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

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

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MAY 0 7 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 PLA-5748 Docket Nos. 50-387 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 A r 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:

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

72T9 B.E./Rhoads 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 Environmental Monitoring Program (REMP) sampling met or exceeded the requirements of the Susquehanna Steam Electric Station (SSES) Technical Requirements. The types of analyses that were performed on these samples for the identification and quantification of radioactivity also met or exceeded the SSES Technical Requirements. The result of this effort was the verification of the SSES Effluent Monitoring Program data that indicate that the SSES operation has no deleterious effect on the health and safety of the public or the environment.

The amounts of the radionuclides detected in environmental samples during 2003 were very small, as in past years. Based on the radionuclide levels measured by the REMP, the maximum whole body dose or maximum organ dose to a member of the public from SSES operation is estimated to be less than one-tenth of one percent of the per unit dose guidelines established by the Nuclear Regulatory Commission (NRC) as stated in 10 CFR 50, Appendix I.

The maximum hypothetical off-site whole body and organ doses from radionuclides detected by the REMP 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 OF A VERA GE ANNUAL PUBLIC EFFECTIVE DOSE-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).

2003 Radiological Environmental Monitoring Report I

2003 Radiological Environmental Monitoring Report I

I I Summary and Conclusions lived, naturally occurring radionuclide found in the human body, is estimated to deliver an average annual dose to the blood forming organs of individuals in the United States of about 27 millirem.

While a small portion of the background dose from natural radiation sources, the.

potassium40 dose is still 18,000 times the estimated maximum whole body and organ doses to a hypothetical member of the public from ingestion of radionuclides attributable to the SSES.

The maximum direct radiation dose from SSES operation to a member of the public was determined to be approximately 0.0314 millirem/year.

The total whole body dose from both ingested radionuclides and direct radiation is negligible compared to the public's exposure from natural background radiation, medical irradiation, and radiation from consumer products of more than 300 millirem/year effective dose-equivalent.

Identified Radionuclides and Their Dose Contributions Naturally Occurring Radionuclides In 2003, the SSES REMP reported the naturally occurring radionuclides beryllium-7, potassium-40, radium-226, and thorium-228 in the environment at levels exceeding the minimum detectable concentrations (MDCs) for their respective gamma spectroscopic analyses. Beryllium-7 was identified in air and sediment. Potassium40 was observed in fish, sediment, surface water, ground water, milk, soil, and fruit and vegetables. Thorium-228 and radium-226 were reported in sediment.

These radionuclides are not related to the operation of the SSES. Doses from the presence of these radionuclides were not included in the estimate of the dose from SSES attributable radionuclides.

Man-made Radionuclides Although not all due to SSES operation, the following man-made radionuclides were reported at levels in the environment in excess of the MDCs for their respective analyses: tritium, iodine-131 and cesium-137. These radionuclides, with the exception of cesium-137, were identified in surface, ground and drinking water. Tritium was measured above minimum detectable concentrations in some surface water, drinking water, and ground water samples. Iodine-131 was identified in surface water and drinking water. Cesium-137 was observed in sediment and soil.

Tritium is the only man-made radionuclide attributed to SSES operation. Tritium in media other than the Susquehanna River water downstream of the SSES was attributed to both natural production by the interaction of cosmic radiation with the upper atmosphere and previous atmospheric testing of nuclear weapons.

The presence of cesium-137 was attributed to non-SSES sources.

Cesium-137 was considered to be present only as residual fallout from atmospheric weapons testing. Iodine-131 was found in the aquatic pathway.

Evidence indicates that it is there only as the result of the discharge of medical waste to the Susquehanna or Lackawanna Rivers through sewage treatment plants upstream of the SSES.

2 2003 Radiological Environmental Monitoring Report 2

2003 Radiological Environmental Monitoring Report

Summary and Conclusions All of the man-made radionuclides mentioned above were not analyzed for in all media. For example, no analyses were performed in an effort to determine iodine-13 1 levels in ground water. When selecting the types of analyses that would be performed, consideration was given to the potential importance of different radionuclides in the pathways to man and the regulatory analysis requirements for various environmental media.

Relative Radionuclide Activity Levels in Selected Media Some media monitored in the environment are significant for the numbers of gamma-emitting radionuclides routinely measured at levels exceeding analysis MDCs.

Sediment in the aquatic pathway and soil in the terrestrial pathway are two such media.

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.

AQUATIC PATHWAY PERCENT TOTAL GAMMA ACTIVITY SEDIMENT Natural 99.5%

Marmade:

MaMnmade:

non-SSES SSES 0.1%

0.4%

TERRESTRIAL PATHWAY PERCENT TOTAL GAMMA ACTIVITY SOIL r

=

r

=

A FEZ ne%

'\\

NM ed SKSE 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 2003 Radiological Environmental Monitoring Report 3

2003 Radiological Environmental Monitoring Report 3

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 Contributing to Dose fromn 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.

4 2003 Radiological Environmental Monitoring Report 4

2003 Radiological Enivironmental MNonitorin g Report



2 Radiological Environmental Monitoring The enclosed information is consistent with the objectives outlined in the SSES ODCM and in IOCFR50 Appendix I,Section IV.B.2, IV.B.3 and IV.C.

In addition to the steps taken to control and to monitor radioactive effluents from the SSES, the SSES Technical Specifications also require a program for the radiological monitoring of the environment in the vicinity of the SSES.'

The objectives of the SSES REMP are as follows:

Fulfillment of SSES Technical Requirements' radiological environmental surveillance obligations,'

PPL has maintained a Radiological Environmental Monitoring Program (REMP) in the vicinity of the existing Susquehanna Steam Electric 'Station Units 1 and 2 since April, 1972, prior to construction of both units and ten years prior to the initial operation of Unit I in September, 1982. The SSES is located on an approximately 1500 acre tract' along the Susquehanna River, five miles northeast of Berwick in Salem Township, Luzerne County, Pennsylvania. The area around the site is primarily rural, consisting predominately of forest and agricultural lands. (More specific information on the demography, hydrology, meteorology, and land use characteristics of the area in the vicinity of the SSES can be found in the Environmental Report (Reference 1),

the Final Safety Analysis Report (Reference 2), and the Final Environmental Statement (Reference 3) for the SSES.) The purpose of the preoperational REMP (April, 1972 to September, 1982) was to establish a baseline for radioactivity in the local environment that could be compared with the radioactivity levels observed in various environmental media throughout the operational lifetime of the SSES. This comparison facilitates assessments of the radiological impact of the SSES operation.

The SSES REMP was designed on the basis of the NRC's Radiological Assessment Branch Technical Position on radiological environmental monitoring, as described in Revision/1, November 1979.(Reference 4)

Verification of no detrimental effects on public health and safety and the environment from SSES operations, Assessment of dose impacts to the" public, if any, Verification of adequate SSES '

radiological effluent controls, and Identification, measurement,'

'trending, and evaluation' of radionuclides' and their concentrations in critical environmental pathways near the SSES.

203Rdilgca nirneta oitrn Rpr_

2003 Radiological Environmental Monitoring Report Is

I I Introduction However, the REMP conducted by PPL for the SSES exceeds the monitoring suggested by the NRC's branch technical position, as well as the SSES Technical Requirements in terms of the number of monitoring locations, the frequency of certain monitoring, the types of analyses required for the samples, and the achievable analysis sensitivities.

Potential Exposure Pathways The three pathways through which radioactive material may reach the public from nuclear power plants are the atmospheric, terrestrial, and aquatic pathways. (Figure 1 depicts these pathways for the intake of radioactive materials.) Comprehensive radiological environmental monitoring must sample media from all of these pathways.

Mechanisms by which people may be exposed to radioactivity and radiation in the environment vary with the pathway.

Three mechanisms by which a member of the public has the potential to be exposed to radioactivity or radiation from nuclear power plants such as the SSES are as follows:

inhalation (breathing) ingestion (eating and drinking), and whole body irradiation directly from a plant or from immersion in the radioactive effluents.

REMP Scope During the operational period of the SSES, it has been important to establish two different categories of monitoring locations, called control and indicator locations, to further assist in assessing the impact of the station operation.

Control locations have been situated at sites where it is considered unlikely that radiation or radioactive material from normal station operation would be detected. Indicator locations are sited where it is expected that radiation and radioactive material that might originate from the station would be most readily detectable.

Control locations for the atmospheric and terrestrial pathways are more than 10 miles from the station. Preferably, the controls also are in directions from the station less likely to be exposed to wind blowing from the station than are the indicator locations. Control locations for the aquatic pathway, the Susquehanna River, are upstream of the station's discharge to the river.

Indicator locations are selected primarily on the basis of proximity to the station, although factors such as meteorology, topography, and sampling practicality also are considered.

Indicator locations for the atmospheric and terrestrial pathways are typically less than 10 miles from the station.

Most often, they are within 5 miles of the station. Indicator locations in the Susquehanna River are downstream of the station's discharge. Monitoring results from indicator locations are compared with results from control locations. These comparisons are made to discern any differences in the levels and/or types of radioactive material and/or radiation that might exist between indicators and controls and that could be attributable to the station.

In 2003, the SSES REMP collected more than 850 samples at more than 40 6

2003 Radiological Environmental Monitoring Report 6

2003 Radiological Environmental Monitoring Report

Introdtiction locations and performed more than 1,500 analyses. In addition, the REMP monitors ambient radiation levels using.

thermoluminescent dosimeters (TLDs) at 84 indicator and control locations,..

making as many as 336 radiation level measurements each year. The media monitored and analyses performed are summarized in the table below.

Figures 2 through 7 display the REMlvP.

TLDs and sampling locations in the vicinity of the SSES. Appendix C provides directions, distances, and a,'

brief description of each of the locations in Figures 2 through 7.

Regulatory agencies also participate in monitoring the SSES environment and, also oversee PPL's monitoring efforts.. -

The State of Pennsylvania's Department of Environmental Protection (PADEP).

monitors air for radioactive particulates and radioactive iodine. It also monitors milk, fruits and vegetables, surface and drinking water, fish, river sediments, and ambient radiation levels. PADEP makes this data available to the NRC.

Inspectors from the NRC regularly visit the SSES to review procedures and supporting the effluent and environmental monitoring for the SSES.

REMP Monitoring Sensitivity The sensitivity of the SSES REMP was demonstrated in 1986, following the problem with the Chernobyl reactor in the former Soviet Union. When the Chernobyl incident occurred, the SSES REMP was able to detect a relatively small increase in the level of gross beta activity in air samples at both control and indicator locations, as well as the presence of some specific radioactive materials that are not normally.

observed.

Detection of radiation and radioactive material from the SSES in the environment is complicated by the presence of naturally occurring radiation and radioactive materials from both.

terrestrial and cosmic sources. Man-made radiation and radioactive material from non-SSES sources, such as nuclear, fallout from previous nuclear weapons tests and medical wastes, also can make identification of SSES radiation 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 SSES. This effort is further complicated by the natural variations that typically occur from both monitoring location to location and with time at the same locations.

The naturally occurring radionuclides potassium-40, beryllium-7, radium-226, and thorium-228 are routinely observed in certain environmental media.

Potassium-40 has been observed in all monitored media and is routinely seen at readily detectable levels in such media as milk, fish, fruits and vegetables. Seasonal variations in beryllium-7 in air samples are regularly observed. Man-made radionuclides, such as cesium-137 left over from nuclear weapons testing are often observed as well. In addition, the radionuclide tritium, produced by both cosmic radiation interactions in the upper atmosphere as well as man-made (nuclear weapons), is another radionuclide typically observed.

PPL's contracted REMP radioanalytical laboratories are capable of meeting the analysis sensitivity requirements found in the SSES Technical Requirements.

Summary descriptions of the analytical procedures and the accompanying calculational methods used by the laboratories can be found in Appendix E.

Additional terrestrial and aquatic environmental monitoring is performed independent of the SSES REMP by the Academy of Natural Sciences of Philadelphia, Pennsylvania. The monitoring program is titled "Safety Net" and an annual report is provided to PPL Susquehanna, LLC. Although the Safety Net program is not part of the SSES REMP, the data has provided additional information relative to the environmental impact of the operation of the SSES.

j--

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

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2003 Radiological Environmental Monitoring Report

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

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FIGURE 2 2003 TLD MONITORING LOCATIONS WITHIN ONE MILE OF THE SSES a~~~~ MILE

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FIGURE 3 2003 TLD MONITORING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES C-Q
4

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

FIGURE 6 2003 ENVIRONMENTAL SAMPLING LOCATIONS FROM ONE TO FIVE MILES FROM THE SSES o

=

a o

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

Ambient Radiation Monitoring AMBIENT RADIATION MONITORING INTRODUCTION The principal or primary method for the SSES REMP's measurement of ambient radiation levels is the use of thermoluminescent dosimeters (TLDs).,-

The TLDs are crystals (calcium sulfate).-

capable of detecting and measuring low levels of radiation by absorbing a portion of the radiation's energy that is incident upon them and storing the captured energy until the TLDs are processed (read). Processing involves.

heating the TLDs to release their stored energy in the form of light and; measuring the intensity of the light that they emit. The intensity of the emitted light is proportional to the amount of radiation to which they were exposed.

Calibration of the TLD processors permits a reliable relationship to be established between the light emitted -

and the amount of radiation dose received by the TLDs; the result permits accurate measurements of the ambient radiation in the environment.

Environmental TLDs are continually.

exposed to natural radiation from the-.

ground (terrestrial radiation) and fromri the sky (cosmic) radiation. In addition, they also may be exposed to man-made.

radiation. Most of the environmental TLD's natural radiation exposure comes from sources in the ground.. These terrestrial sources vary naturally with.

time due to changes in soil moisture, 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 due to locational differences' in such factors as soil characteristics (amounts of organic matter, particle size, etc.),

drainage opportunities,, and exposure'to sunlight.' Environmental TLDs can also be affected by direct radiation (shine) from the SSES turbine buildings during' operation, radwaste transfer and storagge, and radioactive gaseous effluents from the SSES.

Unfortunately, TLDs do' not have any inherent ability to indicate the source of the radiation to which'they are exposed.

The placement of numerous TLDs in the environment can facilitate decision-'

making about the possible radiation sources'to which TLDs 'are exposed.'

However, a method for evaluating TLD data is still required. ' The SSES REMP relies on a statistically based approach to simultaneously compare indicator TLD data with control TLD data and operational TLD data with' preoperational TLD data. This approach permits the flagging of environmental TLD doses that might' have been produced by both nman-made sources of radiation, as well as natural radiation sources. It also provides a means for attributing a portion of the total TLD dose to SSES operation if appropriate. Appendix E, pages E-6 through E-1O, provides a description'of the process for evaluating the results of TLD measurements.

2003 Environmental Radiological Monitoring Report 16

I I A mbient Radiation iVonitoring Scope TLDs The area around the SSES was divided for monitoring purposes into sixteen sectors radiating outwards. from the plant site, each encompassing an area described by an arc of 22.5 degrees.

TLDs were placed in all 16 sectors at varying distances from the plant.

Monitoring locations were chosen according to the criteria presented in the NRC Branch Technical Position on Radiological Monitoring (Revision 1, November, 1979). The locations for the TLDs were selected by considering factors such as local meteorological, topographical, and population distribution characteristics.

During 2003, the SSES REMP, had 76 indicator TLD locations and eight, control TLD locations. This level of monitoring exceeds that which is required by the Nuclear Regulatory.

Commission. The indicator TLDs nearest the SSES are positioned at the security or perimeter fences surrounding the site. This is the closest that a member of the public would be able to approach the station. The control TLDs are the most distant from the SSES, ranging from 10 to 20 miles from the site.

Monitorin2 Results TLDs TLDs were retrieved and processed quarterly in 2003. Average ambient radiation levels measured by environmental TLDs generally remained constant throughout 2003, as shown in the bar graph on the following page. Refer to Figure 8 which trends both indicator and control data quarterly from 1973 through 2003.

The 2003 annual average exposures for indicator and'control locations were 20.2 mRlstd. qtr. and 19.0 mR/std. qtr.,

respectively. The 2003 exposures are within the ranges of annual averages for the prior operational periods at each type of monitoring location. Refer to Figure 8 at the end of this section which trends quarterly TLD results for both preoperational and operational periods at the SSES. Refer to Appendix H, Table H I, page H 3 for a comparison of the 2003 mean indicator and control TLD results with the means for the preoperational and prior operational periods at the SSES.

Indicator environmental TLD results for 2003 were examined quarterly on an individual location basis and compared with both current control location results and preoperational data. Very small SSES exposure contributions were suggested during 2003 at the following onsite locations: I S2, 6S4, 6S9,7S6,8S2,9S2,10S2,11S3,12S4, 13S2, 13S4, 13S5, 16S1, and 16S2.

Thus, there were 10 monitored locations in 2003 where a SSES dose contribution is considered to have been discernible.

Refer to Appendix E, page E-6, for'a discussion of "TLD Data Interpretation." TLD results for all locations for each quarter of 2003 may be found in Appendix 1, Table I-1, beginning at page 1-2.

17 2003 Environmental Radiological Monitoring Report 17 2003 Environmental Radiological Monitoring Report

Ambient Radiation Monitoring 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.

2003 Environmental Radiological Monitoring Report 18 2003 Environmental Radiological Monitoring Report 18

FIGURE 8 Exposure Rate (mR/STD Qtr)

- AMBIENT RADIATION LEVELS BASED ON TLD DATA 50 45 40 35 30 25 20 15 10 5

0 tmr tt_

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0 0

0 ON

• N I-ON N

N as ON as ON ON 00 ON a,

a C

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4 m4 4

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P.M V

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-Indicator

-Control

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Aquatic Pathwaiy Monitorini

-rAUATICPATHWAYM,,,ONITORING INTRODUCTION The following media were monitored in 2003 by the SSES REMP in the aquatic pathway: surface water, drinking water, fish, and sediment. Some of the media (e.g., drinking water and fish) provide' information that can be especially useful to the estimation of possible dose to the public from potentially ingested radioactivity, if detected. Other media,'

such as'sediment, can be useful for trending radioactivity levels in the aquatic pathway, primarily because of' their tendency to assimilate certain materials that might enter the surface water to which they are exposed. The results from monitoring all of these media provide a picture of the aquatic' pathway that is clearer than that'which' could be obtained if one or more were' not included in the REMP.

Fruits or vegetables that are grown in fields irrigated with surface water would also be in the aquatic pathway. The land use census (Reference 11) conducted in 2003 looked at farms within 10 miles downstream of the SSES. Two farm fields were found to have been irrigated during the 2003 growing season.

The aquatic pathway in the vicinity of the SSES is the Susquehanna River.

