133 121 0.91 pCi/I Sr-90 12 13 1.08 March-03 E3608-162 Water pCi/I Sr-S9 114 104 0.91 pCi/I Sr-90 10 II 1.10 June-03 e3704-162 Water pCi/I H-3 11953 10643 0.89 Junc-03 e3705-162 AP Filter pCi Gr. Alpha 21 20 0.95 pCi Gr. Beta llS 116 1.01 June-03 E3706-162 AP Filter pCi Ce-141 154 149 0.97 pCi Cr-51 130 134 1.03 pCi Cs-134 56 54 0.96 pCi Cs-137 125 135 1.08 pCi Co-58 50 53 1.06 pCi Mn-54 101 110 1.09 pCi Fe-59 54 60 1.11 pCi Zn-65 99 110 1.11 pCi Co-60 72 71 0.99 June-03 E3707-162 AP Filter pCi Sr-89 87 78 0.90 pCi Sr-90 24 - 24 1.00 J-7 C. C (~.,

CI

( TABL J-2 C

ANALYTICS ENVIRONMENTAL RADIOACTIViTY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 3 of 4)

I Analytics Identifncation Calculated Fra nmatorne Framatome/Analytics Month/Year No. Medium Units Nuelide Results I R Results Ratio June-03 E3153-162 Milk pCi/ 1-131 103 109 1.06 pCi/ 1-131 LL 103 104 1.01 pCiNl Ce 141 283 283 1.00 pCiAI Cr-SI 239 239 1.00 pCi/I Cs-134 103 98 0.95 pCi/I Cs-137 230 232 1.01 pCi/I pcin Co-58 93 92 0.99 Pain Mn-54 186 186 1.00 Fe-59 99 100 1.01

.Pain Zn-65 181 181 1.00 Co-60 li2 134 1.02, W.

ae pc~in September-03 E3866-162 Water guin Gross Alpha Gross Beta 36 246 37 242 1.03.

0.98 September-03 E3867.162 Water pCillI 1-131' 76 69 0.91 1-13ILL 76 78 1.03 Ce-141 81 78 0.96.

pcvl Pei/,: Cr-51 221 198 0.90 pCi/I Cs-134 113 108 0.96 p.Ci/I Cs-137 84, 85 1.01 pcin pCi/I Co-58 94 92 0.98 PCVI Mn-54 88 93, 1.06 pcill Ft-59 75 74. 0.99 PCVI.

Zn-65 166 170 1.02 Co-60 .117 118 1.01 September-03 E3868.162 AP Filter pCi Or. Alpha 28 30 1.07 pCi Gr. Beta 189 197 1.04

• 1-131 LL= radiochemical separation analysis J-8 I . I, ,-

TABLE J-2 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 4 of 4)

Analytics Identification Calculated Framatome Framatorne/Analytics Month/Year No. Medium Units Nuctide Results 1Results Ratio Scptember-03 -3869-162 Millk pCi/i 1-131 74 66 0.89 pCi/I 1-13ILL 74 74 1.00 pCi/i Cc-141 86 90 1.05 pCi/I Cr-t5 233 228 0.98 pCi/i Cs-134 119 123 1.03 pCi/I Cs-137 88 94 1.07 pCi/i Co-58 99 99 1.00 pCi/I Mna54 93

• 101 1.09 pCi/I Fe-59 79 84 1.06 pCi/I Zn-65 176 178 1.01 pCi/I Co-60 123

• 129 1.05 September-03 e3870-162 Milk pCi/i Sr-89 100

• 80 0.80 pCi/i Sr-90 14 1II 0.79

• 1-131 LL = radiochemical separation analysis J.9

(__ C- (I

C C TABLt; J-3

(

PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 -

FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page l of 5)

Identification Analyties Framatome Framatome/Analytles Month/Year No. Medlum Units Nuclide Calculated Results (a) Results (a) Ratio March-03 E3573.186 Sediment pCAg Ce-141 358 +/- 18 351 +/- i4 0.98, pCi/kg Cr-51 508 t 25 511 +/- 41 1.01 pCi/kg Cs-134 186 +/- 9 189 +/- 6 1.02 pCiAg Cs-131 497 +/- 25 536 +/-9 1.08 pCi/g Co-58 96 +/-5 97 5 1.01 Mn-54 133 t 65 132 11 0.99 .

pC/kg Pe.59 98 +/ 104+/- 7 1.06

.,I pCAg Zn-65 192 1I 197 +/- 10 1.03 pCi/kg Co-60 335 +/- 17 340 6 1.01 Marh-03 E3575.186 Milk pallI 1-131 75 '* 3 73 9, 0.97.

PCA Ce. 14t 188

• 17 19it 7 1.03, Cr-51 ' 267

• 35 244 31 0.91 pC,/

Cs-134 98 +/- 5 95 *4' 0.97, pCi/

Pan Cs-137 ' 217 *22 22i 6 1.02 pall Co-58 51'* 2 ' 50 3 0.98 pCiA Mn-54 70

• 3 ' 70 4 1.00 Fe-59 ' 51

• 2 51 +/-5 1.00 Zn-65 101 t 5 101 8 1.00, pC'f Co-60 176

• 16 179 4 1.02.

Marh-03 E3576-186 AP Filter pC Ce-141 160

• 6 143 +/-2 0.89 pCi Cr-5I 227 +/- 8 219 +/- 11 0.96 pCa Cs134 83

• 3 78 +/- 2 0.94 pCa Cs-137 185 +/- 6

• 179 +/-3 0.97 pCa Co-58 43

• 2 41 +/-2 0.96 pCa Mn-54 59 t 2 59 +/- 2 0.99 pCi Fe-59 44

• 2'. 45 *2 1.01 Zn-65 86 +/-f3 87 *4 1.01 pCi Co-60 149 +/-5

• 133 +/-2 0.89 J-10 (a) Counting error is two standard deviations.