Monitoring of all of the aquatic media,'

except drinking water, is conducted' both downstream and upstream of the location from which occasional SSES -

low-level radioactive discharges enter the river. The upstream monitoring locations serve as controls to provide data for comparison with downstream monitoring results. The potential exists for radioactive material that might be present in SSES airborne'releases to enter the Susquehanna River upstream of the plant through either direct deposition (e.g., settling or washout) or by way of runoff from deposition on land adjacent to the river. However, direct deposition and runoff are considered to be insignificant as means of entry for SSES radioactivity into the Susquehanna River when compared to liquid discharges under normal conditions.

Lake Took-a-While (LTAW), which is located in PPL's Riverlands Recreation Area adjacent to the Susquehanna River, is also considered to be part of the aquatic pathway for monitoring purposes. Although it is not in a' position to receive water discharged to the river from the'SSES, it can receive storm runoff from the SSES. Storm' runoff from the SSES site should not normally contain any measurable radioactivity from the plant. However, the SSES REMP, consistent with other aspects of aquatic monitoring and the REMP, in general, goes beyond its requirements by monitoring LTAW.

Scope Surface Water Surface water was routinely sampled from the Susquehanna River at one indicator location (6S5) and one control' location (6S6) at the SSES River Water Intake during 2003. Sampling also took 2003 Radiological Environmental Monitoring Report 20

I I Aquatic Pathway Monitoring' place at the following additional indicator locations:' the SSES discharge line to the river (2S7/6S7) and Lake Took-A-While (LTAW).

Drinking Water Drinking water samples were collected at location 12H2, the Danville Municipal Water Authority's treatment facility on the Susquehanna River, in 2003. Treated water is collected from the end of the processing flowpath, representing finished water that is suitable for drinking. This is the nearest point downstream of the SSES discharge to the River at which drinking water is obtained. No drinking water control location is sampled.' For all intents and purposes, control surface water sampling locations would be suitable for comparison.

Fish Fish were sampled from the Susquehanna River in the spring and fall of 2003 at one indicator location, IND, downstream of the SSES liquid discharge to the River and one control location, 211, sufficiently upstream to essentially preclude the likelihood that the fish caught there would spend any time below the SSES discharge. In addition, fish were also sampled in the fall from PPL's Lake Took-a-While, location LTAW. This location is not downstream of the SSES discharge. It is sampled because of its potential for receiving runoff from the SSES.

LTAW is considered an indicator location.

Sediment Sediment sampling was performed in the spring and fall at indicator locations 7B and 12F and control location 2B on the Susquehanna River. In addition, sediment was also obtained from location LTAW.

Sampling Surfiace Water Weekly grab sampling was performed at the indicator location 6S5. Weekly grab samples were composited both monthly and biweekly at this location. Location 6S5 was considered a backup for locations 2S7 and 6S7 in the event that water could not be obtained from the automatic samplers at these locations.

Nevertheless, 6S5 was sampled routinely throughout 2003, since it is the closest downstream sampling point to the SSES discharge.

Indicator locations 2S7 and 6S7, the SSES Cooling Tower Blowdown Discharge (CTBD) line, and control location 6S6, the SSES River Water Intake structure, were sampled time proportionally using automatic continuous samplers. The samplers were typically set to obtain 30-60 ml aliquots every 20-25 minutes. Weekly, the water obtained by these samplers was retrieved for both biweekly and monthly compositing.

The other surface water monitoring location, LTAW, was grab sampled once each month.

Drinking Water Treated water was sampled time proportionally by an automatic sampler.

The sampler was typically set to obtain three 12-ml aliquots every twenty minutes. Weekly, the water obtained by this sampler was retrieved for both biweekly and monthly compositing.

JH 21 2003 Radiological Environmental Nlonitoring Report 21 2003 Radiological Environmental Monitoring Report

-.1-1-Aquatic Pathvay Monitorinz Fish Fish were obtained by electrofishing. !

Electrofishing stuns the fish and allows them to float to the surface so that those of the desired species and sufficient size can be sampled. Sampled fish include recreationally important species, such as smallmouth bass, and also channel catfish and shorthead redhorse. The fish are filleted and the edible portions are kept for analysis.

Sediment Shoreline sediment was collected to depths of four feet of water.

Sample Preservation and Analysis' I

Surface andDrinking Water Surface and drinking water samples were analyzed monthly for beta activities, the activities of gamma-emitting radionuclides, and tritium activities. Biweekly composite samples.

were analyzed for I-131. In addition, drinking water samples were analyzed.

for gross alpha activity.

The use of nitric acid and sodium.,.

bisulfite as preservatives in surface and drinking water samples was discontinued in 2003 (at the request of the vendor laboratory).

Sediment and Fish Fish are frozen until shipment. All samples are analyzed by gamma spectroscopy for the activities of any gamma emitting radionuclides that may be present.

Monitoring Results Surface Water Results from specific sample analyses of surface water may be found in Tables 1-2 and 1-3 of Appendix I. A summary of the 2003 surface water data may be located in Table G of Appendix G. Comparisons of 2003 monitoring results with those of past years may be found in Tables H 2 through H 4 of Appendix H.

The Nuclear Regulatory Commission (NRC) requires that averages of the activity levels for indicator; environmental monitoring locations and for control environmental monitoring locations of surface water, as well as other monitored media, be reported to the NRC annually. Data from the following three surface water.

monitoring locations were averaged together as indicators for reporting,;

purposes: one location (6S5) on the Susquehanna River downstream of the SSES, Lake-Took-a While (LTAW) adjacent to the river, and the SSES cooling tower blowdown discharge, (CTBD) line to the river (2S7).

Technically, the CTBD line is not part of the environment. The CTBD line is a below ground pipe to which the public has no access, contrary to the other.

environmental monitoring locations on the Susquehanna River to which the public does have access. However;,

currently there is no automatic composite sampling of an indicator location on the Susquehanna River, so the CTBD line from the SSES is included as an indicator monitoring 2003 Radiological Environmental Monitoring Report 22 2003 Radiological Environmental Monitoring Report 22

I'I Aquatic Pathway Monitoring location in the radiological environmental monitoring program.

Most of the water entering the Susquehanna River through the SSES CTBD line is simply water that was taken from the river upstream of the SSES, used for cooling purposes without being radioactively!

contaminated by SSES operation, and returned to the river. Nevertheless, batch discharges of relatively small volumes of slightly radioactively contaminated water are made to the river through the SSES CTBD at times throughout each year. The water is released from tanks of radioactively contaminated water on site to the CTBD and mixes with the noncontaminated water already present in the CTBD.

Flow rates from the tanks containing radioactively contaminated water being discharged to the CTBD vary based on the radioactivity level of the batch release. In addition, the minimum flow rate for the returning water in the CTBD is maintained at a flow rate of 5,000 gpm or higher. These requirements are in place to ensure adequate dilution of radioactively contaminated water by the returning noncontaminated water in the CTBD prior to entering the river.

At the point that CTBD water enters the river, additional, rapid dilution of the discharged water by the river is promoted by releasing it through a diffuser. The diffuser is a large pipe with numerous holes in it that is positioned near the bottom of the river.

CTBD discharges exit the diffuser through the many holes, enhancing the mixing of the discharge and river waters. The concentrations of contaminants are reduced significantly as the discharged water mixes with the much larger flow of river water. The mean flow rate of the Susquehanna River in 2003 was approximately 9,910,000 gpm.' This is more than 1,900 times the required minimum flow rate through the CTBD for discharges to be permitted.

The amounts of radioactively contaminated water being discharged are small. Nevertheless, sensitive analyses of the water samples can often detect the low levels of certain types of radioactivity in the CTBD water following dilution. Though the levels of radioactivity measured in the CTBD water are generally quite low, they tend to be higher than those in the river downstream of the SSES. Most radionuclides discharged from the SSES CTBD are at such low levels in the downstream river water that, even with the sensitive analyses performned, they cannot be detected.

When the radioactivity levels from the CTBD samples throughout the year are averaged with those obtained from actual downstream monitoring locations, the result is an overall indicator location average that is too high to be'representative' of the actual average radioactivity levels of the downstream river water. As the following discussions are reviewed, consideration should be given to this inflation of average radioactivity levels from the inclusion of CTBD (location 2S7/6S7) results in the indicator data that is averaged.

The 2003 data for gross beta activity analyses of surface water indicator locations is higher than those of 2002.

I, 23 2003 Radiological Environmental Monitoring Report 23 2003 Radiological Environmental Monitoring Report

Aquatic Pathway Monitoring The 2003 !mean gross beta 'activity of 6.1 pCiAiter for indicator locations is' greater than the 2002 indicator mean gross beta activity of 5.4 pCiAiter. The' 2003 indicator mean activity is within the range of the annual means for the previous operational period of the SSES. The 2003 mean gross beta activity of 2.4 pCiAiter for control locations is less than the 2.9 pCilliter for the 2002 control mean gross beta activity. The 2003 control mean activity is within the range of the annual means for previous operational periods.

The 2003 control mean is below the" range of annual means for preoperational periods. 'Refer to Figure 9 which trends gross beta activities separately for surface water.

indicator and control locations quarterly from 1975 through 2003.

Comparison of the 2003 indicator mean (6.1 pCi/l) to the 2003 control mean (2.4 pCi/1) suggests a contribution of beta activity from the SSES. The 2003 data is similar in this regard to the averages of annual means for indicator and control locations for the prior operational period. 'During the pior operational period, the average of annual indicator means exceeds the average of annual control means for gross beta activity.

The 2003 means for iodine-131'activity' at indicator and control surface water moitoring location's wee0.36 pCi/liter monitrn loaton were 03 ~/ie and 0.26 pCi/liter, respectively. The 2003 indicator and control means are less than the corresponding 2002 means.;

The 2003 indicator mean activity is greater than the averages of the annual' means for indicator locations for the' prior operational and preoperational periods of the SSES. The 2003 control mean activity is less than the averages of the annual means for control locations for the prior operational and preoperational peiiod of the SSES.

Throughout the course of a year, iodine-131 is typically measured at levels in excess of analysis MDCs in some samples obtained from control surface water monitoring locations on the Susquehanna River upstream of the' SSES as well as indicator locations downstream of the SSES. 'As determined by measurements of samples obtained by the SSES REMP, the mean iodine-131 activity level from the CTBD for all of 2003 was approximately 0.78 pCi/liter. This may be compared to the activity level of 0.26 pCi/liter for control surface water monitoring locations in 2003.

Iodine-131 from the discharge of medical wastes into the Susquehanna River upstream of the SSES is drawn into the SSES cooling tower basins" through the SSES River Water Intake Structure. It is reasonable to assume that concentration of the already existing io'dine-131 in the cooling tower basins occurs as it does for other' substances found in the river. For example, the SSES routinely assumes concentration'factors in the basin for calcium of four to five times the concentrations in the river water entering the basins, based on past measuremnents. This concentrating:

effect occurs because of the evaporation' of the water in the basins, leaving behind most dissolved and suspended materials in the unevaporated water remaining in the basins. If a concentration factor of four for iodine-2003 Radiological Environmental Monitoring Report 24 2003 Radiological Environmental Monitoring Report 24

I I Aquatic Path way Monitorine 131 were to be applied to the 2003 mean iodine-131 activity level for the control samples from the Susquehanna River, a mean concentration of 1.04 pCi/liter for iodine-131 in the basin water and the water being discharged from the basins would be expected. The actual 2003 mean of 0.78 pCi/liter for the CTBD iodine-131 activity level was less than this.

Because iodine-131 is radioactive, unlike the calcium that has been measured, iodine-131 is removed from the water while it is in the basins through the radioactive decay process.

Thus, it might be expected that the net concentration factor for iodine-131 would be somewhat less than that for calcium, considering this additional removal process. The extent to which the iodine-131 concentration factor is less than that for calcium would depend on the mean residence time for the water in the basins compared to iodine-131 's radioactive half-life - the greater the ratio of the mean residence time to the half-life, the smaller the concentration factor. A mean residence time for water in the basins is expected to be about two days. This is only about one-fourth of the approximately eight-day half-life of iodine-131. Thus, radioactive decay would not be expected to reduce the concentration factor for iodine-131 by a large amount.

Therefore, the difference between the 2003 mean iodine-131 activity of about 0.78 pCi/liter in the CTBD and the 2003 mean iodine-131 activity for the control location of 0.26 pCi/liter should be the result of concentration in the basins.

Iodine-131 was not reported to have been discharged with water released from the SSES to the Susquehanna River during 2003.

The 2003 mean tritium activity for indicator locations is more than the corresponding 2002 mean. The 2003 means for tritium activity at indicator and control locations were 1,567 pCi/liter and 31.8 pCi/liter, respectively. The 2003 indicator mean is greater than the annual average mean for prior operational and preoperational periods of the SSES. Note that the 2003 mean tritium activity at indicator locations is higher than the range for both operational and preoperational periods. The control mean is 'within the range of the corresponding annual mean reported for the prior operational period of the SSES. Refer to Figure 10 which trends tritium activity levels separately for surface water indicator and control locations from 1972 through 2003.

The 2003 indicator mean tritium level for all surface water locations can be misleading for those interested in the mean tritium level in the Susquehanna River downstream of the SSES for 2003. The much higher levels of tritium observed in the CTBD line (location 2S7/6S7), when averaged with the low levels from the downstream location 6S5 sample analysis results distort the real environmental picture. The mean tritium activity level from indicator location 6S5 for 2003 was 140 pCi/liter, which is greater than the mean tritium activity, 31.8 pCi/liter, for the control location, but is within the range of prior operational' and preoperational periods.

In spite of the fact that the tritium activity levels reported for 2S7/6S7 are from the discharge line prior to dilution 25 2003 Radiological Environmental Monitoring Report 25 2003 Radiological Environmental Monitoring Report

- Aquatic Pathiwav Monitorine in the river, the highest quarterly average tritium activity reported at 2S7/6S7 during 2003 was' approximately 6,990 pCi/liter for the first quarter, well below the NRC non-routine reporting levels for quarterly' -"

average activity levels of' 20,000 pCi/liter when a drinking water pathway exists or 30,000 pCi/liter when no drinking water pathway exists.,

The tritium activity reported in the CTBD line from location 2S7/6S7 is,'

attributable to the SSES. Refer to the "Dose from the Aquatic Pathway" discussion at the end of this section for additional information'on the projected dose to the population from fritiuhiand other radionuclides in the aquatic pathway attributable'to' the SSES.

With the following exceptions, no gamma-emitting radionuclides were -

measured in surface water primary samples at an activity level exceeding an analysis MDC in 2003: potassium-40 and iodine-131.

Drinking Water Drinking water was monitored during 2003 at the' Danville Water Compay's facility 26 miles WSW ofthe SSES on, the Susquehanna River. Fromi 1977- ;

(when drinking water samples were first collected) through 1984, drinking 'vatei samples were also 'obtaine6d from the"`

Berwick Water Company at location"'

12F3,' 5.2 miles WSW of the SSES.

The drinking water suoply for the' Berwick'Water Company is not,,

however, water from the Susquiehanna "

River; it is actually well water r.-

"e There are no known drinking water supplies in Pennsylvania on the Susquehanna River upstream of the SSES and therefore no drinking water control monitoring locations. Danville' drinking water analysis results may be compared to the results for surface water control monitoring locations.

Results from specific sample analyses of drinking water may be found in Table I-4 of Appendix 1. A summary of the 2003 drinking water'data may be located in Table G of Appendix G.

Comparisons of 2003 monitoring results with those of past years may be found in Tables H 5 through H 7 of Appendix H.'

Gross alpha activity has been monitored in' drinking water since 1980. Gross alpha activity has been observed at levels above the analysis MDCs in a small minority of the samples during most years since 1980. The 2003 -mean gross alpha activity level for.drinking water was 0.18 pCi/liter. The 2003 mean alpha activity level is within the range of the corresponding annual means for the prior operational years.

No gross alpha activity in drinking water during 2003 is attributed to liquid discharges from the SSES to the' Susquehanna River.

Gross beta activity has been monitored' in drinking water since 1977. '.Gross beta activity is typically measured at levels exceeding the MDCs in drinking water samples. The 2003 nmean gross beta activity level for drinking water was 2.13 pCi/liter. The 2003 me'an is below the 2002 mean gross beta activity level for drinking water but within the' range of the corresponding annual means for prior operational periods.

The 2003 mean is below the range of the'corresponding annual means for 2003 RailgclEvrnetlntrn eot2 2003 Radiological Environmental Monitoring Report 26

I I Aquatic Path way Afonitoring preoperational periods. Refer to Figure I1 which trends'gross beta activity levels separately for drinking water indicator and control locations' from 1977 through 2003. No gross beta activity in drinking water during 2003 is attributed to liquid discharges from the SSES to the Susquehanna River.

Iodine-1 31 was measured in excess of analysis MDCs in 2 out of 26 drinking water samples in 2003. This compares with results from 6 samples for which analysis MDCs were exceeded in 2002.

The 2003 mean iodine-131 activity level in drinking water samples was 0.18 pCi/liter. This is less than the 2002 mean drinking water activity level of 0.22 pCi/liter. Also, it is less than the 2003 mean of 0.26 pCi/liter for the surface water control location. No iodine-131 activity in drinking water during 2003 is attributed to liquid discharges from'the SSES to the Susquehanna River.

Tritium was measured in excess of analysis MDCs twice in 2003 in drinking water.. The 2003 mean tritium activity level for drinking water was 62 pCi/liter. The 2003 mean is equal to the averages of the corresponding annual means for both the prior operational and preoperational periods of the SSES. The 2003 mean tritium activity level for drinking water is higher than the 2003 mean tritium activity level for the surface water control location. Tritium activity in drinking water can be attributed to liquid discharges from the' SSES to the Susquehanna River.

With the exception of I-13.1, no gamma-emitting radionuclides were measured above the analysis MDCs for gamma spectroscopic analyses of drinking water samples during 2003.

Fish Results from specific sample analyses of fish may be found in Table I 5 of Appendix 1. A summary of the 2003 fish data may be located in Table G of Appendix G. A comparison of 2003 monitoring results with those of past years may be found in Table H 8 of Appendix H.

Three species of fish were sampled at each of one indicator location and one control location on the Susquehanna River in May 2003 and again in October 2003. The species included the following: smallmouth bass, channel catfish, shorthead redhorse,'and white sucker. In addition, one largemouth bass was sampled from PPL's LTAW.

A total of 13 fish were collected and analyzed.

The only gamma-emitting radionuclide reported in excess of analysis MDCs in fish during 2003 was naturally occurring potassium-40. The 2003 indicator and control means for the activity levels of potassium-40 in fish were 3.57 pCi/gram and 3.16 pCi/gram, respectively. The 2003 indicator and control means were less than the 2002 means. Both the 2003 indicator and control means are within the ranges of their corresponding annual means for prior operational years. The 2003 indicator mean is greater than the range of corresponding annual means for preoperational periods. The 2003 control mean is within the range of corresponding annual means for preoperational periods. Naturally Ji 27 2003 Radiological Environmental Monitoring Report 27 2003 Radiological Environmental Monitoring Report

Aquatic Path way Afonitorinj occurring potassium-40 in fish is not attributable to the liquid discharges from the SSES to the Susquehanna River.