TABLE J-3 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 2 of 5)

Identification Analytics Framatonme Franatonte/Analytics MonthlYear No. Medium Units Nucide Calculated Results (a) Results (a) Ratio March-03 E3577-186 APFIlUr pCi Co-141 133 +/- 5 121 +/- 2 0.91 pQ Cr-51 189 t7 172 t 9 0.91 pCi Cs134 69 t 2 62 t 1 0.89 pa Cs-137 154 +/- 5 153 i 3 0.99 pa Co-S58 36 t 1 36 t 2 0.99 pai Mn-54 50 t 2 50 t 2 1.01 pai Po-59 36 t 1 40+/-2 1.11 pai Zn-65 72 t3 71 +/-4 0.98 pa Co-60 125 +/-4 113 +/- 2 0.90 March-03 E3578.186 APSFItr Pa Co-141 171 t6 162 t2 0.95 pi Cr-51 242 t8 235 t 11 0.97 pi Cs134 89 t3 82 t2 0.93 pa Cs-137 197 t7 200 t3 1.02 PC Co-58 46 t2 44 +/- 2 0.96 pa Mn-54 63 t2 68 t2 1.08 pa Fe-59 47 t2 53 t2 1.12 pa Za-65 91 t3 95 t 4 1.05 pO Co-60 159 t6 148 t2 0.93 Jun-03 E3770-186 APHFItr pai Co-141 230 t8 209 t2 0.91 Pa Cr-51 194 +/- 7 190 t 11 0.98 pa Cs134 84 t3 78 t 2 0.93 pa Cs-137 188 t7 191 t3 1.02 pa Co-58 76 t3 74 t2 0.98 pa Mn-54 151 t5 157 +/- 3 1.04 pa Fe-59 81 t3 85 t 3 1.04 PCa Z-65 148 t 5 157 +/- 5 1.06 pa Co-60 108t4 100 t 2 0.92 J-11 (a) Conitng cnor is two standard deviations.

I- C-

( TABLx J-3 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 3 of 5)

Identification AnalytIcs Franmatome Framatome/Analytics Month/Year No. Medium Units Nuclide Calculated Results (a) Results (a) Ratio June-03 E3771-186 APRilter pO Ce.141 203

• 7 189

• 2 0.93 pci Cr-51 171 +/- 6 170 t 10 0.99 pC, Csl34 74 +/-:3 69 +/- 2 0.94 PC, Cs-137 165+/- 6 170 +/- 3 1.03 PO Co-58 67 t 2 66 +/-t2 0.99 pCi Mn-54 133* 5 142t 3 1.06 pCi Pe-59 71+/- 2 78 +/-t3 1.09 pC, Zn-65 130 5 138 +/- 5 1.06 PI? Co-60 95 3 89 +/- 2 0.94 June-03 E3772.186 APRiiter pCi Ce-141 225 t 8 203+/- 2 Q90 ipa Cr-51 190+/-e1' 177 10 0.93 pC Cs134 82 +/- 3, 76+/- 2 0.93 pC, Cs-137 183

• 6 186+/- 3 1.02 pOa Co-58 74 +/- 3 71 +/- 2 0.96 pCi Mn-54 148 +/- 5 152 +/- 3 1.03 pC, Pe-59 79 +/- 3 84 +/- 3 1.06 PC, Zn-65 144 +/-5 154+/- 5. 1.07 IC, Co-60 105 t 4 97+/-t.2 0.92 June-02 E3773-186 Charcoal rilter pCa 1i131 66 +/- 2 80 +/- 7 1.22 E3774-186 Charcoal Filter 0ii 1-131 51 +/- 2 (1)

E3775-186 Chasroal Filter paC 1.131 59 +/- 2 68 +/- 6 1.15 J-12 (a) Counting error is two stardard deviations.

TABLE J-3 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOMEANP ENVIRONMENTAL LABORATORY (Page 4 of 5)

Idendncatlon Analytics Frunatomne Franuatome/Analytlcs Mna^{WYrar a8allW$v 1szr NA_

1^o. Medlunm Units Nuctide Calculated Results (a) : Results (a) Ratio Squnber-03 E3891-186 Milk pCa 1-131 75 t 2 83 t 8 1.10 pQi/1 Co-141 188

• 11 191 t 6 1.01 piA Cr-51 510 t 87 543 t 35 1.06 Cs-134 261 t 23 245 +/- 6 0.94 paiA PCW Cs 137 193 t 12 196 +/- 5 1.02 Co-58 216 t 15 214 t 6 0.99 pQf PaA Mn-54 203 t 14 187 t 5 0.92 pal Fe-59 173 t 10 173 &7 1.00 pCzA Zn-65 385 +/- 50 398 +/- 12 1.03 pQa Co-60 270 t 24 283 t 5 1.05 Dccmber-03 E3977-186 Qaarcoal Filter pCi 1-131 76 t 2.5 85 +/- 6 1.12 E3978-186 CharcoalFilter pCi 1-131 68 t 2.3 78 t 6 1.15 E3979-186 Chsaroal Filter pCi 1-131 86 t 2.9 94 +/-6 1.09 J-13 (a) Countlln error is two stairlanl deviations.