Sediment Shoreline sediment was sampled in May 2003 and again in October 2003.

Results from specific sample analyses of sediment may be found in Table I-6 of Appendix I. A summary of the 2003 sediment data is located in Table G of Appendix G. Comparisons of 2003 monitoring results with those of past years may be found in Tables H 9 through H 12 of Appendix H.

Naturally occurring potassium40, radium-226, and thorium-228 were measured at activity levels above analysis MDCs in all shoreline sediment samples in 2003.

The 2003 indicator and control means for potassium-40 activity levels in shoreline sediment were 12.3 pCi/gram and 12.9 pCi/gram, respectively. :The 2003 indicator mean for potassium40 activity is less than the corresponding 2002 mean. The 2003 control mean is greater than the corresponding 2002 mean. The 2003 indicator and control means were within the ranges of corresponding annual means for all prior operational years.

The 2003 indicator and control means were greater than the ranges of corresponding means for preoperational periods.

The 2003 indicator and control means for radium-226 activity levels in shoreline sediment were 2.38 pCi/gram and 1.6 pCi/gram, respectively. The 2003 indicator mean radium-226 activity is higher than the corresponding 2002 mean. The 2003 control mean radium-226 activity is lower than the corresponding 2002 means. The 2003 radium-226 mean was above the range of corresponding annual means for all prior operational years. The 2003 control mean was within the range of corresponding annual means for all prior operational years.

The 2003 indicator and control means for thorium-228 activity levels in shoreline sediment were 3.2 and 3.0 pCi/gram, respectively. The 2003 indicator and control means are higher than the corresponding 2002 means.

The 2003 indicator and control means are greater than the range of corresponding means for prior operational years. The naturally occurring radionuclides in sediment discussed above are not attributable to the liquid discharges from the SSES to the Susquehanna River.

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

2003 Radiological Environmental Monitoring Report 28 2003 Radiological Environmental Monitoring Report 28

I I Aquatic Pathway Monitorinz Dose from the Aquatic Pathway Tritium was the only radionuclide identified in 2003 by the SSES REMP in the aquatic pathway that was attributable to SSES operation and also included in the pathway to man.

The total tritium activity released from the SSES for the year was estimated based on REMP monitoring results for use in projecting maximum doses to the public. This estimate assumed that the tritium was present continuously in the CTBD line throughout 2003 at a level equivalent to the annual mean activity level of tritium. It was also assumed that the annual average activity level of tritium being contributed to the Susquehanna River water could be represented by the difference between the annual mean activity levels of tritium in the CTBD line (without correction for cooling tower basin reconcentration) and in the river upstream of the SSES.

The annual mean activity level of tritium in the CTBD line (monitoring location 2S7\\6S7) for 2003 was 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.

This estimate is 3 curies less than the amount of tritium determined by effluent monitoring to have been released to the river by the SSES in 2003. This agreement between the estimate based on environmental monitoring and the amount reported by effluent monitoring is consistent with previous years comparisons.

J Given the total tritium activity released, the maximum whole-body and organ doses to hypothetical exposed individuals in four age groups (adult, teenager, child, and infant) were determined according to the methodology of the Offsite Dose Calculation manual using the RETDAS computer program. This is in accordance with SSES Technical Requirement 3.11.4.1.3.

The maximum dose obtained from the ingestion of tritium was estimated at the nearest downriver municipal water supplier via the drinking water pathway and near the outfall of the SSES discharge to the Susquehanna River via the fish pathway. The maximum whole body and organ doses were each estimated to be approximately 0.0015 mrem.

.S 29 2003 Radiological Environmental Monitoring Report 29 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

e e

e

,4 f

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 Pathway MonitorinR ATMOSPHERIC ATHWAY MONITORING-'".,

C.. 1, -

Sampling and Anialysis INTRODUCTION Atmospheric monitoring by the SSES REMP involves the sampling and analysis of air. Because the air is the first medium that SSES vent releases

{

enter in the pathway to man, it is fundamental that it be monitored.

Mechanisms do exist for the transport of airborne contaminants to other media and their concentration in them. For example, airborne contaminants may move to the terrestrial environment and concentrate in milk. Concentrations of radionuclides can make the sampling and analysis of media like milk more sensitive approaches for the detection of.

radionuclides, such as iodine-131, in the pathway to man than the monitoring of, air directly. (PPL also samples milk; refer to the Terrestrial Pathway Monitoring section of this report.)

Nevertheless, the sensitivity of air monitoring can be optimized by the proper selection of sampling techniques and the choice of the proper types of.,

analyses for the collected samples.

Air The SSES REMP monitored the air at four indicator locations and two control locations durin'g 2003. The SSES Technical Requirements require monitoring at'only a total of five sites.

Monitoring is required at three locations.

at the SSES site'boundary in different sectors with the greatest predicted sensitivities for the'detection of SSES releases. Monitoring must be performed at the community'in the'vicinity of the SSES with the greatest predicted sensitivity. A control l6cation that is expected to be u niffected by any routine SSES releases must be monitored.

Airborne particulates were collected on glass fiber filters' using low volume.

(typically 2.0 to 2.5 cfm sampling rates) air samplers that run continuously. Air iodine samples were collected on' charcoal cartridges, placed downstream of the particulate filters.

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

Air sample volumes for particulate filters and charcoal cartridges were measured with dry-gas meters.

Scope Air samples were collected on particulate filters and charcoal cartridges at indicator locations 3S 12S1, 13S6 and 12E1, and control locations 6G1 and 8G1.

2, r

.1 I

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.

203Rdooia. niometlMntrn eot3 2003 Radiological Environmental Monitoring Report 33

I I Atmospheric Pathway Monitoring Monitoring Results Air Particulates Gross beta activity is always measured at levels in excess of the analysis MDCs on the fiber filters. The highest gross beta activity levels that have been measured during the operational period of the SSES were obtained in 1986 following the Chernobyl accident in the former Soviet Union. Figure 12 trends the quarterly mean gross beta activities for the indicator and control locations separately from 1974 through 2003.

Note that prior to SSES operation, before 1982, the unusually high gross beta activities were generally attributable to fallout from atmospheric nuclear weapons tests. Typical gross beta activities measured on air particulate filters are the result of naturally occurring radionuclides associated with dust particles suspended in the sampled air. They are thus terrestrial in origin.

Particulate gross beta activity levels for each monitoring location and monitoring period in 2003 are presented in Table I-8 of Appendix I.

Comparisons of 2003 gross beta analysis results with those of previous years may be found in Table H 13 of Appendix H. For 2003, the annual means for the beta activities of the indicator and control locations are 1.47E-2 pCi/nm3 and 1.34E-2 pCi/mI3, respectively. These are near the low end of the corresponding ranges of previous operational yearly averages. They are significantly below the corresponding lower ends of their preoperational yearly averages. A contribution of radioactivity from the SSES may be suggested from the 2003 airborne gross beta data based on the higher mean activity reported for indicator location.

The SSES Technical Requirements Manual requires radionuclide analysis if any weekly gross beta result was greater than ten times the yearly mean of control sample results. This condition did not occur during 2003.

Quarterly gamma spectroscopic measurements of composited filters often show the naturally occurring radionuclide beryllium-7. Occasionally, other naturally occurring radionuclides, potassium-40 and radium-226, are also observed. Beryllium-7 is cosmogenic in origin, being produced by the interaction of cosmic radiation with the earth's atmosphere. The other two gamma-emitting radionuclides originate from soil and rock.

Beryllium-7 was measured above analysis MDCs for all quarterly composite samples in 2003. The 2003 indicator and control means for beryllium-7 activity were

9. 1OE-2 pCi/m.3, and 8.20E-2 pCi/M3, respectively. The 2003 means are lower than the corresponding 2002 means.

The 2003 indicator and control means were lower than the averages of the corresponding annual means for the prior operational and preoperational periods. Beryllium-7 activity levels for each 2003 calendar quarter at each monitoring location are presented in Table 1-9 of Appendix I. Comparisons of 2003 beryllium-7 analysis results with previous years may be found in Table H 14 of Appendix H. Potassium-40 was measured above analysis MDCs for one quarterly composite sample during 2003 (control location 6G1).

34 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

4 4 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

Terrestrial Pathway MonitorinjR

-IN-TERRESTION

PTT'W-YAT MONITORING-INTROD~UCTION----

The following media were monitored in the Terrestrial Pathway in 2003: soil, milk, fruits and vegetables.

Soil can be a great accumulator of man-made radionuclides that enter it. The' extent of the accumulation in the soil depends of course on the amount of the,.

radionuclides reaching it, but it also depends on the chemical nature of those radionuclides and the particular characteristics of the soil. For example,';

the element cesium, and, therefore, cesium-137 can be bound very tightly to clay in soils. The amount of clay in s6il can vary greatly from' one location to another. In clay soils, cesium-137 may' move very slowly and also may be taken' up very slowly in plants as they absorb soil moisture.

Any medium, such as soil, that tends to accumulate radioactive materials 'can also provide more sensitivity for radionuclide detection in the environment than those media that don't. Such a medium facilitates the early identification of radionuclides in l! ';

the environment, as well as awareness' of changes that subsequently may occur in the environmental levels of the' identified radionuclides.

The SSES REMP samples'soil near four of the six REMP air sampling stations. '

The purpose for soil sampling near the'i air sampling sites is to make it easierit'o""

correlate air sampling results with soil' sampling results if any SSES related radioactive material were found in either medium. Sampling is performed at different depths near the surface to help provide information on how recently certain radioactive materials may have entered the soil: Sampling at more than one depth also may help ensure the detection of materials that move relatively quickly through the soil.

Such quick-moving materials may have already passed through the topmost layer of soil at the time of sampling.

Milk was sampled at four locations and fruit and vegetable samples were obtained at 2 locations in 2003. SSES Technical Requirements require that the SSES REMP'samnple milk at the three most sensitive monitoring locations near the SSES and one control location distant from the SSES. SSES Technical Requirements only require that fruit and vegetables be sampled at locations irrigated by Susquehanna River water from points downstream of the SSES discharge to the River. There are only:

three locations withinr 10 miles downstream of the SSES that have been' known to irrigate with water from the Susquehanna River during unusually dry periods. These locations do not irrigate every year. Irrigation was performed at the Chapin Farms "Drake Field" (1 1F2) and the Lupini Farm "Route 93 Nescopeck Field" (11D2),

during 2003 as identified by the 2003 Land Use Census (Reference 11).

No requirement exists for the SSES REMP to monitor soil. All monitoring of the terrestrial pathway that is conducted by the SSES REMP in 200 R-iloia Eniomna oitrn eot3 2003 Radiological Environmental Monitoring Report 37

I I Terrestrial Pathway Monitoring addition to milk and certain fruit and vegetables is voluntary and reflects PPL's willingness to exceed regulatory requirements to ensure that the public and the environment are protected.

Scope Soil Soil was sampled in September 2003 in accordance with its scheduled annual sampling frequency, at the following four REMP air sampling locations, 3S2, 12S1, 13S6, and 8G1. Location 8G1 was a control sampling location; the remaining sampling sites were indicator locations.

Twelve soil plugs were taken at selected spots at each monitoring location. The plugs were separated into "top" (0-2 inches) and "bottom" (2-6 inches) segments. Each set of top and bottom segments was composited to'yield 2 soil samples from each location for analysis.

Since there are four monitoring locations, a total of 8 soil samples were analyzed in 2003.

Fruits and Vegetables Potatoes were sampled during the harvest season at 2 locations surrounding the SSES. A total of 2 samples were collected from locations I 1D2, and I 1F2.

Both locations were identified as having irrigated with Susquehanna River water from downstream of the SSES during 2003. There are often years with adequate rainfall when no irrigation is performed.

Sample Preservation and Analysis All media in the terrestrial pathway are analyzed for the activities of gamma-emitting radionuclides using gamma spectroscopy. The other analysis that is routinely performed is the radiochemical analysis for iodine-131 in milk. The use of sodium bisulfite as a preservative in milk samples was discontinued in 2003 (at the request of the vendor laboratory).

I Milk Milk was sampled at least monthly at the following four locations in 2003:

10D1, 10D2, 12B2 and 10Gi.

Milk was sampled semi-monthly from April through October when cows were more likely to be on pasture. Locations IODI, 10D2, and 12B2 are believed to be the most sensitive indicator sites available for the detection of radionuclides released from the SSES.

Location IOGI is the control location. A total of 76 milk samples from both indicator and control locations were analyzed in 2003.

Monitoring Results The only man-made radionuclides normally expected at levels in excess of analysis MDCs in the terrestrial pathway are strontium-90 and cesium-137. Both of these radionuclides are' present in the environment as a residual from previous atmospheric nuclear weapons testing.

Strontium-90 analyses are not now routinely performed for any media samples in the terrestrial pathway.

Strontium-90 activity would be expected to be found in milk. SSES Technical Requirements do not require 2003 Radiological Environmental Monitoring Report 38

Terrestrial Pathway Monitoinz 2

that milk be analyzed for strontium-90.

Strontium-90 analyses may be' performed at any time if the results of other milk analyses would show.

detectable levels of fission product activity which might suggest the SSES as the source.

Cesium-137 normally has been measured in excess of analysis MDCs in most soil samples.'Although game is_

not currently'being monitored, cesium-137 has also been'seen often at levels above the MDCs in game in the past.

Certain naturally occurring radionuclides are also routinely found above analysis MDCs in terrestrial' pathway media. Potassium-40, a primordial and very long-lived radionuclide, which is terrestrial in' origin, is observed in all terrestrial pathway media. Other naturally occurring'radionuclides often observed are thorium-228 and radium-226 in soil,-

and beryllium-7 in fruits and vegetables.

The results of the 2003 terrestrial pathway monitoring resemble those of the past; Results for specific sample analyses of terrestrial pathway media '

may be found in Tables 1-10 through I-12 of Appendix I. A summary of the.

2003 terrestrial monitoring data may be "'

located in Appendix G. Comparisons of 2003 monitoring results with those of :;!

past years may be found in Tables H 15.;

through H 19 of Appendix H.

Soil.

The following gamma-emitting radionuclides are routinely measured in'.

soil at levels exceeding analysis MDCs:

naturally occurring potassium-40, radium-226, and thorium-228 and man-made cesium-137. The 2003 analysis results were similar to those for previous years. No other gamma-emitting radionuclides were reported at levels above analysis MDCs.

The 2003 means for indicator and control location sample potassium40 activity were 14.4 pCi/gram and 10.6 pCi/gram, respectively. The indicator and control means are within the range of corresponding means for both prior operational and preoperational years. This is not the result of SSES operation because the potassium-40 is naturally occurring. The 2003 indicator and control means for potassium-40 were greater than the corresponding 2002 means.

Ra-226 analysis of soil samples was deleted from the SSES REMP in 2002.

Ra-226 was not performed on any soil samples in 2003 and has been discontinued from the SSES REMP soil sample analysis library.

The 2003 means for indicator and control location sample thorium-228 activity were both 0.8 pCi/gram. The 2003 indicator mean is equal to the corresponding 2002 mean. -The 2003 control mean for thorium-228 is greater than the corresponding 2002 mean. The indicator and control means are within the ranges of the corresponding means for both the previous operational and preoperational periods, as applicable, of.

the SSES. Thorium-228 in soil is not the result of SSES operation because it is naturally occurring.

The 2003 means for indicator and control location sample cesium-137 activity were 0.04 pCi/g and 0.07 pCi/g, respectively. The 2003 indicator mean is within the range of the corresponding 39 2003 Radiological Environmental Monitoring Report 39 2003 Radiological Environmental Monitoring Report

I I Terrestral Pathway Monitorinj annual means for prior operational years. The 2003 indicator mean is below the ranges of the corresponding means for preoperational years. The 2003 control mean is below the ranges of the-corresponding annual means for both prior operational and preoperational years. Cesium-137 levels in soil samples typically vary widely from sample to sample. Levels of cesium-137 activity in 2003 samples varied by a factor of four over the entire range.

Cesium-137 in soil, although man-made, is not from the operation of the SSES. It is residual fallout from previous atmospheric nuclear weapons testing.

Milk Iodine-131 has been chemically separated in milk samples and counted routinely since 1977. Refer to Figure 13 which trends iodine-131 activity in milk for indicator and control locations separately from 1977 through 2003.

Typically, iodine-131 is not reported at levels exceeding the MDCs for the analyses in any milk samples during a monitored year. The 2003 monitoring year was no exception; no iodine-131 above the analysis MDCs was observed in either indicator or control samples.

The preoperational years 1976, 1978, and 1980 were exceptional years in the sense that iodine-131 activity was observed in excess of MDCs due to fallout from atmospheric nuclear weapons testing. Iodine-13 1. activity was also measured at levels exceeding MDCs in milk samples in 1986 in the vicinity of the SSES as a result of the Chernobyl incident.

With the exception of the naturally occurring potassium-40, no gamma-emitting radionuclides were measured in excess of analysis MDCs in 2003.

The 2003 means for indicator and control location sample potassium40 activity were 1383 pCi/liter and 1406 pCi/liter, respectively. The 2003 indicator mean is less than the 2002 mean. The 2003 control mean is greater than the corresponding 2002 mean. The 2003 indicator and control means for potassium40 activity are within the corresponding ranges of annual means for previous operational and preoperational years. The potassium-40 activity in milk is not attributable to the SSES operation because it is naturally occurring.

Fruits and Vegetables Naturally occurring potassium-40 was the only gamma-emitting radionuclide measured in fruits and vegetables at an activity level in excess of analysis MDC during 2003.

Due to excessive rainfall during the 2003 growing season, fruits and/or vegetables were only sampled twice, both from indicator locations. The 2003 indicator location sample potassium-40 activity mean was 4.6 pCi/gram. The 2003 indicator mean is higher than its corresponding 2002 mean. The 2003 indicator mean is above the range of the corresponding annual means for pre-operational and prior operational years.

Potassium-40 in fruits and vegetables is not attributable to SSES operation because it is a naturally occurring radionuclide.

2003 Radiological Environmental Monitoring Report 40 2003 Radiological Environ-mental Monitoring 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< ^,959 ^,,9,9

<,9

,9&

,<,9o9 99>

993 99t 98\\

999 Ad 0 Indicator El Control

Ground Water Monitoring -

i4?

ae f

GROUND,WTER D-iAMN1T0RIN.-

INTRODUCTION..