QC C

( TAlC.T J-3 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOMEANP ENVIRONMENTAL LABORATORY (Page 5 of 5)

COMMENTS Framatome ANP unable to analyze sample. Charcoal cartridge damaged during shipment from Analytics.

1 .. .1 J-14

TABLEJ4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 1 of 4)

IdentifIcation EFIL Known Framatome FramatomecEML Month/Year No. hMedium Units Nuclide Results Results Ratio March-03 QAP 58 AP Falter Bq Mn-54 43.8 43.2 0.99 Bq Co-60 33.5 33.5 1.00 Bq Sr-90 2.8 2.3 0.83 Bq Cs-137 99.7 102.7 1.03 Bq U-234 0.2 0.2 0.93 Bq Pu-238 0.5 0.5 0.99 Bq U-238 0.2 0.2 0.92 Bq Pu-239 0.3 0.3 1.00 Bq Am-241 0.3 0.3 0.98 Bq Gross Alpha 1.2 1.1 0.93 Bq Gross Bcta 1.5 1.4 0.94 March-03 QAP 58 Soil Bq/kg K40 636.0 653.0 1.03 Bq/kg Cs-137 1450.0 1497.6 1.03 Bq/kg Ac-228 57.6 54.9 0.95 Bq/kg U-234 120.0 115.7 0.96 Bqlkg Pu-238 21.9 23.5 1.07 Bq/kg U-238 125.0 122.9 0.98 Bqlkg Pu-239 23.4 24A 1.04 Bq/kg Am-241 15.6 12.4 0.79 (1)

March-03 QAP 58 Vegetation Bq/kg K-40 1120 1172 1.05 Bqlkg Co-60 12.1 13.02 1.08 Bq/kg Sr-90 650 545.3 0.84 Bq/kg Cs-137 444 469.1 1.06 Bq/kg Pu-239 5.17 5.05 0.98 Bq/kg Am-241 3.51 3.487 0.99 Bq/kg Cm-244 2.01 2.05 1.02 J-15

(, C (.

': TAClJ J-4 DOE -ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

C QUALITY ASSESSMENT PROGRAM (QAP)

FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 2 of 4)

Identification EML Known Framatome Framatome/EML MonthlYear No. Medium Units Nucilde Results Results Ratio March-03 QAP 58 Water Bq/l H-3 426.0 390.0 0.92 Bq/l Co-60 219.0 234.0 1.07 Bq/l Sr-90 4.1 4.3 1.07 Bq/l Cs-134 29.4 30.5 1.04 Bqtl Cs-137 59.6 63.8 1.07 Bq/l U-234 2.3 2.1 0.90 Bq/l Pu238 3.7 3.3 0.91 Bq/1l U-238 2.1 2.2 1.02 Bq/l Pu-239 4.2 3.9 0.92 Bq/l Am-241 2.2 2.1 0.99 Bq/l Gr. Alpha 418.1 377.5 0.90 Bq/l Gr. Beta 682.4 627.5 0.92 September-03 QAP 59 AP Filters Bq Co-60 55.1 56.0 1.02 Bq Cs-137 54.8 57.1 1.04 Bq Gr. Alpha 3.1 2.8 0.88 Bq Gr. Beta 3.9 3.1 0.80 (2)

Bq Mn-54 58.0 58.3 1.01 September-03 QAP 59 Soil llq/kg AcTh-228 50.8 51.7 1.02 Bqlkg Cs-137 1973.0 2269.0 1.15 nq/kg K-40 488.0 547.0 1.12 1-16

TABLE J-4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 3 of 4)

Identification EMIL Known Framatome Framatome/EML Month/Year No. Medium UInits Nuclide Results

---

Results Ratio September-03 QAP 59 Water Bqtil Co-60 469.4 513.0 1.09 BqIl Cs-134 60.1 63.0 1.05 BqIl Cs-137 73.9 80.3 1.09 Bqtl Gross Alpha 531.0 622.0 1.17 Bqtl Gross Beta 1790.0 1948.0 1.09 September-03 QAP 59 Vegetation Bq/kg (3) (3) (3) (3) 1-17

(_ c (7

TABLE J-4 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 4 of 4)

COMMENTS Low.biasidentified. ConditionReport(CRNo.03-20)generatedbyFramatomeEnv.LabtoinvestigateLowBias.

2 Low bias identified. Condition Report (CR No. 04-03) generated by Framatome Env. Lab to investigate Low Bias.

3 No vegetation saimple was provided by DOEQAP for this test period.

3-18

TABLE J-5 DOE - MAPEP MXED ANALYTE PERFORMANCE EVALUATION PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 1 of 2)

Identification MAPEP Known Framatome Framatome/MIAPEP Month/Year No. Medium Unfit Nuclide

- -------- Resmlt

---

Results Ratio Evaluation March-03 02-W1O Water Bq/L Am-241 058 058 1.00 Agreement Bq/L Cs-134 421.00 398.12 0.95 Agreement Bq/L Cs-137 329.00 301.31 0.92 Agreement Bq/L Co-57 57.00 52.44 0.92 Agreement Bq/L Co-60 38.20 3654 0.96 Agreement Bq/L Fe-55 96.00 87.00 0.91 Agreement Bq/L Mn-54 32.90 3153 0.96 Agreement BqlL Ni-63 13650 126.00 0.92 Agreement Bq/L Pu-238 0.83 0.85 1.03 Agreement Bq/L Pu-239/40 0.03 False Positive (1)