Normal operation of the SSES does not involve the release of radioactive material to ground water directly or -

indirectly through' the ground. As a -

result, there are no effluent monitoring, data to compare with REMP ground water monitoring results. Ground water could conceivably become contaminated by leakage or spills from the plant br by the washout or, deposition of radioactive material that might be airborne. If deposited on the ground, precipitation/soil moisture could aid in'the movement of radioactive materials through the.

ground to water that could conceivably be pumped for drinking purposes. No".'

use of ground water for irrigation near the SSES has been identified.

Because routine SSES operation releases primarily tritium and, to a lesser extent, isotopes of xenon and krypton to the air, no radionuclides attributable to SSES operation are expected to be observed in ground water. Iodine and particulate releases to the air are negligible. Gaseous xenon and krypton tend to remain airborne, deposition or washout of these would be expected to be very minimal. Tritium would be the most likely radionuclide to reach the ground with precipitation and, if not lost to streams (surface water) by runoff, move readily through the soil to the ground water.

Scope -

Ground water in the SSES vicinity was sampled monthly at 2 indicator locations (2S2 and 4S4) and one control location (12F.3) during 2003.

With the exception of location 4S4,.

untreated ground water was sampled.

Untreated means that the water has not undergone any processing such as filtration, chlorination, or softening. At location 4S4, the SSES Training Center, well water actually is obtained from on-site and piped to the Training Center after treatment. This sampling is performed as a check to ensure thai water has not been radioactively, contaminated. Sampling is performed at the Training Center to facilitate the sample collection process.

Sample Preservation &

Analysis Ground water samples were analyzed for the'activities of gamma-emitting radionuclides'and tritium activity.

Gamma spectromnetric'analyses of ground*w'ater were begunfinm 1979 and tritium analyses in 1972, both prior to SSES operation.: The use of nitric'acid as a preservative in ground water' samples was discontinued in 2003'(at the request of the vendor laboratory).

2003 Radiological Environmental Monitoring Report 42

I I Ground Water Monitoring Monitoring Results Tritium activity levels in ground water have typically been observed to be lower than in surface water. A noticeable decline occurred between 1992 and 1993. Fewer measurements were above the analysis sensitivities in 1993 than in 1992.

Gamma-emitting radionuclides in excess of MDCs have been found in only a few samples in all the years that these analyses have been performed.

The naturally occurring radionuclides potassium-40 and thorium-228 have been measured above their MDCs occasionally in ground water.

Potassium40 was reported in 1979, 1981, 1985, 1991, 1992, 1993, and 1997. Thorium-228 was found in 1985 and 1986. The man-made radionuclide cesium-137 has been detected only occasionally since 1979. Its presence has always been attributed to residual fallout from previous atmospheric nuclear weapons tests.

indicator and control means are lower than those for 2002. Both the 2003 indicator and control mean tritium activity levels are within the range of corresponding averages of annual means for prior operational years. The 2003 indicator mean tritium activity is lower than the corresponding means for preoperational years. The 2003 control mean is within the range of corresponding means for preoperational years.

Naturally occurring potassium-40 was measured in excess of analysis MDCs in 2 ground water samples during 2003.

No man-made gamma-emitting radionuclides were determined to be at levels in excess of analysis MDCs. No radioactivity contributions to ground water from the SSES were identifiable in 2003.

I 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.

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

44

e S

r- -;

I I

,. 1

-l APPENDIX A 3

N

~

1-'J',

I 1

i..1.:

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

I I Appendix A REMP Sample Analyses 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.

\\J)

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 2003 Radiological Environmental Monitoring Report A.2 2003 Radiological Environmental Monitoring 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 Environmental Monitoring Report A-3 2003 Radiological Environmental Monitoring Report

APPENDIX B W~

203RM

ts'-'e,.Z03t-EMONITORITNG SCEDUEE

't -rg' tiw.s.+'. s -'-'/";..-9o-'SAL NAL SIS) 2003 Radiological Environmental Monitoring Report B-i 2003 Radiological Environmental Monitoring 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 Particulates 6

W Gross Beta (c)

Gamma Spectrometry W

QC Airborne Iodine 6

W 1-131 W

Sediment 4

SA Gamma Spectrometry Gamma Spectrometry (on edible portion)

SA SA Fish 2

1 SA A

Surface Water (d) 4 MC, M, or Gross Beta BWC 1-131 Gamma Spectroscopy Tritium M

BW M

M Well (ground)

Water 3

M Gamma Spectroscopy Tritium M

M iJ Drinking Water (e)

I MC, BWC Gross Alpha Gross Beta 1-131 Gamma Spectrometry Tritium Cow Milk 4()

M, SM V)

Food Products (Potatoes) 2 A

1-131 Gamma Spectrometry Gamma Spectrometry Gamma Spectrometry M

M BW M

M SM, M SM, M A

A Soil 4

A Direct Radiation 84 Q

TLD Q

Note: See footnotes at end of table.

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

2003 Radiological Environmental Monitoring Report c-I 2003 Radiological Environmental Monitoring Report C-1

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

TLD Locations for the SSES Radiological Environmental Monitoring Program - 2003 J)

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) 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 J

3,

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

Apipendix C

.. I.

TABLE C 1 (Page 2 of 5)

TLD Location's'forthe SSES Radiological Environmental Monitoring Prograu - 2003

. ~-...

R no o

i 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 0.6 ESE -

Restaurant (U.S. Route 11) 8A3 0.9 SSE PPL Wetlands Sign (U. S. Route 11) 15A3 0.9 NW Hosler Residence 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 I

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 I W 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 2003 Radiological Environmental Monitoring Report C-4 2003 Radiological Environmnental Monitoring Report 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 c-s 2003 Radiological Environmental Monitoring Report C-5 2003 Radiological Environmental Monitoring Report

~I It 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 A-d mile B 2 miles C 3 miles D 4 miles E-4-5 miles F 10 miles G 20 miles H - >20 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)

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

13S6'-

- 0_ 4

.. W'. ' j

'Forrher Laydown Area, West'of Confers Lane

-B. \\

a.

e

{

.~

4. 4

• 4 v.,

• r 4

4 4S

• 4 i 4 4,. *,. 4. 4... -. 4.......................

r,-

sttE'>*

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 (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 1Distance Direction Description Code (miles) 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

.j)

L

-- -.
, I, -,
, 1,, "!
, z- ".-
,, ! -1

, z


,
,..
.-

I z
,,
,,. -Z I,,

'.
'. -,,, I, I - 4,,,
I
.
..,
.,

, i.

i-.,

I

t.

)I

-'j;I,

-,
, --, I

,.:

i
- 11,
- -

-.,
T __

1.2 NNE

-IGoudIln 2B1.

E I Rell I

12E1 4.7 1WSW lBerwickHospital 30.0 SSW.

jR.&C.RyinanFanm 10D32

'3.1 SSW Rayrhond Ryman Farm22n.

S_

z

)
,,

0.,

"i 1'.

,. r
,.,

, I ", -!

-I, VIk
;



.
-

"f-:

11,

.1-L

-RUITS/VEGETABLES il'

z I

1ID2 1

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

3 ji 2003 Radiological Environmental Monitoring Report C-S 2003 Radiological Environmental 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 l

SWL. J Chapin (Drake) Field

-T

,i~x RUND.WATER 12F3 l

5.2 WSW I Berwick Water Company C-90 3 R doo i a n io m na o ioi g R p r C-9 2003 Radiological Environmental Monitoring Report

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.

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

. -!J APPENDIX.

i-I '

I I ';a

. I' II

' i I

I..

i

. i I

I

.1 i2003 Radiological Environmental Monitoring Report i

II

. D-1

I I 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.

-2003 Radiological Environmental Monitoring Report D.2

-2003 Radiological Environmental Monitoring 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 I 1F2/SW Chapin (Drake) Farm 5.5 N/A Potatoes 1 ID2/SW Lupini Farm (Rt. 93) 3.5 N/A' Potatoes o

?

I i.:

D3 2003 Radiological Environmental Monitoring Report

~D-3 2003 Radiological Environmental Monitoring Report

l I 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 RESIDENCE NEAREST GARDEN NEAREST DAIRY ANIMAL SECTOR DIRECTION 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 1.3 mi 1.0 mi 0.9 mi 2.1 mi 1.4 mi ac 0.5 mi 0.5 mi 0.6 mi 1.0 mi 0.9mi 1.5 mi 1.1 mi 1.2 mi 0.8 mi 0.8 mi 0.6 mi 3.2mi 2.3 mi 2.7 mi 2.4 mi a,c,d,fl 1.8 mi 2.5 mi 0.6 mi 1.5 mi 1.1 mi 1.2 mi 1.9 mi 1.1 mi 1.2 mi

>5.0 mi 1.8 mi '

4.0 mi

>5.0 mi

>5.0 mi

>5.0 mi

>5.0 mi 4.5 mi g 2.7 mi

>5.0 mi

>5.0 mi

>5.0 mi 3.0 mi a,b,c,d.e,g

>5.0 mi 1.7 mi g'i 5.0 mi j

>5.0 mi

>5.0 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.

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

I I i

I.

, 1 APPENDIX E A'

.^

1 YDSrI.TION.OF. SSES REMI-

.^

<,t,'4'^

AN:-,lY.TICAL-. METHQDS.;-

i.

I..;.

El 2003 Radiological Environmental Monitoring Report -

E-1

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/cm2 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 E-S 2003 Radiological Environmental Monitoring Report E-5

' - 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.

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

Rb 2.22 V(M)

E 4.66

=

total counts for sample

=

count time for sample/background (minutes)

=

background count rate of counter (cpm)

=

dpm pCi

=

volume or mass of sample analyzed

=

efficiency of the counter (cpm/dpm)

=

sigma level Calculation of the Minimum Detectable Concentration (MDC) Value 4.66f4 MDC2=

I (

2.22 (V) (E) 2003 Radiological Environmental Monitoring Report E-1 2 2003 Radiological Environmental Monitoring Report E-12

AppendixL E RADIOCHEMICAL DETERMINATION OF 1-131

.1 I

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) 2003 Radiological Environmental Monitoring Report E-1 4 2003 Radiological Environmental Monitoring Report 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' t2 t

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 (e AT) where X is 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) 2003 Radiological Environmental Monitoring Report E-1 6 2003 Radiological Environmental Monitoring Report t

E-1 6

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-i

-466 'ii MDC (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:

E-9 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.

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

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

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

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

2003 Radiological Environmental Monitoring Report F-4 2003 Radiological Environmental Monitoring Report

~F*4

I.,

I'.

I-

. ;..1,

I,

I--

1:

I 7 I

r I

f.

APPENDIX G.

• 0 RE

-K;ji DP T-OF

.D4 I

-'I..

2003 Radiological Environmental Monitoring Report --

1 I I G-1

I I 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 (rnRfstdl. qtr.)

TLD 333 2.02E+01 (301 / 301)

(1.27E1+01 4.4713+01) 9S2 4.061E+01 (4 / 4) 0.2 nd S

(3.17E+01 4.471E+01)

Surface Water aOn Beta (pan)

Tritium Iodine-131 Gamma Spec Mn-54' Co-58 Fe-59 Co-60 Zn-65 48 4

6.06E+00 (36 / 36)

(2.42E+00 1.5913+01) 48 2000 1.5713+03 (36 / 36)

(-3.54E+01 1.66E+04) 90 1

3.65E-01 (64 / 64)

(.1.10-OI 1.91B+00) 48 3.58E+00 (36 / 36)

(-3.0013+01 5.0013+01) 48 15

-8.37E-.02 (36 / 36)

(.1.90E+00 I.50E+00) 48 I

-.2.053-01 (36 /36)

(-3.30E+00 3.60E+00) 48 30 1A9E-01 (36 /36)

(-6.00E+00 4.70E+00) 48 15 2.961E-01 (36 / 36)

(.1.10+00 1.9013+00) 48 30 4.81-01 (36 / 36)

(-1.073E+01 7.70E+00) 2S7 0.1 2S7 0.1 2S7 0.1 6S5

- 0.9-6S6 0.8 6S5 0.9 6S5 0.9 2S7 0.1 6S5 0.9 mi NNE mi NNE3 iniNNE mH '1SE13 ml-ESE Ini ESE1 mi ESil mi NNE IniESE 1.10E+01 (12 / 12)

(7.0813+00 1.5913+01) 4.42E+03 (12 /12)

(1.13E+02 1.66E+04) 7.77E-01 (26 / 26)

(.1.10-OI 1.911E+00) 4.75E+00 (12 / 12)

(-2.40E+013O 4.1013+01) 2.55E-02 (12 / 12)

(.1.00E+00 2.1013+00) 1.8313-01 (12 / 12)

(.2.40E+00 2.50E+00) 1.23E+00 (12 / 12)

(.2.10E+00 4.7013+00) 3.90E-01 (12 / 12)

(-8.00E-01 1.90E+00) 7.9213-01 (12 / 12j

(.5.50E+00.

6.00E+00) 1.90E+01 (32 / 32)

(1.41E+01 2.361E+01) 2.37E+00 (12 /12)

(6.08E-01 4.321E+00) 3.181+01 (12 /12)

(4.98E+01 1.37E+02) 2.S813-01 (26 /26)

(-1.00E302 7.201E-01) 2.301E-01 (12 /12)

(-1.70E+01 2.4013+01) 2.55E-02 (12 / 12)

(-.0013+00 2.1013+00)

-8.0913-01 (12 / 12)

(2.101+00 2.00Z-01) 4.85E-01 (12 / 12)

(-1.40E+00-5.8013+00) 2.6313-01 (12 /12)

(-8.0013-01 3.00E+00)

-2.911E-01 (12 /12)

(4.40E+00 7.00E+00) 0 0

0 0

0 0

0 0

0 0

'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 (pCi/)

(-5.80E+o0 Nb-95 48 15

-8.60E-02

(-3.80E+oo Cs-134 48 15 3.83E-01

(-1.70E+O0 Cs-137 48 18 5.97E-02

(-IAOE+00 Ba-140 48 60 8.97E-O1

(-3AOE+o0 La-140 48 15 1.03E+O0

(-3.90E+O0 (36 / 36) 3.70E+00)

(36 ( 36) 3.40E+00)

(36 / 36) 2.80E+0O)

(36 / 36) 3.70E+00)

(36 / 36) 5.70E+00)

(36 / 36) 6.50E+00) 6S5 (9.00E-01 6S6 (8.OOE-01 2S7 (1.00-01 LTAW on site

-2.92E-OI mi ESE

(-2.90Et00 2.96E-01 mi ESE

(-2.20E+00 4.73E-0O ml NNE

(-9.00E-O 6.08E-01 NE-ESE

(-1.20E+00 1.36E+00 NE-ESE (1.501E+00 1.57E+00 NEESE

(-1.80E+00 (12 1 12) 1.70EtO0)

(12 / 12) 4A.E+00)

(12 / 12)

IAOE+00)

(12 / 12) 3.70E+00)

(12 / 12) 5.70E+O0)

(12 / 12) 6.50E+00)

-4.02E-01

.(3.00EtOO 2.9611-01

-(2.20E+00 3.73E-01

-(2.70E-01

-4.50-OI

-(1.60E+00

-2.5411-01

-(5.00E+00

-2.87E-01

.(5.80E+00 (12 / 12) 150E+O0)

(12 / 12) 4AOE+00)

(12 1 12) 150E+00)

(12 / 12) 4.7011-01)

(12 1 12) 2.70E+00)

(12 / 12) 3.10E+00) 0 0

0 0

0 0

LTAW on site LTAW on site

(.

I1 C-0-4

(

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 3 of 13 C

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 (pCin) 1.69E-01 (12 / 12)

(.6.54E-01 1.37E+00)

Gross Beta 12 4

2.26E+00 (8.98E-01 Iodine-131 26 1

1.781:-01

(.1.60E-01 Tuitium 12 2000 6.43E+01

(.7.67E+00 (12 / 12) 4.26E+00)

(26 1 26)

• 5.80E-01)

(12 / 12) 1.93E+02) 12112 26 12112 26 12H2 26 12H2 26 1.69E-01 (12 / 12) ml WSW

(-6.54E-01 1.37E+00)

Only indicator stations sampled for this medium.

0 2.26E+00 ml WSW (8.98E-01 1.781-01 mi WSW

(-1.60E-01 6.43E+01 mi WSW

(-7.67E+00 (12 / 12) 4.26E+00)

(26 / 26)

• 5.80E-01)

(12 / 12) 1.93E+02) 0 0

0 Gamma Spec K40 Mn-54 Co-58 Fe-.59 Co-60

-Z.65 Zr-95 12 4.04E+00. (12 / 12)

(-2.00E+01 4.10E+01) 12 15

-5.36E-02 (12 / 12)

(-1.40E+00 9.00E-01) 12 15

-4.26E-01 (12 / 12)

(-1.20E+00 6.00E-01) 12 30

-3.69E-01 (12 / 12)

(-3.60E+00 3.00E+00) 12 15 1.55E-01 (12 / 12)

(-7.00E-01 8.00E-01) 12 30

-1.21E+00 (12 / 12)

(.9.80E+00 6.10E+00) 12 30

-5.11E-01. (12 / 12)

(-2.60E+00 4.00E-01) 12H2 26-12112 26 12112 26 12112 26 12112 26 12H2 26 12112 26 4.04E+00 mi WSW

(-2.00E+01

-5.36E-02 mi WSW

(-1.40E+00

-4.26E-01 mi WSW

(-1.20E+00

-3.69E-01 mi WSW

(-3.60E+00 1.55E-01 mi WSW

(-7.002-01

-1.21E+00 mi WSW

(-9.80E+00

-5.112-01 mi WSW

(-2.60E+00 (12 / 12).

-; -, 4.10E+01)

(12/12).

9.00E-01)

(12/12) 6.0013-01)

(12/12) 3.00E+00)

(12 / 12) 8.00E-01)

(12 / 12) 6.102+00)

(12 / 12) 4.00E-01) 0 0

0 0

0 0

0 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 (PCU1) 12 15 1.8513-01 (12/ 12)

(-1.1013+00 1.1013+00) 12H2 26 12112 26 Cs-134 12 15 9.2313-02 (12 / 12)

(-5.7013-01 1.20E+00)

Cs-137 12 18

-1A4E-01 (12 / 12)

(-2.40E+00 1.60E+00)

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

(-2.80E+00 7.20Et00)

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

(-3.201E+00 8.30E1+00) 12112 26 12H2 26 12112 26 1.8513-01 (12 / 12) mi WSW

(-I.1013+00 1.103E+00) 9.2313-02 (12 /12) ni WSW

(-5.70E-01 1.20E+00)

-1.411E-01 (12 /12) mi WSW

(-2.40E+00 1.6013+00) 3.051E-01 (12 / 12) mi WSW

(-2.80E+00 7.2013+00) 3.72E-01 (12 / 12) mi WSW

(-3.20E+00 8.30E+00)

Only indicator stations sampled for dts mcdiu.

0 0

0 0

0

(

(

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 oali la 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 (pCitkg wet)

K-jl40 Opec K-40 Mn-54 Co-58 Fe-59 CO-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 I..

Ba-140 La-140 13 3.58E+03 (7 / 7)

(1.30E+03 4.39E+03) 13 130 1.95s+00 (7/ 7)

(-9.19E+00 9.692+00) 13 130

-1.67E+00 (7 7)

(.09ss+00o

.6.351+0^)

13 60

-9.SIB3+u0 (7 /

(-4A0E+i"'-

1.57-E+001) 13 130

-1.593+00 (7 7).

(-7.972+00 4.40E+00)'

13 260

-3.992+01 (7

7)

(8.642E+01 2.852+00) 13 1.682-01 (7I7)

(.1.501+01 1.362+01) 13 0.00E+00 (7 7)

(0.00^E+00 0.002+00) 13 130

-1.862+01 (7 7)

(4.351+01 3.39E+00) 13 150 4.532+00 (7 /7)

(07.782-01

- -1.22e+01) 13 4.852+01 (7 /7)

,(-8.44E+01 1.85E+02)

LTAW on site LTAW on site LTAW on site LTAW on site 2H 30 211 30 211 30 2H 30 LTAW on site IND 0.9-1.4 LTAW on site IND.

3.672+03 (I/ 1) 3.162+03 (6 / 6)

NE-ESE (3.672+03 3.672+03)

(1.30E+03 3.922+03) 5.742+00 (I / 1) 3.152+00.

(6 / 6)

NE-ESE (5.742+00 5.74E+00)

(-6.18E+00 1.34E+01)

-9.80E-01 (I / 1)

-2.532+00 (6 6)

NE-ESE

(-9.802-01

-.9.80E-01)

(-6.14E+00- -

1.211+00) 1.0613+01 (I

1)

-1.69e+00 (616)_;

NE-ESE (1.062+01

1.062+01)

(-2.84E+01,. -

1.88E+01) 1.312-01 (6 6),

1.311-01 (6 /6) ml NNE

(-8.69E+00 9.992+00)

(.8.69E+00

- t 9.99E+00)

-3.262+00 (6 /6)

-3.261+00 (6 /6)-,

,mn NNE

(.2.952+01 9.28E+00)

(-2.95E+01 * -

9.28E+00) 3.84E+00 (6 / 6) 3.841+00 (6 / 6) mn NNe

(-3.25E+00 1.382+01)

(-3.25E+00 1.38E+01) 0.002+00 (6 / 6) 0.00E+00 (6 /6) mi NNe (0.00E+00 0.002+00)

(0.00E+00 0.00E+00) 3.391+00 (I / 1)

NE-ESE (3.391+00 3.392+00) 5.192+00 (6 / 6) mi ESE

(-7.78E-01 1.22E+01) 1.5023+02 '(

/ 1)

NE-ESE (1.50E+02 1.502+02)

-6.252+00 (6 / 6) mi ESE

(-5.25E+01 3.312+01)

-1.47E+01 (6 / 6).

(-6.6E2+01 1.19E+00)

-1.782+00 (6 / 6)

(-8.29E+00 3.142+00)

-3.49E+01 (6 / 6) -

(-2.26E+02 4.392+01)

-7.25E+00 (6 / 6)

(-1.94E+01 7.42E-01) 13

.6.57e+00 (7 / 7)

(.5.2.5+01.

3.312+01).

0.9-1.4 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 MEDIUM ORPATHWAY TOTALNUMBER OP ALL INDICATOR LOCATIONS LOCATION WVIT1HHIGHEST MEAN SAMPLED OP ANALYSES DECRITION MEAN (3)

NAME MEAN (3)

(UNIT OFMEASUREMEIM PERFORMED(I)

(LLD) (2)

RANGE DISTANCEANDDIRECTION RANGE NUMBEROP CONTROL LOCATION NONRO LINB MEAN (3)

REPORTED RANGE MEASUREMENTS(4) btdUtntn (pCi/kg dry)

GJanuna Spcc IBe-7 K-40 Mn-.54 Co-58 Fe-59 Co-60 Znr65 7.r-95 Nb-95 Cs-134 Cs. 137 3.30E+02 (6 16)

(-2.53E+01 7.26E+02) 1.37E+04 (6 / 6)

(1.04E+04 1.58E+04) 9.58E+00 (6 / 6)

(1.78E+00 2.55E+01)

.1.07E+01 (6 16)

(-2.57E+01 2.41E+00)

-6.29E+00 (6 / 6)

(-2.98E+01 4.92E+01) 4.57E+00 (6 / 6)

(-9.06E+00 1.12E+01) 7.53E+00 (6 / 6)

(-2.05E+01 4.05E+01) 1.95E+01 (6 / 6)

(1.20E+00 4.37E+01) 0.00E+00 (6 / 6)

(0.OOE+00 0.00E+00) 150

-2.28E+00 (6 / 6)

(-8.52E+00 7.96E+00) 180 5.20E+01 (6 /6)

(6.91E+00 1.00E+02)

-2.30E+01 (6 /6)

(-9.92E+01 7.40E+01) 12P 6.9 LTAW on site LTAW on sitc 12F 6.9 2B 1.6 7B 1.2 LTAW on siLte 7B 1.2 2B 1.6 LTAW on silw 71B 1.2 6.99E+02 (2 / 2) mid WSW NE-ESE NE-ESE mi WSW nii NNE nl SE ml SE mn NNE NE-ESE mi SE (6.71E+02 1.52E+04 (1.47E+04 1.36E+01 (1.78E+00

-7.79E-01 (1.78E+00 2.58E+01 (2.31E+00 7.79E+00 (4.42E+00 2.57E+01 (1.08E+01 3.60E+01 (2.83E+01 0.00E+00 (0.00E+oo 4.96E+00 (1.97E+00 8.92E+01 (7.81E+01 7.26E+02)

(2 2) 1.58E+04)

(2/2) 2.55E+01)

(2 /2) 2.41E+00)

(2 2) 4.92E+01)

(2/2) 1.12E+01)

(212) 4.05E+01)

(2 2) 4.37E+01)

(2 /2) 0.OOE+00)

(2/2) 7.96E+00)

(212) 1.00E+02)

(2 /2) 2.91E+02 (2/ 2)

(2.58E+02 3.25E+02) 1.23E+04 (2 /2)

(7.23E+03 1.73E+04) 3.11E+00 (2 /2)

(-3.54E+00 9.75E+00)

-1.94E+01 (2 /2)

(-2.82E+01

-1.05E+01) 2.58E+01 (2 /2)

(2.31E+00 4.92E+01)

-2.50E+00 (2 /2)

(-1.20E+01 7.04E+00)

-3.32E+01 (2 / 2)

(-6.23E+01 4.07E+00) 1.38E+01 (2 /2)

(5.34E+00 2.22E+01) 0.00E+00 (2 /2)

(0.OOE+00 Q.OOE+00)

-6.59E+00 (2 / 2)

(-1.07E+01

.2.53E+00) 7.56E+01 (2 /2)

(4.14E+01 1.10E+02)

-4.79E+01 (2 / 2)

Ba-140 8

12P

-4.68E+00 6.9 nii WSW

(-7.11E+00 0

-2.25E+00) (-l.lOE+02 1.42E+01)

-4L 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 MEDIUM ORPATHIWAY TOTALNUMBER OF SAMPLED OF ANALYSES DETECTON (UNrr OP MEASUREMENT PERFORMED (1)

(Ufl) (2)

Sediment (cord)

La-140 8

(pCi/kg dry)

Ra-226 8

Th-228 8

Ground Water

'almuma Spec I/1)

K-40 36

,;154

'36 Co-58 36 15 Fe-59 36 30 Co-6O 36 is Zn-65 36 30 Zr-95 36 30 Nb-95 36 i5 Cs-134 36 15 ALLINDICATOR LOCAIIONS MEAN(3)

RANGE

-9.832+00 (6 I 6)

(-9.79E+01 4.89E+01) 2.27E+03 (6 /6)

(1.96E+03 2.86E+03) 3.21E+03 (6 6)

(2.462+03 3.56E+03)

-1.552+00 (24 124)

(-5.102+01?

2.70E+01)

-1.18E-01 (24/ 24)

(-2.90E+00 2.102+00)'

-7.57E-01 (24 1 24)

(-2.70E+00 1.70E+00) 5.832-01 (24'/ 24)'

(-5.30E+00 6.102+00)

-1;282-01 (24 / 24)

(-2.402+00 2.002+00)

-1.32E+00 (24 / 24)

(-9.40E+00 8.502+00)

-6.542-01 (24 / 24)

(-5.70E+00 3.302+00)

-2.462-02 (24 1 24)

(-2.902+00 3.0012+00) 1.742-01 (24 1 24)

NUMBER OF LOCATION wrm TlUGHEST MEAN CONTROL LOCATION NONRfUTINE NAME MEAN(3)

MEAN (3)

REPORTED DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS(4) 7B 2.81E+01 (2 / 2) 1.91E+01 (2 / 2) 1.2 mi SE (7.352+00 4.89E+01)

(1.78E+01 2.05E+01) 7B 2.61E+03 (2 / 2) 1.60E+03 (2 / 2) 1.2 mi SE (2.362+03 2.862+03)

(7.502+02, 2.45E+03) 7B 3.51E+03 (2 /2) 3.01E+03 (2

2) 1.2 nii SE (3.47E+03 3.56E+03)

(1.28E+03 4.74E+03) 2S2 2.492+00 (12 / 12) 2.332+00 (12 / 12) 0.9 mrdn' NNE-' (-1.90E+01 ;-

2.702+01) '-(-3.30E+i01

5.30E+01)>

12F3 1.922-01 (12 / 12) 1.92E-01 (12/ 12) 5.2 ffd WSW'

(-1.402+00. -

'2.00+00)

(-1.402+00 2.00+00) 12F3

-5.00E-02 (12 / 12)

-5.002-02 (12 / 12) 5.2, mil WSW; (-1.70E+00, 1.20E+00)

(-1.70E+00 1.202+00) 2S2 6.422-01 (12 / 12) 3.752-01 (12 / 12) 0.9, mi NNE

(-5.30E+00 6.10E+00)

(-4.20E+00 8.50E+00) 4S4 3.332-02 (12 / 12)

-1.081E-01 (12 /12) 0.5 ml ENE

(-1.502+00 2.002+00)

(-2.80E+00 1.902+00) 4S4

-1.202+00 (12 / 12) 4.432+00 (12 / 12) 0.5 mi ENE

(-9.40E+00 8.502+00)

(-2.80E+00 2.80E+00) 12F3 1.152+00 (12 / 12) 1.152+00 (12 / 12) 5.2 ml WSW

(-2.70E+00 5.40E+00)

(-2.70E+00 5.40E+00) 4S4 3.83E-01 (12 / 12)

-2.422-01 (12 / 12) 0.5 ml ENR

(-2.70E+00 3.002+00)

(-2.40E+00 2.10E+00) 4S4.

4.422-01 (12 / 12)

-3.672-01 (12 / 12) 0.5, mi ENE

(-9.002-01 2.802+00)

(-1.70E+00 1.20E+00)

(-2.40E+00 2.80E+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 NUMBER OF MEDIUM OR PAThWAY TOTAL NUMBER OF ALL INDICATOR LOCATIONS LOCATION WITII IIGiHEST MEAN CONTROL LOCATION NONROUTINE SAMPLED OF ANALYSES DETECTION MEAN (3)

NAME MEAN (3)

MEAN (3)

REPORTED (UNITOFMEASUREMENT)

PERFORMED(I)

(LLD) (2)

RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS(4)

Ground Water (coat)

(pCi/l)

Cs-137 Ba-140 La-140 H-3 36 18

-1.28E-01 (24 / 24)

(-1.70E+00 1AOE+00) 36 60

-2.67E-01 (24 / 24)

(-5.20E+00 3.OOE+00) 36 15

-2.96E-01 (24 / 24)

(-6.00E+00 3AOE+00) 36 2000 5.44E+01 (24 / 24)

(-6.74E+01 1.93E+02) 2S2 0.9 4S4 0.5 4S4 0.5 4S4 0.5

-1.14E-01 (12 / 12)

-3.75E1-01 (12 / 12) mi NNE

(-1.70E+00 1.40E+00)

(-2.20E+00 1.20E+00) 6.08E-01 (12 / 12) 1.08E-01 (12 / 12) mi ENE

(-1.80E+00 2.60E+00)

(-4.80E+00 5.10E+00) 7.00E-01 (12/ 12) 1.25E-01 (12 / 12) mi ENE

(-2.10E+00 3.00E+00)

(-5.50E+00 5.80E+00) 8.43E+01 (12 / 12) 1.74E+01 (12 / 12) mi ENE

(-2.46E+00 1.93E+02)

(-8.84E+01 8.86E+01) 0 0

0 0

Air Partlculates (E-03 pCi/m3)

Air Iodine (E-03 pCi/m3)

Air Particulates Quarterly Composite (E-03 pCi/m3)

Gross Bcta 312 10 1.46E+01 (208 / 208)

(3.59E+00 3.17E+01) 3S2 0.5 1.51E+01 (52 / 53) mi NE (5.30E+01 4.91E+00) 1.34E+01 (104 / 104)

(3.16E+00 3.10E+01)

-6.44E-05 (104 / 104)

(-3.74E-03 6.30E-03) 0 1-131 312 70 6.01E-04 (208 / 208)

(-5.27E-03 5.97E-03) 3S2 0.5 8.29E-04 (52 / 52) mi NE (5.20E+01

-2.79E-03) 0 Gamma Spec Be-7 24 K-40 Mn-54 24 9.06E+01 (16 / 16)

(6.70E+01 1.1IE+02) 1.29E+00 (16 / 16)

(-4.94E+00 4.04E+00) 3.63E-02 (16 / 16)

(-6.98E-02 2.23E-01) 12SI 0.4 3S2 0.5 6GI 13.5 9.10E+0I (4 / 4) mi WSW (7.65E+01 1.06E+02) 2.21E1+00 (4 / 4) mi NE (2.27E-01 4.04E+00) 1.10E-01 (4 / 4) mi ESE

(-5.75E-02 3.29E-01) 8.21E+01 (8 / 8)

(6.63E+01 9.34E+01) 9.20E-01 (8 / 8)

(-5.79E+00 4.66E+00) 9.23E-02 (8 / 8)

(-5.75E-02 3.29E-01) 0 0

0 24

(

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 (UNIT OF MEASUREMET PERFORMED (1 )

LD) (2)

RANGE DISTANCE AND DIRECTION RANGE RANGE MEAS'REMENTS(4)

Air Partic ulates (colt)

Quartery Composite (2-03 pCihn3)

Co-58 24

.1.76E-02 (16 / 16)

(-3.02E-01 4.75E-01)

Fe-59 24

.9.55-02 (16 / 16)

(-1.15+00 1.082+00)

Co-60 24 2.38E-02 (161 16)

(-1.481-01 1.76E-01)

Zn:65 24

-2.882-01 (16 16)

(.1.34E+00' 6.25E-01)

Zr-95' 24' 1.78E-02 (16 116)

(.5.132-01'-'

4.7iE-01j' N-95 24 0.00E+00 (16 /16)

(0.00+00 '

0.00E+00)

Cs.134 24 50 0.00E+00 (16 /16)

(-8.96E-01 8.91E-02)

Cs-137 24 60 4.152-02 (16 /16)

(-9.462-02 1.61E-01)

Ba-140 24

-4.59E+00 (16 /16)

(-2.38E+01 1.74E+01)

La-140 24

.2.94E+00 (16 / 16)

_(-2.42E+01

- - 4.81E+00) 3S2 1.35E-01 0.5 ml NE '

(-6.89E-02 12S1 5.03E-01 0.4 mr WSW (I.OSE-01 801 8.38E-02 12 mi SSE

(-3.44E-Q3 12SI

-7.97E-03 0.4 '

' WSW

(-5.66E01 13S6 8.622-02 0.4 mi' W

(.3.07E-01',

601 0.00,Q +00 13.5 mni ESE (0.00+00 12S I

-3.46E-02 0.4 mi WSW

(-9.70E-02 13S6 1.192-01 0.4 mi W

(6.292-02 12E1 5.54E+00 4.7 mi. WSW (4.032+00 12S1 1.972+00 0.4 ml WSW

(-4.43r-01 (4 1 4) 4.75E-01)

(4 1 4)

)

(4 1 4) 2.13E-01)

(4 1 4) 6.25E-01)

(4 4) 4.77E-01)

(4 4)

-0.0023+00)

(4 1 4) 4.42E-02)

(4 14) 1.61E201)

(4 4)

• 1.74E+01)

(4 14)

• 4.81E+00)

-9.012-02 (8 / 8)

(-3.55E-01 4.8t 4.052-01 (8 / 8)

(-8.34E-01 1.2, 5.702-02, (8 / 8)

(-3.17E-02, 2.1:

-2.46E-01 (8 / 8)

(..012+00, -

-2.9

-7.31E-02 (8 8)

(-2.42E-01 9.6 0.00E+00, (8 18)

(0.00+00 0.0

-3.002-01 (8 / 8)

(-8.09E201 2.4 2.072-02 (8 / 8)

(-6.52E-02 1.C 2.122-01 (t I 8)

(.1.19E+01

- - 8.1 4.772-01 (8 /8)

SE-02) 72+00) 32-01) 323-0 1) 9E-02) 00E+00) 9E-02)

Q3E-01) 7E+00) 0 0

0 0

0 0

0 0

0 0

I

(-5.49E+00 :-

1.25E+01)

.. I 1 :

I...