Bq/L Sr-90 12.31 11.09 0.90 Agreement Bq/L U-233/234 1.54 1.63 1.06 Agreement Bq/L U-238 1.60 1.63 1.02 Agreement Bq/L Zn-65 516.00 509.10 0.99 Agreement March-03 03-S 10 Soil Bq/Kg Cs-134 238.00 248.60 1.04 Agreement Bq/Kg Cs-137 832.00 848.80 1.02 Agreement Bq/Kg Co-57 530.00 544.40 1.03 Agreement Bq/Kg Co-60 420.00 439.20 1.05 Agreement Bq/Kg Mn-54 137.00 143.70 1.05 Agreement Bq/Kg Sr-90 714.00 626.60 0.88 Agreement Bq/Kg K-40 652.00 673.70 1.03 Agreement Bq/Kg Zn-65 490.00 51650 1.05 Agreement J-19

(

C- 0

C TAL , JC5 DOE - MAPEP MIXED ANALYTE PERFORMANCE (Page 2 of 2)

COMMENTS I False positive. Condition Report (CR No. CR 03-14) generated by Framatome Env Lab to investigate and verify MDC of sample with MAPEP.

. .. - . , .. V J-20 t - I . ,

TABLE J-6 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)

PROFICIENCY TESTING PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)

(Page 1 of 2)

Identification ERA Known TBE TBE/ERA ERA MonthlYear No. Medium Units Nuclide Result (a) Results (a) Ratio Control Limits (b) Evaluation May-03 Rad-53 Water pCi/t 1-131 20.8 13.6 0.65 15.6 - 26.0 (1) pCi/l H-3 1250 1200 0.96 678 - 1820 Acceptable pCi/l Co-60 63.8 69.9 1.10 55.1 - 72.5 Acceptable pCi/l Cs-134 75.7 73.5 0.97 67.0 - 84.4 Acceptable pCiAI Cs-137 150 165 1.10 141 - 159 (2) pCi/l Sr-89 31.3 37.0 1.18 22.6-40.0 Acceptable pCi/l Sr-90 27.4 23.5 0.86 18.7 -36.1 Acceptable November-03 Rad-55 Water pCi/l 1-131 28.2 22.2 0.79 23.0 - 33.4 (3) pCi/l H-3 14300 1630 0.11 11800- 16800 (4) pCi/I Co-60 27.7 28.4 1.03 19.0 - 36.4 Acceptable pCi/t Cs-134 23.4 21.7 0.93 14.7-32.1 Acceptable pCi/I Cs-137 64.2 63.6 0.99 55.5 - 72.9 Acceptable pCi/l Sr-89 50.4 47.9 0.95 41.7 -59.1 Acceptable pCi/l Sr-90 10.2 9.23 0.90 1.54- 18.9 Acceptable pCi/I Gr-Beta 168 161 0.96 124 -212 Acceptable (a) Results are the average of three measurements, reported in units of pCi/l.

(b) Per guidelines of the EPA'S National Standards for Water Proficiency Testing Criteria Document, December 1998.

J-21 (3 C (_

C TAILD J-6 ENVIRONMENTAL RESOURCE ASSOCIATES (ERA)

PROFICIENCY TESTING PROGRAM - 2003 -

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)

(Page 2 of 2)

COMMENTS I The stable iodine carrier in the sample was unaccounted for in the calculation. When recalculated, the correct result of 20.0 pCi/L was within acceptance criteria. NCR 03-11 generated by Teledyne to investigate condition.

2 Although Cs-137 is evaluated as N, the TBE/ERA ratio of 1.10 falls within limits of 0.80 - 1L20 and is considered by TBE as acceptable.

3 The decay correction did not take into account the extended count time. When recalculated,'the correct result of 23.2 was within acceptance criteria. NCR 04-06 generated by Teledyne to investigate condition.

4 Due to recalculating H-3 to required reporting units, a decimal 'place was dropped. The correct result of 16300 is within acceptance criteria. NCR 04-06 generated by Teledyne to investigate condition, .

I2 -

J-22 I-'

TABLE J-7 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 1 of 5)

Analytics Identification Calculated TBE TBE/Analytics MonthJYear No. Medium Units Nudide Results Results Ratio March-03 E3585-396 Milk pCi/I Sr-89 133 80: 0.60 (I) pCi/I Sr-90 11.8 11.2 0.95 March-03 E3586-396 Milk pCi/I 1-131 74 75 1.01 pCi/i Ce- 141 173 168 0.97 pci/I Cr-SI 246 243 0.99 pCi/I Cs-134 90 83, 0.92 pCi/I Cs-137 200 207 1.04 pCi/i Co-58 47 49 1.04 pCi/I Mn-54 64 65 1.02 pCviI Fc-59 47 53 1.13 pCi/i Zn-65 93 114 1.23 (4) pCi/I Co-60 162 169 1.04 March-03 E3588-396 AP Filter pCi Cc-141 224 239 1.07 Poi Cr-SI 318 348 1.09 pCi Cs-134 117 101 0.86 pCi Cs-137 259 277 1.07 pCi Co-58 60 66 1.10 Poi Mu-54 83 97 1.17 pCi Fe-59 61 80 1.31 (2)

Poi Zn-65 120 152 1.27 pCi Co-60 209 223 1.07 Poi Fe-55 106 138 1.30 (4)

March-03 E3587-396 Charcoal Filter pCi 1-131 74 68 0.92 J-23 C. C' (

( TABL6 J-7 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 5)

Analytics Identification Calculated TBE TBEiAnalytics Month/Year No. Medium Units Nucide Results Results Ratio June-03 E3747-396 Milk pCinl Sr-89 85 89i 1.05 pCi/l Sr-90 23 20' 0.87 June-03 E3748-396 Milk pCinl 1.131 103 115 1.12 pCin Ce-141 283 285 1.01 pCi/l Cr-51 239 266 1.11 pCi/ Cs-134 103 . 991 0.96 pci/ Cs-137 230 236 1.03 pCi/l Co-58 93 106 1.14 pCin Mn-54 186 190 1.02 pCiI Fe-59 99 108 1.09, pCi/I Zn-65 181 208 1.15.