I j

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

KCiA)

Gamnum Spec 5.32E-02 (57 / 57)

(-1.70E-01 4.40E-01) 1001 9.08E-02 (19 / 19) 9.082-02 (19 / 19) 14 nii SSW

(-8.00E-02 4.50E-01)

(-8.00E-02 4.50E-01) 0 K-40 76 1.38E+03 (57 / 57) 1001 (9.40E+02 1.55E+03) 14 M&,54 76

-1.88E-01 (57 / 57) 10D2

(-4.30E+00 2.50E+00) 3.1 Co-58 76

-4.00E-01 (57 /57) 10SI

(-4.10E+00 3.30E+00) 14 Fe-59 76 4.60E-01 (57 / 57) 10D2

(-1.20E+01 1.22E+01) 3.1 Co-60 76 2.47E-01 (57 /57) 10DI

(-4.70E+00 5.40E+00) 3 Zn-65 76

-2.77E+00 (57 / 57) 10D2

(-1.60E+01 7.00E+00) 3.1 Zr.95 76

-2.63E-02 (57 /57) 12B2

(-7.20E+00 3.60E+00) 1.7 Nb-95 76 2.56E-01 (57 / 57) 1I00

(-2.80E+00 4.70E+00) 14 Cs-134 76 15

.8.77E-03 (57 / 57) 10D2

(-4.00E+00 4.10E+00) 3.1 Cs-137 76 18

-8.77E-03 (57 /57) 1001

(-3.20E+00 3.50E+00) 14 Ba-140 76 60

-2.49E-01 (57 / 57) 1001

(-4.80E+00 5.00E+00) 14 La-140 76 15

-2.88E-01. (57 / 57) 1001

(-5.50E+00

.5.80E+00) 14 1.41E+03 mi SSW (8.19E+02

-5.26E-02 mn SSW

(-2.60E+00

-7.89E-02 mi SSW

(-3.70E+00 8.32E-01 mn SSW

(-4.00E+00 6.11E-01 ni SSW

(-3.002+00

-9.212-01 mi SSW

(-1.602+01 3.58E-01 mi WSW

(-4.30E+00 4.37E-01 mi SSW

(-2.00E+00 4.11E-01 mi SSW

(-1.70E+00 5.58E-01 I mi SSW

(-1.202+00 1.89E-01 mi SSW

(-2.701+00 2.16E-01 I m SSW

(-3.10E+00 (19 / 19) 1.53E+03)

(19 / 19) 2.50E+00)

(19 /19) 2.30E+00)

(19 / 19) 8.00E+00)

(19 I 19) 3.30E+00)

(19 / 19) 7.00E+00)

(19 1 19) 3.60E+00)

(19 1 19) 2.70E+00)

(19 / 19) 2.80E+00)

(19 /19) 2.60E+00)

(19 / 19) 3.90E+00)

(19 / 19) 4.40E+00) 1.41E+03 (8.19E+02 4.42E-01

(-3.10E+00

-7.892-02

(-3.70E+00 1.42E-01 (4.60E+00 2.21E-01

(-2.90B+00

-2.92E+00

(-1.34E+01

-2.58E-01 (4.30E+00 4.37E-01

(-2.00E+00

-2.212-01

(-2.80E+00 5.582-01

(-1.20E+00 1.89E-01

(-2.70E+00 2.16E-01

(-3.10E+00 (19 / 19) 1.53E+03)

(19 /19) 1.60E+OO)

(19 / 19) 2.30E+00)

(19 / 19) 7.30E+00)

(19 / 19) 2.90E+00)

(19 / 19) 4.20E+00)

(19 / 19) 7.50E+00)

(19 / 19) 2.70E+00)

(19 / 19) 2.60E+00)

(19 / 19) 2.60E+00)

(19 / 19) 3.90E+00)

(19 / 19) 4.40E+00)

(

I C-012

(

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 Janiiay 30, 2004!

Page 11 of 13 ANALYSIS AND LOWER LIMIT NUMBER OF MEDIUM ORPATIIWAY TOTALNUMER 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 (pCi/kg dry)

Gamma Spec K-40 Mn-54 CO-58 Fe-59 Co:60 Zn--65 Zr-95 I.

I ~..

Nb-95 Cs-134

,Cs-137 Ba-40 Ba-140 8

8 8

8 8

8 8

8 8

8 8

8 1.44E+04 (6 / 6)

(1.0313+04 1.82E1+04) 0.4

-1.5013+00 (6 / 6) 13S6

(-9.0013+00 4.0013+00) 0.4

-6.3313+00 (6 /6) 3S2

(-.18013+01 9.OOE+00) 0.5

-6.17E+00 (6 /6) 13S6

(-2.80E+01 3.6013+01) 0.4

.4.0013+00 (6 / 6) 3S2 1.2013+01) 0.5

-1.8713+01 (6 / 6) 12SI

(-1.10E+02 6.00E+01) 0.4

-1.15E+03 (6 / 6) 8C1

(-6.70E+03 3.0E+01) 12

-4.6713+00 (6 / 6) 8GI

(-4.30E+01 1.6013+01) 12 3.83E+00 (6 / 6) 801

(-7.00E+00 2.4013+01) 12 4.2813+01 (6 / 6) 12SI

(-2.1013+01

-, 9.60E+01) 0.4 6.6713-01 (6 / 6) 3S2

(.5.00E+01 8.00E+01) 0.5

-1.1313+01 (6 /6) 3S2

-(4.90E+01 1.4013+01) 0.5 13S6 1.6213+04 (2 /2) 1.0613+04 mi W

(1.43E+04 1.82E+04)

(1.02E+04

-5.0013-01 (2 / 2)

.1.2013+01 mn W

(.5.0013+00 4.0013+00)

(.1.90E+01 1.0013+00 (2 / 2)

O.O0E+00 nil NE

(-7.0013+00 9.0013+00)

(.5.0013+00 4.OOE+00 (2/2)-,..

4.0513+01 al W

(-2.8013+01 3.6013+01)

(.7.20E+01 7.0013+00 (2/ 2)

-1.0013+01 mi NE (2.0013+00 1.2013+01)

(-1.8013+01 9.O0E+00 (2 / 2) 5.0013+00 mld WSW

(-3.2013+01 5.00E+01)

(.3.0013+01 4.8013+01 (2 / 2),

4.8013+01 nii SSE (4.70E+01 4.9013+01)

(4.7013+01 1.7013+01 (2 / 2) 1.7013+01 mi SSE

(-5.OOE+00 3.9013+01)

(-5.0013+00 3.30E+01 (2 12) 3.30E+01 nii SSE (1.4013+01 5.20E+01)

(1.40E+01 8.6013+01 (2 / 2) 7.4513+01 mi. WSW (7.6013+01, 9.60E+01)

(5.2013+01 (2/ 2) 1.1013+04)

(2/ 2)

-5.0013+00)

(2/2) 5.00E+00)

(2 2)

-9.0013+00)

(2 / 2)

-2.0013+00)

(2 2) 4.00E+01)

(2 2) 4.9013+01)

(2/ 2) 3.90E+01)

(2/ 2) 5.20E+01)

(2/ 2) 9.7013+01) 0 0

0 0

0 0

0 0

0 0

0 0

2.5013+01, (2 / 2) mi NE

'(1.0013+01 4.0013+01)

-1.8013+01 (2 / 2)

(.2.50E+01

-1.1013+01) 1.0513+01 (2 / 2)

-2.0513+01 (2 / 2) nu NE (7.00E+0 1.4013+01)

-(2.80E+01

-1.30E+01)

I

, 1,

1 I I

-
o.
,,, I "

I I.,

I

. I I

I I I, 0 I I-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 NUMBER OF MEDIUM ORPATIlWAY TOTALNUMBER OF ALLINDICATORLOCATIlONS LOCATION WIT111GI]EST MEAN CONTROLLOCATION NONROUTINE SAMPIED OF ANALYSES DETECTION MEAN(3)

NAME MEAN(3)

MEAN(3)

REPORTED (UNITOPMEASUREMEbBT PERFORMED(1)

(LLD) (2)

RANGE DISTANCE AND DIRECTION RANGE RANGE MBASUREMENTS(4)

Soil (colt)

(pCi/kg dry)

Ra-226 0

0 Food/Garden Crops (pCi/kg wet) nh-228 Gammn Spcc Bc-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Z&-65 Zr-95 Nb-95 7.891E+02

(-2.00E+00 8.431E+00 (2.95E+00 4.56E+03 (4.47E+03

-4.75E-01

(-2.31E+00

-1.281E+00

(-1.48E+00

-3.75E-01

(-2.72E+00 3.481E+00 (1.42E+00

-2.01E+01

(-2.33E+01 7.40E-01 (4.25E3+00 0.00E+00 (0.OOE+00 (6 6) 1.04E+03)

(2 / 2) 1.39E+01)

(2 1 2) 4.66E+03)

(2 2) 1.36E+00)

(2 2)

-1.07E+00)

(2 / 2) 1.97E+00)

(2 1 2) 5.53E+00)

(2/2)

.1.69E+01)

(2 1 2) 5.73E+00)

(212) 0.001E+00) 3S2 11F IID:

IID:

1ID:

llF;

lip, 11F lF IID 1.02E+03 0.5 mi NE (1.00E+03 2

1.391E+01 5.5 mi SW (1.39B+01 2

4.66E+03 3.5 mi SW (4.66E+03 2

1.36E+00 3.5 mi SW (1.36E+00 2

-1.07E+00 3.5 mi SW

(-1.07E+00 1.97E+00 5.5 mi SW (1.97E+00 2

5.53E+00 5.5 mi SW (5.53E+00 2

-1.691E+01 5.5 mi SW

(-1.69E+01 2

5.73E+00 5.5 mi SW (5.7313+00

)2 0.00E+00 3.5 mi SW (0.OOE+00 (2 2) 8.15E+02 (2 /2) 1.04B+03)

(7.30E+02 9.00E+02)

(1 1) 1.39E+01)

(1/ 1) 4.66E+03)

(1 1) 1.3613+00)

(1/1)

-1.07E+00)

(1 /1) 1.9713+00)

(1/ 1) 5.531E+00)

(1/ 1)

-1.69E+01)

(I I 1) 5.73E+00)

(1/1) 0.0013+00) 1-131 2

-6.3213+00 (2 / 2) liF2

(-6.631E+00

-6.01E+00) 2

-6.01E+00 (I / 1) 5.5

'mi SW

(-6.01E+00

-6.0113+00) 0 I

c 0-14

(.

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 Page 13 of 13 January 30,2004 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)

(-2.0013+01

-1.82E+01)

-3.5413+00 (2 / 2)

(-6.0013+00

-1.07E+00) 11F2 5.5 1ID2 3.5 Cs-137 2

-1.8213+01 (I / I) mi SW

(-1.82E+01

-1.8213+01)

-1.07E+00

( I /1) ml SW

(-1.07E+00

-1.07E+00) 4.4113+01 (I / 1) ml SW (4.41E+01 4.41E+01) 5.5813-01 (I / 1) mni SW (5.58E-01 5.58E-01) 0 0

Ba-140 La-140 2

1.8913+01 (2 / V 11F2

(-6.32E+00 4.4113+01) 5.5

-1.8413+00 (2 / 2) 1 ID2

(-4.24E+00 5.5813-01) 3.5 0

2 0

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 NiEANSSULT I

IRIc

'S TWIT-H S

t ;;

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

^;;:-tt~,st>.

~'tt

,','~

f : ;.i;!;?

1

.VR

'ii;~~~

~

T

~

b E~;E R

I Nf4 FRI ji;~f 2003 Radiological Environmental Monitoring Report H-I 2003 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.

2003 Radiological Environmental Monitoring Report H-2

-2003 Radiological Environmental Monitoring Report H-2

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

I

--Location --7 Indicato l -

'.Control.

Period Pre-Op Operational l

Pre-Op l

Operational 1978-81 1982-02 2003 1978-81 '

1982-02

'2003 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 Indicator

=

Control

Period, Pre-Op Operational J.

Pre-Op Operational 1979-81 1982-02 2003 1979-81 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, DRINKING WATER GROSS ALPHA ACTIVITIES (pCi/I)

Period Preoperational

[

Operational 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

J)

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 2003 Radiological Enyironmental Monitoring Report H-4 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' 8.6-10.4 7.4-13.6 7.5-110

.6.2-13.0 l'Mean'

`9.3 10.8

12.3 J 7.7

.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 TABLEHJ 1.

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 -:1982-02..

-2003

.1978-81 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 pCiin3)

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 1990 values is questionable in some instances. Laboratory analysis error is suspected. See the 1990 Annual Report.

_-Ji 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 Ji 2003 Radiological Environmental Monitoring Report H-6 2003 Radiological Environmental Monitoring Report

-.H-6

Appendix H

.TABLE H 16 SOIL RADIUM-226-.4-CTIVITIES '(Ci/g Iry)

Location I '_ '

Indicator I

Control Period

. Pre-Op:

' Operational.I

..Pre-Op :

Operational I

1979&81. 1; 1984-02* 1 2003*'

1979&81.-..1984-02 1 2003 Range

'0.8-1.3 l0.8-2.5

-0.8-1.2

1.0-2.2 Mean 1.1 1.6 4

'0 J 10 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 1 Operational Pre-Op 4Operati nal 1979&81 198402 l 2003 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 1 Indicator l

_Control_7 Period Pre-Op Operational 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

.1 a 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 2003 Radiological Environmental Monitoring Report H-S

-2003 Radiological Environmental Monitoring Report

,.H-8

l.

I

l.

' I' 1,

I.;

w i

I I

l X..

APPENDIX I

• VIDz ANf

'AVP14t rr'n

' 'Q{;

s

-- 'ttii~u

., LY3.V.

3 JU+/-'..L J

t SS

~

I~

i, I

I I

• I 1.

I

-1 I

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

(

C.

-TABLE I-1 ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY RESULTS SUSQUEHANNA STEAM ELECTRIC STATION - 2003.

Results (I) are in mR/std. qtr (2) +/- 2S (3)

(

a 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 2S2 2S3 3S2 3S3 3S4 4S3 4S6,,,,;

5S4§4 5S7 6S4';

6S9 7S6 7S7 8S2 9S2 10S 10S2 10S3 I1S3 IiS7 23.6 I 1.4 17.5 +/- 1.8 20.4 +/- 0.8 17.6 +/- 1.4 17.0 +/- 1.6 17.2 +/- 1.4 22.0 : 1.2 17.8 +/- 1.6 16.1+-1.0 17.8 +/- 1.8-23.8-+/- 1.

22.6 b 0.6 22.9 +/--1.8 17.3 + 1.0' 22.9 +/- 1.4 31.7 4-1.8 17.1 b 1.8 26.6 +/- 1.2 16.3 +'0.6 24.8 +/- 1.6 18.0 +/- 1.2 24.3 +/-: 1.9 15.8 + 1.3 20.5 + 1.5 16.0 +/- 1.1 15.0 + 1.3 (4) 21.0 + 1.1 16.9 + 1.3 14.9 k-1.3 16.6 > 1.1-24i.3+/- 2.1 23.2 :+/- 1.1 23.3 1.3 15.9 +/-!1.5 22.5 +/- 1.7 41.9 +/- 6.4 15.9 6 1.7 29.2 +/- 1.1 15.1 +/- 1.3 24.6 +/- 1.1 16.9'+/- 1.1 23.6 +/- 1.2 20.5 +/- 0.8 23.6 +/- 0.4 19.5 +/- 1.2 19.1 +/- 2.6 19.4 + 1.8 24.2 + 1.0 20.8 +/- 1.2

---18.4 +/- 1.6-19.6 +/- 1.4 27.9 + 1.2 27.6 +/- 1.8 26.7 +/- 1.2 19.9+/- 1.2 2i.'4 4+/- 3.0' 44.7 4 2.6 19.1 +/- 2.4 33.3 +/- 2.4 18.6 +/- 1.4 28.1 +/- 1.4 20.8 +/- 2.4 26.5 +/- 2.1 17.9 +/- 1.1 23.2 +/- 2.3 18.4 4 1.5 18.1 4 0.9 18.3 +/- 1.1 23.5 +/- 1.9 18.4 I 1.3

-17.2 0.9-18.3 +/- 1.5' 26.8 +/- 0.9~

25.7 +/- 0.8 25.8 +/- 1.3 19.1 +/- 0.9 25.5 +/- 0.9 44.1 +/- 3.0 18.1 +/- 1.1 31.6 +/- 1.9 16.8'+ 0.9 27.4 +/- 0.9 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 -

4GI '

6GI 7GI.

I I

7G2 8GI 1 2G1 19.9 4-1.2 20.0 1 1.4 19.5 + 2.0 17.1 + 1.2 17.3 1, 1.0 15.9 +/- 1.0 17.2 + 2.0 19.7 19.9 20.2 16.5 16.9 14.1 15.2 17.8

+ 1.7

+/- 0.6

+ 1.7

+ 0.9

+ 0.4

+ 1.1

+ 1.1

4 0.9 21.2 + 0.6 21.7 +/- 1.8 23.6 + 1.0 19.1 + 1.0 20.2 4: 0.7 17.3 + 1.8 17.8 +/- 0.8 21.3 4-1.4 21.2 + 0.0 21.3 + 0.6 21.9 + 0.6 18.5 + 0.6 18.8 + 1.9 16.9 1: 0.7 18.0 + 0.7 20.4 -1 0.4 12G4 20.3 i-

,.1, 4..

I

. See the comments at the end of this table.,.

.i, 3

2.

") ! !

X 7-A' 1.4 t,,

Location Indicator Average (5)

Control Average (5) 19.6 + 11.8 I.,

1

• 18.6 i1 12.9 21.9 4: 12.9 20.7 + 12.2 19.6 +/- 2.4 18.4 +/- 4.1 17.5 +/- 3.2 20.3 +/- 3.5 I

2 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 I

I' 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 2S7 6S5 LTAW 6S6 2S7 6S5

LTAW, 6S6 2S7 6S5 LTAW 6S6 6S7 6S5 LTAW 6S6 2S7 6S5 LTAW 6S6 2S7 6S5 LTAW 12/30/02 12/30/02 01/06/03 01/20/03 01/27/03 01/27/03 02/03/03 02/18/03 03/03/03 03/03/03 03/10/03 03/17/03 03/31/03 03/31/03 04/07/03 04/14/03 04/28/03 04/28/03 05/05/03 05/12/03 06/02/03 06/02/03 06/09/03 06/09/03 01/27/03 01/27/03 01/27/03 03/03/03 03/03/03 03/03/03 03/31/03 03/31/03 03/31/03 04/28/03 04/28/03 04/28/03 06/02/03 06/02/03 06/02/03 06/30/03 06/30/03 06/30/03

<129 170

• 87.3

<126

<149

<135 4770

• 177 1310 +/- 114 246

• 90.1

<146 16600 + 307

< 149

<147

<134 293

• 91.7

<123 244 +/- 87.5

<141 261

• 95.3

<142 225 +/- 92.7

<134 3790

• 166

<140 192 +/- 95.7 1.9 +/- 1.2 15.9 + 2.9 3.2

• 1.4 4.6

• 1.6

<2.01 8.3 + 2.4 4.5 + 1.8 3.7 + 1.6 4.3

• 1.5 9.9 + 2.2 3.2

• 1.4 4.0 + 1.4

<1.87 7.2

• 2.1 2.6

• 1.4 2.6 + 1.4

<1.76 10.9 + 2.4 3.9 + 1.4 3.7

• 1.6

<1.88 7.1 + 2.1 3.1

• 1.4 3.6 + 1.6 4.

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 1.01

'.50 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

(

(.

TABLE 1-3 IODINE-131 ANALYSES OF SURFACE WATER SUSQUEHANNA STEAM ELECTRIC STATION - 2003 I Rcsults in pCi/liter + 2S 1

(D LOCATION COLLECTION DATE 1-131 COMMENTS 6S6 2S7 6S5 LTAW 6S6 2S7 6S5 10/20/03 - 11/03/03 10/20/03 - 11/03/03 10/27/03 & 11/03/03 11/10/2003 11/03/03 - 11/17/03 11/03/03 - 11/17/03 11/10/03 & 11/17/03 6S6 11/17/03-12/01/03 2S7 11/17/03-12/01/03 6S5 11/24/03'&

12/01/03 6S6

- 12/01/03-12/15/03 2S7 12/01/03 - 12/15/03 6S5 12/08/03 & 12/15/03 LTAW 12/15/2003 6S6 12/15/03 - 12/29/03 2S7 12/15/03 - 12/29/03 6S5 12/22/03 & 12/29/03 Comments:

.15 4.27 1.91 +/-.70

.26.23

<0.41

.31 4.51

.68b.60

.24 +/-.44

.14 +/-.26

.23 4-.29

.01 +.15

.21 +/-.50 1.02 +/-.64

.32.45

.33 +/-.45

.15.46

.92 +/-.78

.27.45

• 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 ND IND 2H 2H 2H IND IND ND 2H 2H 2H Smallmouth Bass Shorthead Redhorse Channel Catfish Smallmouth Bass Shorthead Redhorse Channel Catfish Channel Catfish Smallmouth Bass White Sucker.

Channel Catfish Smallmouth Bass White Sucker 04/28/03 - 04/28/03 04/28/03 - 04/28/03 04/29/03 - 04/30/03 05/12/03 - 05/12/03 05/12/03 - 05/12/03 05/12/03 - 05/13/03 10/07/03 - 10/08/03 10/08/03 - 10/08/03 10/08/03 - 10/08/03 10/15/03 - 10/16/03 10/16/03 - 10/16/03 10/16/03 - 10/16/03 4.15 +.37 4.39 +.43 3.89 4.33 3.92 +.28 3.20 +.26 3.49 4.25 3.69 +.33 3.99 4-.37 1.30 4.14 3.44 1.37 1.30k.24 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 7B 12F LTAW 2B 7B 12F LTAW c-5/20/2003 5/20/2003 5/20/2003 5/20/2003 10/27/2003 10/27/2003 10/27/2003 10/27/2003 17.3 I.8 15.8 +/-.5 11.8 +/-.8 15.8 4.8 7.22 +/-.24 13.6 +/-.5 10.4 +/-.4 14.7 +/-.4

.11 +/-.03

.10 +/-.02

.09 +.04

<.03

.04 +/-.01

.07 +/-.02

<.02

<.01 2.45 4.65 2.86 +/-.59 2.12 4.85 1.96 +/-.61

.75 +/-.16 2.36 :.46 2.17 +/-.40 2.18 +/-.37 4.74 +.67 3.56 +.54 3.34 +.82 3.21 +/-.60 1.28 +.18 3.47 +/-.43 2.46 +.38 3.23 4.41 I-16 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 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 1/20/2003 1/20/2003 1/20/2003 2/18/2003 2/18/2003 2/18/2003 3/17/2003 3/17/2003 3/17/2003

<145

<149

<140

<135

<137 178 + 87.3

<143

<141

<143 12F3 2S2 4S4 Treated 2S2 -

4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated -

. I 4/14/2003 4/14/2003 4/14/2003 5/12i2003 5/12/2003 5/12/2003 6/9/2003 6/9/2003 6/9/2003 7/14/2003 7/14/2003 7/14/2003 8/11/2003 8/11/2003 8/11/2003

<131 167 83.1 142 + 83.2

<136

<136'

<137

<146

<145

<146

<147

<137

<143

<138

<140

<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 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 12F3 2S2 4S4 Treated 9/8/2003 9/8/2003 9/8/2003 10/13/2003 10/13/2003 10/13/2003 11/10/2003 11/10/2003 11/10/2003 12/15/2003 12/15/2003 12/15/2003

<139

<138 193 +/- 89.6

<125

<124

<122

<127

<122

<125

<121

<120

<126 c

C 1-18

(__

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 1/8/03-1/15/03 1/1503'- 1/22/03 1/22/03 1/29/03 '

i.

12.8 14.3 14 14.1

+ 2.2

+ 2.1

+/- 2.2

+/- 2.3 11.1' 2.3 14.2 + 2.2 18.6 + 2.5 14.6 + 2.3 FEB 1/29/03 '-215i03 215/03 - 2/12iO3 2/12/03 - 2/19/03 2/19/03 - 2/26/03 MAR 2/26/03 - 3/5/03 -

3/5/03 - 3/12/03 3/12/03 - 3/19/03 3/19/03'- 3/26/03' 3/26/03 -4/2/03 APR' 4/2/03 - 4/9/03:

4/9/03 - 4/16/03 4/16/03 - 4/23/03 4/23/03 - 4/30/03 MAY 4/30/03 5/7j03 5/7/03 - 5/14/03' 5/14/03 - 5/21/03 5/21/03 - 5/28/03 JUN 5/28/03 - 6/4/i03 6/4/03 - 6/11/03 6/11/03 - 6/18/03 6/18/03 - 6/25/03 6/25/03 - 7/2/03 13.8 b2.3 16.2 2.4 14.8 ' 2.2 16.2 + 2.4 9.9 b 2.0 12.2 + 2.1 12.6 + 2.3 17.7 ': 2.5 14.5 ' 2.3 18.8 9 2.6 216 I: 2.7 19.4 -

2.5 18.3 2.5 17.8 2.4 10.4 + 2.1 10.5 '

2.0 9.5 '

2.0 11.6 ' 2.0 7.6 "

1.9 9;6 2.0-13.0 + 2.2 15.9 + 2.3 10.5 b2.0 13.6 2.1 11.3 42.0 14.7 2.2 9.4 '

2.1 -'

10.5 4-2.1 9.3 2.1 7.3 + -1.9 7.9 4f 2.0 9.1

+ 2.0 3.2 +/- 1.5' 4.1 4-1.5 7.0 d 2.1 8.5 b2.3 5.8 +/- 2.2 10.5 *2.2 7.0 42.1 9.4 42.1 10.5 42.1 11.4 +/-2.2 16.9 + 2.6 23.5 + 3.0 14.6 + 2.8 13.8 + 2.3 20.6 + 2.8 17.3 I2.6 15.7 + 2.3 17.8 9 2.4 14.2 + 2.2 19.2 +2.3 19.7 + 2.6 25.9 1 2.8 17.6 2.4 12.6 2.5 10.5 9.5 + 2.0 14.3 + 2.1 15.0 + 2.3 15.3 +/-2.3 13.5 ' 2.4 11.2 +2.2 6.6 + 1.9 4.9 + 1.7 10.6 + 2.3 10.0 4 2.1 12.5 +/- 2.2 9.7- + 2.1 17.3 + 2.6 13.6 15.9 18.7 15.7

+2.5 4 2.2

+ 2.5

+ 2.3 13.1 13.7 17.6 18.2 16.7 17.8 14.9 14.9 I 2.6 4 2.2

+ 2.5

' 2.5 10.8 I 2.3 16.0 + 2.3 16.3 I 2.4 17.1 + 2.4 15.2 + 2.3 18.1 + 2.4 14.1 + 2.2 16.1 I 2.4 15.2 17.5 14.2 16.0 I 2.4 4 2.3

+ 2.2 I 2.4

+ 2.6 4 2.4 4 2.2

+ 2.4 17..9 +/- 2.!

18.2 4 2.'

17.9 4 il 9.8 ' - 2.(

10.4

• 2.t F.:

10.0 ' + 2.(

14.7 +/- 2.,

12.8 + 2.

11.4 +2.4 5

18.1

• 2.5 5

23.6 + 2.8 4

18.4

• 2.6 I-11.82.2 0

10.7 *2.0 9.9 2.1 2

12.7

• 2.1 1

14.3 2.2 D

13.3 + 2.2 2

11.1 + 2.3 9.3

• 2.1 9

7.0

• 2.0 5

5.2

• 1.7 1

9.2

• 2.2 8

8.5

• 2.0.!

0 11.0

• 2.2 1

10.4

• 2;1 8

21.9

• 2.8 19.5 +/- 2.6 18.6 4 2.5 18.4 + 2.5 11.7 *2.1 12.6

• 2.1 9.6

• 2.0 14.3

2.2 13.3 +/- 2.1 12.8 +/- 2.1 11.2 + 2.2 7.5 + 1.9 8.4

• 2.0 4.9

• 1.6 8.5

• 2.1' 7.9 +/- 1.9 10.3 +/- 2.0 11.7 +/-2.2 21.9 +/- 2.8 10.5 8.9 6.7 3.6 8.7 7.1 9.3

-10.6 18.1

+ 2.:

I 2.1

+ 1.'

i 1.I 4 2.

+ 1.I

+ 2.'

+ 2.

+ 2.

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 GAMMA* SPECTROSCOPIC ANALYSES OF COMPOSITED AIR PARTICULATE FILTERS SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in E-03 pCi/Cu. M. + 2S C

LOCATION COLLECTION DATE Be-7 K-40 OTIIER ACTIVITY

.I 6G1 8G1 3S2 12EI 12S1 13S6 01/02103 - 04/02/03 01/02/03 -04/02/03 01/02/03 - 04/02/03 01/02/03 -04i/2/03 01/02/03 - 04/02/03 01/02/03 - 04/02/03 91.1 + 10.3 93.4 +/- 7.03 106+/- 8.29 109 + 8.69 106 + 7.54 99.1 +/- 7.15

<5.01

<1.97

<3.05

<1.78

<6.66

<6.30 6GI 8GI 3S2 12E1 12S1 l 13S6 601 8G1 3S2 12EI 12SI 13S6 04/02.03 -07/2/03 04/02103 -07/2/03 04/02/03 -07/2/03 04/02/03 - 07/2/03 04/02/03;- 07/2/03 04/02/03 - 0712/03 07/02/03 - 10/01/03 07/02/03 - 10/01/03 07/02/03 - 10/01/03 07/02/03 - 10/01/03 07/02/03 - 10/01/03 07/02/03 - 10/01/03 74.7 +/- 9.41 88.5 +/- 9.42 86.6 +/- 10.4 91.4 +/- 8.50 83.2 +/- 12.2

• 111 +/- 11.1 I

7 89.2 +/- 8.23' 83.8 +/- 7.33 101 +/-2.47 86.7 +/- 9.03 97.7 +/- 8.28 85.5 +/- 9.95 4.16 +/- 2.31

<1.78

<3.40

<2.03

<1.99

<5.17

<2.81

<7.31

<.794

<3.27

<2.22

<8.26 6GI 8GI 3S2 12EI 12S I 13S6 10/01/03 - 12/30/03 10/01/03 - 12/30/03 10/01/03 - 12/30/03 10/01/03 - 12/30/03 10/01/03 - 12/30/03 10/01/03 - 12/30/03 70.3 +/- 6.57 66.3 +/- 7.22 69.3 +/- 5.85 74.9 +/- 7.10 76.5 +/- 4.33 67.0 +/- 6.96

<2.80

<7.83

<2.02

<2.60

<1.38

<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(

TABLE 1-10 IODINE-131, AND GAMMA* SPECTROSCOPIC ANALYSES OF MILK SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCifliter +/- 2S C

LOCATION 10D2 12B2 COLLECTION DATE 05/19/03 05/19/03 K40 14801 110 13501: 110 OTHER ACTIVITY COMMENTS 10GI 10DI 10D2 12B2 lOGI 10DI 10D2 1

2B2 1,,, j 16, "I...

10DI I 0D2 12B2 lobi 10DI IOD2 12B2 06/04/03 06/04/03 06/04103 06/04103 06/1 03' 06/19/03 06/19/03 07106/03 07/06/03) 07/21103 07/21/03 07/21/03 07121/03 1340+ 110 1390 +/- 140 1190b 160 1390 +/- 120 1400+/- 160 1460 160 1400 150 1350 150.

13501 +/-130 13401: 130, 1420 110.,

1500 110 1470 110 1340 150 1550 1 160 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 940k i94 i

i.

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 L 1.0 0.027 +/-.024 0.95 +.11

(_

(_

C 1-26 a

C TABKIE1-12 GAMMA* SPECTROSCOPIC ANALYSES OF FOOD PRODUCTS (FRUITS. AND VEGETABLES)

SUSQUEHANNA STEAM ELECTRIC STATION - 2003 Results in pCi/grn (wet) + 2S C

LOCA.TION SAMPLE TYPE COLLECTION DATE K-40 OTHER ACTIVITY 1 1D2' Potato 08/21/03 4.66 +.19 4.47 +.29

.I11F2 Potato 09/04/03

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 Nuclide Mn-54 Co-58 Fc-59 Co-60 Zn-65 Zr-95 Nb-95 Ru-103 1-131 Cs-134 Cs-137 Ba-140 La-140 Ce-141 Fish (pCi/g wet) 0.019 0.023 0.050 0.015 0.028 0.020 N/A N/A 0.100 0.010 0.015 0.300 0.040 N/A Sediment (pCi/g dry) 0.028 0.035 0.110 0.028 0.071 0.070 N/A N/A 0.173 0.032 0.033 0.310 0.100 N/A A

A Surface Water (pCi/I) 2.9 2.1 5.1 3.3 7.8 6.4 4.3 4.9 15.4 2.3 2.4 7.8 12.1 6.8 Ground Water (pCi/A) 4.1 4.6 10.2 5.3 14.4 7.8 5.8 5.3 8.1 5.2 4.8 9.0 10.1 7.8 Potable Water (pCi/I) 1.7 1.8 8.3 2.5 6.7 5.4 3.2 2.6 13.2 2.6 2.5 9.2 10.2 6.8 Nuclide Mn-54 Co-58 Fc-59 Co-60 Zn-65 Zr-95 Nb-95 Ru-103 1-131 Cs-134 Cs-137 Ba-140 -

La-140 Ce-141 Air Particulate (10-3 pCi/m3) 0.33 0.51 2.31 0.28 0.75 0.88 N/A N/A 70.3 0.27 0.29 36.2 11.5 N/A Milk (pCi/A) 5.5 5.1 12.4 5.7 13.4 7.7 6.1 5.2 8.2 4.8 4.4 6.7 7.8 8.1 Fruit/Veg.

(pCi/g wet) 0.008 0.008 0.032 0.009 0.025 0.016 N/A N/A 0.019 0.007 0.008 0.055 0.016 N/A Soil (pCi/g dry) 0.037 0.039 0.993 0.055 0.176 0.995 0.071 0.051 0.097 0.057 0.047 0.255 0.11 0.078 1-28 Ci U

APPENDIX J PERFORMNEUMR FRH ENiRoNMETAL SAMPLE-AMEDI 03

.j.

-i C

I...........

)

'A F W' k'a'P ANPENV.

E LABORATORY A E~~~~-R NVI'N-ENGINP.-E -D O0.

.,-.TELEDYNERto EG't A~

-r.,,',i 2003 Radiological Environmental Monitoring Report J-I

I I 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.

2003 Radiological Environmental Monitoring Report J-2 2003 Radiological Environmental Monitoring 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).

J-3 2003 Radiological Environmental Monitoring Report 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 No.

ERA Known Framatome FramatomelERA Nudide Result (a)

Results (a)

Ratio IERA Contrl Limits (b)

Medium Units Evaluation Rad-52 Rad-53 Rad-54 Water pai/I pCi/I pCi/i pcifl pCi/I pCi/I pci/I pCi/I Water pCill pCi/I Water pCi/I pCi/I pCi/I pCi/I pCi/I pCi/i Water.

pai/I pCi/I Gross Alpha Gross Beta Sr-89 Sr-90 Ba-133 CO60 Cs-134 Cs-137 Zn-65 Nat. Uranium H-3 1.131 Gross Alpha Gross Beta Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Nat. Uranium 131 Tritium 37.6 8.55 15.9 9.03 19.5 37.4 17.8 44.2 60.3 53.7 1250.0 20.8 65.1 31.6 58.8 20.6 20.7 I37.4.,

32.6

.44.3 60.2 11.4 28.2.'

14300 28 8.97 13 8.74 17.9 36.6 17.9 45.4 60 56 1080.0 21.4 0.74 1.05 0.82 0.97 0.92 0.98 1.01 1.03 1.00 1.04 0.86 1.03 1.08 1.01 0.94 0.91 0.96 1.00 0.95 1.06 1.02 1.01

.O."

0.99 1.03 70.4 31.9 55.5 18.7 19.9 37.4 31.0 47.0 61.3 11.5 28 14800 21.3-53.9 0.00-17.2 7.24-24.6 0.37-17.7 10.8-28.2 28.746.1 9.14-26.5 35.5-52.9 49.9-70.7 4.4-63.0 678-1820 15.6-26.0 36.9-93.3 22.940.3 50.1-67.5 11.9-29.3 12.0-29.i 28.746.1 23.941.3 35.6-53.0 49.8-70.6 6.20-16.6 23.0-33.4 llW0-16800 Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Rad-5!

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 I

ANALYTICS ENVIRONMENTAL RADIOACTIVITY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page I of 4)

Analytics Identifcatlon Calculated Framatome Framator Month/Year No.

Medium Units Nucide Results I Results R

ndAnalytlcs Ratlo March-03 E3600-162 March-03 E3597-62 E3597-162 E3598-162 Milk pCi/l pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I pCi/I Wae p 7iII Water pCifl Water pCi/I Water pCi/I pCi/I pCi/I pCi/I pCi~l pCi/I pCi/I pCi/i pCi/I pCi/I I1 31U.

1-131 Cc-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co60 Gr. Alpha Or. Beta 1-131LL*

1-131 Ce 141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 74 74 173 246 90 200 47 64' 47 93 162 53 186 70 70 168 238 88 195 42 63 46 90 157 72.5 73 170 244 86 196 44 61 47' 96 162 55 146 67.7 68 163 243 83 188 44 61 48 88 156 0.98 0.99 0.98 0.99 0.96 0.98 0.94 0.95 i.00 1.03 1.00 1.04 0.78 0.97 0.97 0.97 1.02 0.94 0.96 1.05 0.97 1.04 0.98 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 r

No.

Medium Units Nuclide Results I Results R

De/Analytics Ratio MonthtYea March-03 March-03 March-03 June-03 Junc-03 E3599-162 E3601-162 E3608-162 e3704-162 e3705-162 AP Falter Milk Water Water AP Filter pCi Gr. Alpha pCi Or. Beta pCi/I pCi/I pCi/I pCi/I pCi/I Sr-89 Sr-90 Sr-S9 Sr-90 H-3 49 148 133 12 114 10 11953 21 llS 52 157 121 13 1.06 1.06 0.91 1.08 104 II 0.91 1.10 10643 0.89 pCi Gr. Alpha pCi Gr. Beta 20 116 0.95 1.01 June-03 June-03 E3706-162 E3707-162 AP Filter AP Filter pCi Ce-141 pCi Cr-51 pCi Cs-134 pCi Cs-137 pCi Co-58 pCi Mn-54 pCi Fe-59 pCi Zn-65 pCi Co-60 pCi Sr-89 pCi Sr-90 C

154 130 56 125 50 101 54 99 72 87 24 149 134 54 135 53 110 60 110 71 0.97 1.03 0.96 1.08 1.06 1.09 1.11 1.11 0.99 78 24 0.90 1.00 J-7 C.