-cin 606 132 142 1.08 June-03 E3750-396 AP Filter pCi' Ce-141 248 238 0.96.

pCi Cr-51 209 239 1.14 pCi Cs-134 91 i9! 0.87 pCi Cs-137 202 189 0.94 pCi Co-58 81 71 0.88 pCi Mn-54 163 164 1.01 pCi Fe-59 87 91j 1.05 pCi Zn-65 159 155 0.97 pCi Co-60 116 109 0.94 pCi Fe-55 97 160 1.65 (3)

June-03 E3749-396 Charcoal Filter pCi 1-131 62 78: 1.26 (4)

-J24

TABLE J-7 ANALYTICS ENVIRONMENTAL RADIOACTIVlTY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of 5)

Analytics Identirication Calculated TBE TBE/Analytics Monthear No. Medium Units Nudide Results Results Ratio Septembcr-03 E3898-396 Milk pCi/i Sr-89 100 45 0.45 (I) pCi/I Sr-90 14 13: 0.93 Scptember-03 E3899-396 Milk pCi/I 1-131 74 73 0.99 pCi/I Cc 141 86 85 0.99 pCi/i Cr-SI 233 220 0.94 pCi/I Cs-134 119 106 0.89 pCvi/ Cs-137 88 90 1.02 pCviI Co-58 99 96 0.97 pCi/i Mn-54 93 95: 1.02 pai/I Fe-59 79 84 1.06 pCi/I Zn-65 176 187, 1.06 pCi/I Co-60 123 132 1.07 Septcmbcr.03 E3901-396 AP Filter pCi Ce-141 77 79 1.03 pCi Cr-51 210 227 1.08 pCi Cs-134 108 93 0.86 pCi Cs-137 79 70 0.89 pCi Co-58 89 80 0.90 pCi Mn-54 84 73 0.87 pCi Fe-59 71 74 1.04 pCi Zn-65 158 143 0.91 pCi Co-60 Ill 93' 0.84 pCi Fc-55 112 144 1.29 (4)

Scptcmber-03 E3900-396 Charcoal Filter pCi 1-131 86 74 0.86 Novcmbcr-03 E3790-396 Milk pCi/i Sr-89 168 185 1.10 pci/l Sr-90 17 19 1.12 J-25

(__ - _. a

r TABj u.!J-7 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 4 of 5)

Analytics Identirfcation Calculated TBE TBWiAnalytics MonthlYear No. Medium Units Nuclide Results Results Ratio November-03 E3971-396 Milk pCili 1-131 90 87 0.97 pCi/I Ce-141 202 186 0.92 pCi/I Cr-51 280 287 - 1.03 pCi/I Cs-134 135 I119 0.88 pCin Cs-137 129 116 0.90

• ' ' ' ' ' ' ' pCi/I icill Co-58 III iII 1.00

, I. I. pCi/I Mn-54 173 176 1.02 Fe-59 '102 ' 941 0.92 pCi/ Zn-65 -197 *190. 0.96

• ,.*, . pan/

Co-60 153 140 0.90

,,, fNovember-03,;. ,S, E3973-396 4:tAP!.' ilter pCi .. Ce-i41t '- 142 144 1.01 pCi Cr-SI 198 203 1.03 Cs-134 96 90' 0.94 pCi Cs-137  ! 19- ': , 'If ,,,85' 0.93 1;,  : , .. ".-"! ,  : . I pCi l Co 78 - ~80( 1.03 pCi Mn-54 122 11I 0.94

. .pCi Fe-59 72 72 1.00

. I pCi Zn-65. 139., 121 0.87 pCi Co-60 109 102 0.94 pCi Fe-55 96 62. 0.65 (5)

November-03 E3972-396 Charcoal Filter . pCi- 1-131 77 67: 0.87 1-26 i

.. II r

.. , ,,,1 ,-- --

I I

TABLE J-7 ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE QUALITY CONTROL SPIKE PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 5 of 5)

COMMENTS I Incorrectly calculated. The recalculated March & September Sr-89 results of 138 & 95.8 pCi/L, respectively, are acceptable.

The efficiency required for these samples is different than the efficiency for regular samples.

NCR 04-02 generated by Teledyne to investigate conditon.

2 Using only the results from'the 1099.2 keV photon, the Fe-59 would be 71 pCi, which is acceptable. Coincidental summing occurs only with significant Fe-59 activity levels. Therefore, there is no impact on environmental samples.

NCR 04-02 generated by Teledyne to investigate condition.

3 Reprocessed to separate Fe-55 peak. Reprocessed result of 103 total pCi is acceptable. NCR 04-02 generated by Teledyne to investigate the condition.

4 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.

5 NCR 04-07 generated by Teledyne to investigate condition. The mylar film (not a filter) from Analytics is not typical of samples received from Teledyne clients. Since the analytics sample was mylar, the laboratory tried to adjust to the new matrix by ashing the filter before analysis.

Analytics thought Teledyne was performing a direct count of the mylar (no preparation or chemical separation).

Teledyne believes that some of the Fe-55 was lost during ashing.

Teledyne has changed their request to Analytics and will now receive glass fiber filters for analysis.

Inaddition, Teledyne has also verified the validity of their Fe-55 efficiencies by comparing to a standard from a different standards lot.

J-27 t ~C:X U

TAIL! J-8 PPL REMP LABORATORY SPIKE PROGRAM

(

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 1 of 5)

IdentificatIon Analytics i I~l TBE. TBEJAnalytics Month/Year No. Meduhm Units Nuclide Calculated Results (a) i Results (a) Ratio I-March-03 E3573-186 Sediment pCi/kg Ce-141 358

• 18 409

• 17 1.14-pCi/kg Cr.51 - 508

• 25 576 +/- 99 1.13 pCi/kg Cs-134' 186 +/- 9 180 +/- 9 0.97 pCi/kg Cs- 137 497 : 25 598 +/-i 19 1.20 pCi/kg Co-58 96 +/- 5 116 +/- 13 1.21 pCi/kg Mn-54 133 +/- 65 157 :+/- 13 1.18 pCi/kg Fe-59 98 +/- 5 120 +/- 17 1.22 pCi/kg Zn-65 192 11 271 +/- 23 1.41 (1) pCi/kg Co-60 335 +/- 17 408

• 13 1.22 March-03 E3569-186 Milk pci/I 1-131 6*4.

75 3 67 +/--7. 0.89.

pCi/i Ce- 14i 188 +/- 17 188:+/- 8 1.00; pCi/i Cr-51, 267+/-,35 262 - 37 0.98 pCi/I Cs.134 98 +/-5' 86 +/-3 0.88 pCi/I pCai Cs-137 217 +/-22 214 +/- 7. 0.99.

pcihx Co-58 51+/-2 50

• 4 0.98 pCi/i Mn-54 74 +/- 5 1.05 pCi/i Fe-59 51 :2 56 t 6 1.10 pCi/i Zn-65 101I:. 5 110 *9 1.09 pCi/i Co-60 176 +/- 16 173

• 5 0.98 March-03 E3570-186 AP Filter pCi Ce-141 151.+/- 5 153 f 7 1.01 pCi Cr-5I 215 +/- 8 241 +/-38 1.12.

pCi Cs.134 79 +/-i 3 67 +/- 4. 0.84 pCi Cs-137' 175.+/- 6 180 :9 1.03 pCi' Co-58 41 +/-1 45 +/-t 6 1.09 pci Mn-54' 56 +/- 2 59.5 +/- 7 1.06 pCi . - - Fe59 41 I 52.9 +/- 8 1.29 (1) pCi Zn-65 81 3 96.3 +/- 13 -1.19 pci Co-60 141 +/-'5 148 :t 7 1.05 J-28 II. .

(a) Counting error is two standard deviations.

TABLE J-8 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 5)

Identilication Analytics TBE TBE/Analytics MontblYear No. Medium Units Nuclide Calculated Results (a) Results (a) Ratio March-03 E3571-186 AP Filter pC Cc-141 156+/- 5 170 +/- 8 1.09 pc Cr-51 221 +/- 8 255 :+/- 46 1.15 pCi Cs-134 81 +/- 3 65.3 +/- 5 0.81 pCi Cs-137 180 +/- 6 187 t 9 1.04 pCi Co-58 42+/- I 39.5 +/- 8 0.94 pCi Mn-54 58 2 59.1 +/- 7 1.02 pCi Fe-59 43 +/- 2 51 +/- 9 1.19 pCi Zn-65 84 +/- 3 110+/- 13 1.31 (I) pCi Co-60 146 t 5 148 +/- 7 1.01 March-03 E3572-186 AP Filter pC Cc-141 182 +/- 6 180 +/- 7 0.99 pCi Cr-51 259 +/- 9 240 +/- 40 0.93 pCi Cs-134 95 +/- 3 76.3 t 4 0.80 pc Cs-137 211 +/- 7 217 +/- 9 1.03 pCi Co-58 49 +/- 2 51.5 +/- 7 1.05 pCi Mn-54 68 +/- 2 75.5 +/- 7 1.11 pc Fc-59 50+/- 2 60.3 +/- 9 1.21 pCi Zn-65 98 +/- 3 115 +/- 14 1.17 pCi Co-60 170 +/- 6 173 +/- 7 1.02 March-03 E3574-186 Water pCi/L H-3 4463 +/- 230 4840 +/- 176 1.08 June-03 E3776-186 AP Filtcr pCi Ce- 141 152 t 5 157 +/- 17 1.03 pCi Cr-51 128 +/- 4 142 +/- 102 1.11 pCi Cs-134 55 +/- 2 58.3 +/- 8 1.06 pCi Cs-137 123 +/- 4 147 +/- 14 1.20 pCi Co-58 50 t 2 46.5 +/- 14 0.93 pCi Mn-54 99 t 3 105 +/- 14 1.06 pC Fe-59 53 +/- 2 63 +/- 19 1.19 pci Zn-65 97 t 3 115+/- 18 1.19 pCi Co-60 71 +/- 2 87.9 +/- 10 1.24 J-29 (a) Counting crror is two standard deviations.

C

( TAB( J8 PPL REMP LABORATORY SPIKE PROGRAM

{

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of 5)

Identification Analytics TBE TBE/Analytics Month/Year No. Medium Units Nucide Calculated Results (a) Results (a) Ratio June-03 E3777A-186 AP Filter pCi Ce-141 238 +/- 8 267 + 20 1.12 pCi Cr-51 201 +/- 7 176+/- 112 0.88 pCi Cs-134 87 +/- 3 91 +/- 8 1.05 pCi Cs-137 194* 7 219+/- 17 1.13 pCi Co-S8 78 +/- 3 84.3 +/- 13 1.08 pCi Mn-54 156 +/- 5 172 +/- 17 1.10 pCi Fe-59 83 +/- 3 107 +/- 20 1.29 (1) pCi Zn-65 153 +/- 5 179 +/- 23 1.17 pCi Co-60 Ill +/- 4 127+/- II 1.14 June-03 ' E3778A-i86 AP Filter pCi Ce 141 140 +/- 5 128 +/- 20 0.91I

.. .,  !- f,. . Pai.

pCi Cr-51, 118 +/-C4 122'+/-' 89 1.03' pCi.

P, Cs-134 51 +/- 2 53.7 +/- 6 1.05, pCi Cs-137 114 +/- 4 112+/- 12 0.98 pCi Co-58 46 +/- 2 35+/- 10 0.76 pCi Mn-54 92+/- 3 96.2 +/-l Ii 1.05' pCi' Fe-59 49 +/- 2 42.4 18 0.87, pCi Zn-65 89 f 3 74.1 +/-18 0.83, pOi Co-60 65 +/- 2 69.6 +/- 7 1.07, pCi June-03 E3779-186 Charcoal Filter 1-131 66 +/- 2' 73.9 +/- 3 1.12 June-03 E3780-186 Charcoal Filter pCi 1-131 59 +/- 2 68.6 +/- 3 1.16 June-03 E3781-186 Charcoal Filter pCi 1-131 51 +/- 2 61.6 +/- 4 1.21

., . I . I .... .. , ' .' J-30

.. "I . I .1 I.

-1 . i (a) Counting error is two standard deviations.

- .I

TABLE J-8 PPL REMP LABORATORY SPIKE PROGRAM ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 4 of 5)

Identification Analytics TBE TBE/Analylics Month/Year No. Medium Units Nuclide Calculated Results (a) Results (a) Ratio Scptcmber-03 E3889- 186 Milk pCi/i 1-131 75 +/- 2 65.9 +/- 8 0.88 pCi/I Ce-141 188+/- 11 171 11 0.91 pCi/i Cr-51 510 t 87 429 +/- 48 0.84 pCi/I Cs-134 261 +/- 23 212 +/- 5 0.81 pCi/i Cs-137 193 +/- 12 181 :t 8 0.94 pCi/i Co-58 216 t 15 197 +/- 8 0.91 pCi/I Mn-54 203 +/- 14 202 t 9 1.00 pCi/I Fe-59 173 +/- 10 177 +/- 10 1.02 pCi/I Zn-65 385 t 50 368 +/- 16 0.96 pCi/I Co-60 270 +/- 24 264 +/- 7 0.98 Scptcmber-03 E3890-186 Watcr pCi/I H-3 8000 +/- 300 8240 +/- 222 1.03 December-03 E3981-186 Charcoal Filter pCi 1-131 77 +/- 3 83 +/- 3 1.07 December-03 E3982-186 Charcoal Filter pCi 1-13 68 t 2 73 +/- 2 1.07 December-03 F3983-186 Charcoal Filter pCi 1-131 86 +/- 3 92 :+/- 5 1.07 J-31 (a) Counting error is two standard deviations.

(' (,

a

K K (

TABLE J-8 PPL REMP LABORATORY SPIKE PROGRAMI ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 5 of 5) i i

COMMENTS i, i

I High Bias identified. Evaluation of results requested by PPL via email on April 19, 2004. i I

-j. J-32

TABLE J-9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page I of 4)

Identification EML Known TBE TBE/EML Month/Year No. Medium Units Nucilde Result Results Ratio March-03 QAP-58 AP Filter Bq Am-241 0.34 0.34 1.00 Bq Co-60 33.5 35.9 1.07 Bq Cs-137 99.7 113.7 1.14 Bq Gr-Alpha 1.2 0.9 0.73 (1)

Bq Gr-Beta 2 1.6 1.07 Bq Mn-54 43.8 49.4 1.13 Bq Pu.238 0.52 0.59 1.13 Bq Pu-239 0.3 0.4 1.06 Bq Sr-90 2.8 2.4 0.86 March-03 QAP-58 Soil Bqlkg Ac-228 57 70 1.23 (4)

Bq/kg Am-241 16 16 0.99 Bqgkg Bi-212 61 73 1.20 (4)

Bqtkg Bi-214 67 76 1.14 Bq/kg Cs-137 1450 1883 1.30 (2)

Bq/kg K-40 636 806 1.27 (4)

Bq/kg Pb-212 58 75 1.29 (4)

Bq/kg Pb-214 71 79 1.11 Bq/kg Pu-239 23 25 1.09 Bqgkg Sr-90 64 54 0.83 Bq/kg Th-234 127 169 1.33 March-03 QAP-58 Vcgctation Bq/kg Co-60 12 14 1.19 Bqgkg Cs-137 444 522 1.18 Bqgkg K-40 1120 1360 1.21 Bq/kg Sr-90 650 498 0.77 J-33 C-!

C- TABLEi J-9 C DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 4)

Identill[cation EML Known TBE T [IE/EML MonthfYear N,D. Medlum Units Nuclide Result Results Ratio March-03 QAP-58 Water Bqnl Am-241 2.13 2.4 1.13 Bqll Co-60 234 252 1.08 Bq/l Cs- 134 31 31 1.02 Bq/l Cs- 137 64 72 1.12 Bq/l Gr-Alpha 378 484 1.28 (4)

Bq/1 Gr-Beta 628 821 1.31 (4)

Bq/l. H-3 390 418. 1.07 Bq/1 Pu-238 . 3.3 .4.0 1.20. (3) io Bq/l Pu-239 3.9 4.6 1.16 Bq/l Sr-90 4.3 3.6 0.84 Septem303 QAP 59 AP Filter Bq Mn-54 58 54 0.93 Bq Co-60,, 55.1. 53.3, 0.97.

Bq, , Sr-90. 2.1, 1.7 0.81-Bq " Cs-137 54.8 51.2. 0.93.,

Bq U-234 0.4 0.4 0.92 Bq Pu-238 0.2 0.2 1.00 Bq U-238 0.4 0.4. 0.93 Bq Pu-239 0.4 0.4 1.00 Bq Am-241 0.4 0.4 0.90 Bq Gr-Alpha 3.1 3.1 1.00 Bq Gr-Beta 3.9 3.4 0.87 J-34

TABLE J-9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of 4)

Jdentillcatlonl EML Known TBlEi TBEIEML Month/Year No. Medium Units Nuciide Result Results Ratio Septembcr-03 QAP 59 Soil Bq/kg K-40 488 517 1.06 Bq/kg Sr-90 80 70 0.87 Bq/kg Cs-137 1973 2127 1.08 Bq/kg Bi-212 54 56 1.04 Bq/kg Pb-212 51 53 1.04 Bq/kg Bi-214 34 36 1.06 Bq/kg Pb-214 35 42 1.18 Bqlkg Ac-228 51 56 1.11 Bq/kg Th-234 116 145 1.25 Bq/kg U-234 127 115 0.91 Bq/kg Pu-238 15 114 0.92 Bq/kg U-238 127.1 114 0.90 Bq/kg Pu-239 30.4 28.3 0.93 Bq/kg Am-241 18.4 16.5 0.90 Scptember-03 QAP59 Water Bq/l H-3 446 511 1.14 Bq/ Co-60 513 491 0.96 Bq/l Sr-90 7 6 0.84 Bq/l Cs-134 63 62 0.99 Bq/l Cs-137 80 75 0.93 Bq/l U-234 2.79 2.7 0.97 Bq/l Pu-238 2.07 2.2 1.06 Bq/l U-238 2.8 2.6 0.93 Bq/1 Pu-239 4.99 5.4 1.08 Bq/1 Am-241 8.76 9.2 1.05 Bq/i Gr-Alpha 622 612 0.98 Bq/l Gr-Beta 1948 1663 0.85 J-35 C- C- i

( TABQ' J-9 c DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP) I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 4 of 4) l COMMENTS 1 Gas flow Proportional efficiencies are established using Am-241, industry standard for clieni samples.

EML requires an efficiency based on Th-230. Using Th-230 efficiency, the result of 1.18 is acceptable.

NCR 03-07 generated by Teledyne to investigate condition. -

2 Incorrect bottle size used. Sampie'was placed into a smaller container and recounted. All re count results were acceptable except Bi-212 which was acceptable with warning. Previously analyzed samples were exam ined and no other incorrect container sizes were noted. NCR 03-07 generated by Teledyne to investigate condition.

. h-e o.

3 The electroplating cell was determined to have trace amounts of plutonium, causing an eievwted activity. .The electroplating cell has been taken out of service.

4 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.

. . I j . . I J-36

TABLE J-10 DOE - MAPEP MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)

(Page 1 of 2)

Identificallon MAPEP Known TBE TBE/MAI'EP No. Medium Units Nuclide Result Results Ratio Evaluation 02-W10 Water pCi/l Am-241 0.578 0.61 1.06 Agreement pCi/i Cs-134 421 382.7 0.91 Agreement pCiA Cs-137 329 329.3 1.00 Agreement pCill Co-57 57 58.17 1.02 Agreement pCi/l Co-60 38.2 41.2 1.08 Agreement pCi/l Fe-55 96 97.7 1.02 Agreement pCitl Mn-54 32.9 35.07 1.07 Agreement pCi/l Ni-63 136.5 151.3 1.11 Agreement pCi/i Pu-238 0.83 0.91: 1.10 Agreement pCi/l Sr-90 12.31 11.70 0.95 Agreement pCi/I Tc-99 132 84.00 0.64 Low Bias (1) pCi/l U-234/233 1.54 1.49 0.97 Agreement pCi/l U-238 1.6 1.61 1.01 Agreement pCi/l Zn-65 516 566 1.10 Agreement 03-S10 Soil pCi/kg Cs-134 238 204 0.86 Agreement pCi/kg Cs-137 832 803 0.97 Agreement pCi/kg Co-57 530 499 0.94 Agrcemcnt pCi/kg Co-60 420 427 1.02 Agreement pCi/kg Fe-55 1020 892 0.87 Agreement pCi/kg Mn-54 137 136 0.99 Agreement pCi/kg Ni-63 770 803 1.04 Agreement pCi/kg Pu-238 66.9 69 1.03 Agreement pCi/kg Pu-239/240 52.7 57.7 1.09 Agreement pCi/kg K40 652 686 1.05 Agreement pCi/kg Sr-90 714 651 0.91 Agreement pCi/kg U-2341233 89 70.2 0.79 Agreement (2) pCi/kg U-238 421 394 0.94 Agrcemcnt pCi/kg Zn-65 490 528 1.08 Agreement J-37 CK C_ _

C TABC J-10 DOE - MAPEP MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (TBE)

(Page 2 of 2)

COMMENTS Teledyne lab technician read the pipette incorrectly, delivering a 20 ml aliquot rather than the 30 ml aliquot used to calculate the result. The re-analyzed Tc-99 result of 127 Bq/L is acceptable.

NCR 03-05 generated by Teledyne to document/investigate the event.

2 Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.

J-38