(~.,

(

CI TABL J-2 ANALYTICS ENVIRONMENTAL RADIOACTIViTY CROSS CHECK PROGRAM - 2003 FRAMATOME ANP QUALITY CONTROL SPIKE PROGRAM C

FRAMATOME ANP ENVIRONMENTAL (Page 3 of 4)

Identifncation No.

Medium Units Nuelide LABORATORY I

Analytics Calculated Fra Results I R nmatorne Framatome/Analytics Results Ratio Month/Year June-03 September-03 September-03 September-03 E3153-162 E3866-162 E3867.162 E3868.162 Milk W.

ae Water Water AP Filter pCi/

pCi/

pCiNl pCiAI pCi/I pCi/I pCi/I pcin Pain

.Pain pc~in guin pCillI Pei/,:

pCi/I p.Ci/I pCi/I pcvl pcin PCVI pcill PCVI.

1-131 1-131 LL Ce 141 Cr-SI Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Gross Alpha Gross Beta 1-131' 1-13ILL Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Ft-59 Zn-65 Co-60 103 103 283 239 103 230 93 186 99 181 li2 36 246 76 76 81 221 113 84, 94 88 75 166

.117 28 189 109 104 283 239 98 232 92 186 100 181 134 37 242 69 78 78 198 108 85 92 93, 74.

170 118 30 197 1.06 1.01 1.00 1.00 0.95 1.01 0.99 1.00 1.01 1.00 1.02, 1.03.

0.98 0.91 1.03 0.96.

0.90 0.96 1.01 0.98 1.06 0.99 1.02 1.01 1.07 1.04 pCi Or. Alpha pCi Gr. Beta

• 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)

Identification No.

Analytics Calculated Medium Units Nuctide Results Month/Year Framatome 1 Results Framatorne/Analytics Ratio Scptember-03 September-03

-3869-162 e3870-162 Millk Milk pCi/i pCi/I pCi/i pCi/I pCi/i pCi/I pCi/i pCi/I pCi/I pCi/I pCi/I pCi/i pCi/i 1-131 1-13ILL Cc-141 Cr-t5 Cs-134 Cs-137 Co-58 Mna54 Fe-59 Zn-65 Co-60 Sr-89 Sr-90 74 74 86 233 119 88 99 93 79 176 123 100 14 66 74 90 228 123 94 99

• 101 84 178

• 129

• 80 1 II 0.89 1.00 1.05 0.98 1.03 1.07 1.00 1.09 1.06 1.01 1.05 0.80 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 No.

Month/Year March-03 Marh-03 E3573.186 E3575.186 Medlum Units Sediment pCAg pCi/kg pCi/kg pCiAg pCi/g pC/kg

.,I pCAg pCi/kg Milk pallI PCA pC,/

pCi/

Pan pall pCiA pC'f Analyties Nuclide Calculated Results (a)

Ce-141 358 +/- 18 Cr-51 508 t 25 Cs-134 186 +/- 9 Cs-131 497 +/- 25 Co-58 96 +/- 5 Mn-54 133 t 65 Pe.59 98 +/ Zn-65 192 1

I Co-60 335 +/- 17 Framatome Results (a) 351 +/- i4 511 +/- 41 189 +/- 6 536 +/-9 97 5

132 11 104+/- 7 197 +/- 10 340 6

73 9,

19it 7 244 31 95 *4' 22i 6 50 3

70 4 51 +/-5 101 8

179 4

Framatome/Analytles Ratio 1-131 Ce. 14t Cr-51 Cs-134 Cs-137 '

Co-58 Mn-54 Fe-59 '

Zn-65 Co-60 75 '* 3 188

• 17 267

• 35 98 +/- 5 217 *22 51'* 2 '

70

• 3 '

51

• 2 101 t 5 176

• 16 0.98, 1.01 1.02 1.08 1.01 0.99.

1.06 1.03 1.01 0.97.

1.03, 0.91 0.97, 1.02 0.98 1.00 1.00 1.00, 1.02.

Marh-03 E3576-186 AP Filter pC pCi pCa pCa pCa pCa pCi pCi Ce-141 Cr-5I Cs134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 160

• 6 227 +/- 8 83

• 3 185 +/- 6 43

• 2 59 t 2 44

• 2'.

86 +/-f 3 149 +/-5 143 +/- 2 219 +/- 11 78 +/- 2

• 179 +/-3 41 +/-2 59 +/- 2 45 *2 87 *4

• 133 +/-2 0.89 0.96 0.94 0.97 0.96 0.99 1.01 1.01 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 MonthlYear No.

March-03 E3577-186 Medium Units AP FIlUr pCi pQ pCi pa pa pai pai pai pa Nucide Co-141 Cr-51 Cs134 Cs-137 Co-S58 Mn-54 Po-59 Zn-65 Co-60 Analytics Calculated Results (a) 133 +/- 5 189 t 7 69 t 2 154 +/- 5 36 t 1 50 t 2 36 t 1 72 t3 125 +/-4 Framatonme Results (a) 121 +/- 2 172 t 9 62 t 1 153 i 3 36 t 2 50 t 2 40+/-2 71 +/-4 113 +/- 2 Franatonte/Analytics Ratio 0.91 0.91 0.89 0.99 0.99 1.01 1.11 0.98 0.90 March-03 Jun-03 E3578.186 E3770-186 APSFItr Pa Co-141 pi Cr-51 pi Cs134 pa Cs-137 PC Co-58 pa Mn-54 pa Fe-59 pa Za-65 pO Co-60 APHFItr pai Co-141 Pa Cr-51 pa Cs134 pa Cs-137 pa Co-58 pa Mn-54 pa Fe-59 PCa Z-65 pa Co-60 171 t 6 242 t 8 89 t 3 197 t 7 46 t 2 63 t 2 47 t 2 91 t 3 159 t 6 230 t 8 194 +/- 7 84 t 3 188 t 7 76 t 3 151 t5 81 t3 148 t 5 108t4 162 t 2 235 t 11 82 t 2 200 t 3 44 +/- 2 68 t 2 53 t 2 95 t 4 148 t 2 0.95 0.97 0.93 1.02 0.96 1.08 1.12 1.05 0.93 209 t 2 190 t 11 78 t 2 191 t 3 74 t 2 157 +/- 3 85 t 3 157 +/- 5 100 t 2 0.91 0.98 0.93 1.02 0.98 1.04 1.04 1.06 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 +/-t 2

0.99 pCi Mn-54 133* 5 142t 3 1.06 pCi Pe-59 71+/- 2 78 +/-t 3

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 i pa Cr-51 190+/-e 1' 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 NA_

Analytics Medlunm Units Nuctide Calculated Results (a)

Frunatomne Results (a)

Franuatome/Analytlcs Ratio Mna^{WYrar a8allW$v 1 szr 1^o.

Squnber-03 Dccmber-03 E3891-186 Milk pCa pQi/1 piA PCW paiA PaA pQf pal pCzA pQa 1-131 Co-141 Cr-51 Cs-134 Cs 137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 75 t 2 188

• 11 510 t 87 261 t 23 193 t 12 216 t 15 203 t 14 173 t 10 385 +/- 50 270 t 24 76 t 2.5 83 t 8 191 t 6 543 t 35 245 +/- 6 196 +/- 5 214 t 6 187 t 5 173 & 7 398 +/- 12 283 t 5 85 +/- 6 1.10 1.01 1.06 0.94 1.02 0.99 0.92 1.00 1.03 1.05 1.12 E3977-186 Qaarcoal Filter pCi 1-131 E3978-186 CharcoalFilter pCi 1-131 E3979-186 Chsaroal Filter pCi 1-131 (a) Countlln error is two stairlanl deviations.

QC 68 t 2.3 86 t 2.9 78 t 6 94 +/-6 1.15 1.09 J-13 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 C

DOE -ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

FRAMATOME ANP ENVIRONMENTAL LABORATORY (Page 2 of 4)

Identification No.

MonthlYear Medium Units EML Known Framatome Nucilde Results Results Framatome/EML Ratio March-03 QAP 58 Water Bq/l Bq/l Bq/l Bq/l Bqtl Bq/l Bq/l Bq/1l Bq/l Bq/l Bq/l Bq/l H-3 Co-60 Sr-90 Cs-134 Cs-137 U-234 Pu238 U-238 Pu-239 Am-241 Gr. Alpha Gr. Beta 426.0 219.0 4.1 29.4 59.6 2.3 3.7 2.1 4.2 2.2 418.1 682.4 390.0 234.0 4.3 30.5 63.8 2.1 3.3 2.2 3.9 2.1 377.5 627.5 0.92 1.07 1.07 1.04 1.07 0.90 0.91 1.02 0.92 0.99 0.90 0.92 September-03 QAP 59 September-03 QAP 59 AP Filters Bq Co-60 Bq Cs-137 Bq Gr. Alpha Bq Gr. Beta Bq Mn-54 55.1 54.8 3.1 3.9 58.0 50.8 1973.0 488.0 56.0 57.1 2.8 3.1 58.3 1.02 1.04 0.88 0.80 1.01 (2)

Soil llq/kg Bqlkg nq/kg AcTh-228 Cs-137 K-40 51.7 2269.0 547.0 1.02 1.15 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 No.

Month/Year EMIL Known Framatome Framatome/EML Results Results Ratio Medium UInits Nuclide September-03 QAP 59 September-03 QAP 59 Water Bqtil Co-60 BqIl Cs-134 BqIl Cs-137 Bqtl Gross Alpha Bqtl Gross Beta 469.4 60.1 73.9 531.0 1790.0 (3) 513.0 63.0 80.3 622.0 1948.0 (3) 1.09 1.05 1.09 1.17 1.09 (3)

Vegetation Bq/kg (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 No.

MAPEP Known Resmlt Framatome Framatome/MIAPEP Results Ratio Month/Year Medium Unfit Nuclide Evaluation March-03 02-W1O Water Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L BqlL Bq/L Bq/L Bq/L Bq/L Bq/L Bq/L Am-241 Cs-134 Cs-137 Co-57 Co-60 Fe-55 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-233/234 U-238 Zn-65 058 421.00 329.00 57.00 38.20 96.00 32.90 13650 0.83 12.31 1.54 1.60 516.00 058 398.12 301.31 52.44 3654 87.00 3153 126.00 0.85 0.03 11.09 1.63 1.63 509.10 1.00 0.95 0.92 0.92 0.96 0.91 0.96 0.92 1.03 0.90 1.06 1.02 0.99 Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement False Positive (1)

Agreement Agreement Agreement Agreement March-03 03-S 10 Soil Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Bq/Kg Cs-134 Cs-137 Co-57 Co-60 Mn-54 Sr-90 K-40 Zn-65 238.00 832.00 530.00 420.00 137.00 714.00 652.00 490.00 248.60 848.80 544.40 439.20 143.70 626.60 673.70 51650 1.04 1.02 1.03 1.05 1.05 0.88 1.03 1.05 Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement J-19 C-0

(

C TAL, JC5 DOE - MAPEP MIXED ANALYTE PERFORMANCE (Page 2 of 2)

COMMENTS False positive. Condition Report (CR No. CR 03-14) generated by Framatome Env Lab to investigate and verify MDC of sample with MAPEP.

V I

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)

Identification No.

Analytics Calculated Results TBE Results TBE/Analytics Ratio MonthJYear Medium Units Nudide March-03 March-03 March-03 E3585-396 E3586-396 E3588-396 Milk Milk AP Filter pCi/I pCi/I pCi/I pCi/i pci/I pCi/I pCi/I pCi/i pCi/I pCviI pCi/i pCi/I pCi Poi pCi pCi pCi Poi pCi Poi pCi Poi Sr-89 Sr-90 1-131 Ce-141 Cr-SI Cs-134 Cs-137 Co-58 Mn-54 Fc-59 Zn-65 Co-60 Cc-141 Cr-SI Cs-134 Cs-137 Co-58 Mu-54 Fe-59 Zn-65 Co-60 Fe-55 133 11.8 74 173 246 90 200 47 64 47 93 162 224 318 117 259 60 83 61 120 209 106 80:

11.2 75 168 243 83, 207 49 65 53 114 169 239 348 101 277 66 97 80 152 223 138 0.60 0.95 1.01 0.97 0.99 0.92 1.04 1.04 1.02 1.13 1.23 1.04 1.07 1.09 0.86 1.07 1.10 1.17 1.31 1.27 1.07 1.30 (I)

(4)

(2)

(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 7 1 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)

Identirication No.

Analytics Calculated Results TBE Results TBE/Analytics Ratio Monthear Medium Units Nudide Septembcr-03 Scptember-03 Septcmbcr.03 E3898-396 E3899-396 E3901-396 Milk Milk AP Filter pCi/i pCi/I pCi/I pCi/I pCi/i pCi/I pCvi/

pCviI pCi/i pai/I pCi/I pCi/I pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi Sr-89 Sr-90 1-131 Cc 141 Cr-SI Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Fc-55 100 14 74 86 233 119 88 99 93 79 176 123 77 210 108 79 89 84 71 158 Ill 112 45 13:

73 85 220 106 90 96 95:

84

187, 132 79 227 93 70 80 73 74 143 93' 144 0.45 0.93 (I) 0.99 0.99 0.94 0.89 1.02 0.97 1.02 1.06 1.06 1.07 1.03 1.08 0.86 0.89 0.90 0.87 1.04 0.91 0.84 1.29 (4)

Scptcmber-03 Novcmbcr-03 E3900-396 Charcoal Filter pCi 1-131 Sr-89 Sr-90 86 168 17 74 185 19 0.86 1.10 1.12 E3790-396 Milk pCi/i pci/l 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)

Identirfcation No.

Analytics Calculated Results TBE Results TBWiAnalytics Ratio MonthlYear Medium Units Nuclide November-03 E3971-396 Milk pCili pCi/I pCi/I pCi/I pCin icill

' pCi/I pCi/I pCi/

pan/

1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60

, I.

I.

90 202 280 135 129 III 173

'102

-197 153 142 198 96 9-

! 1 ':

78 122 72 139.,

109 96 87 186 287 I119 116 iII 176

' 941

• 190.

140 144 203 90'

'If

,,,85'

- ~80(

11I 72 121 102 62.

0.97 0.92 1.03 0.88 0.90 1.00 1.02 0.92 0.96 0.90 1.01 1.03 0.94 0.93 1.03 0.94 1.00 0.87 0.94 0.65 (5)

,,, fNovember-03,;.

,S, E3973-396 4:tAP ilter pCi Ce-i41t pCi pCi 1;,

I pC i l pCi Cr-SI Cs-134 Cs-137 Co Mn-54 Fe-59 Zn-65.

Co-60 Fe-55

.pCi

. I pCi pCi pCi 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.

In addition, 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

Month/Year 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 No.

March-03 E3573-186 Meduhm Units Sediment pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg Milk pci/I pCi/i pCi/i pCi/I pCi/I pCai pcihx pCi/i pCi/i pCi/i pCi/i Nuclide Ce-141 Cr.51 -

Cs-134' Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 Ce-14i Cr-51, Cs.134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 March-03 E3569-186 E3570-186 Analytics Calculated Results (a) 358

• 18 508

• 25 186 +/- 9 497 : 25 96 +/- 5 133 +/- 65 98 +/- 5 192 1 1 335 +/- 17 75 3

188 +/- 17 267+/-,

35 98 +/-5' 217 +/-22 51+/-2 51 :2 101I:. 5 176 +/- 16 151.+/- 5 215 +/- 8 79 +/-i 3 175.+/- 6 41 +/-1 56 +/- 2 41 I

81 3

141 +/-'5 I~l i

TBE.

i Results (a) 409

• 17 576 +/- 99 180 +/- 9 598 +/-i 19 116 +/- 13 157 :+/- 13 120 +/- 17 271 +/- 23 408

• 13 6*4.

67 +/--7.

188:+/- 8 262 -

37 86 +/-3 214 +/- 7.

50

• 4 74 +/- 5 56 t 6 110 *9 173

• 5 0.89.

1.00; 0.98 0.88 0.99.

0.98 1.05 1.10 1.09 0.98 1.01 1.12.

0.84 1.03 1.09 1.06 1.29

-1.19 1.05 TBEJAnalytics Ratio I-1.14-1.13 0.97 1.20 1.21 1.18 1.22 1.41 1.22 (1)

March-03 AP Filter pCi Ce-141 pCi Cr-5I pCi Cs.134 pCi Cs-137' pCi' Co-58 pci Mn-54' pCi. -

Fe59 pCi Zn-65 pci Co-60 153 f 7 241 +/-38 67 +/- 4.

180 :9 45 +/-t 6 59.5 +/- 7 52.9 +/- 8 96.3 +/- 13 148 :t 7 (1)

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 No.

Analytics Calculated Results (a)

TBE Results (a)

TBE/Analytics Ratio MontblYear Medium Units Nuclide March-03 E3571-186 March-03 E3572-186 E3574-186 E3776-186 AP Filter AP Filter Water AP Filtcr pC pc pCi pCi pCi pCi pCi pCi pCi pC pCi pCi pc pCi pCi pc pCi pCi pCi/L pCi pCi pCi pCi pCi pCi pC pci pCi Cc-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 Cc-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fc-59 Zn-65 Co-60 H-3 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 156+/- 5 221 +/- 8 81 +/- 3 180 +/- 6 42+/- I 58 2

43 +/- 2 84 +/- 3 146 t 5 182 +/- 6 259 +/- 9 95 +/- 3 211 +/- 7 49 +/- 2 68 +/- 2 50+/- 2 98 +/- 3 170 +/- 6 4463 +/- 230 152 t 5 128 +/- 4 55 +/- 2 123 +/- 4 50 t 2 99 t 3 53 +/- 2 97 t 3 71 +/- 2 170 +/- 8 255 :+/- 46 65.3 +/- 5 187 t 9 39.5 +/- 8 59.1 +/- 7 51 +/- 9 110+/- 13 148 +/- 7 1.09 1.15 0.81 1.04 0.94 1.02 1.19 1.31 1.01 (I)

March-03 180 +/- 7 240 +/- 40 76.3 t 4 217 +/- 9 51.5 +/- 7 75.5 +/- 7 60.3 +/- 9 115 +/- 14 173 +/- 7 4840 +/- 176 157 +/- 17 142 +/- 102 58.3 +/- 8 147 +/- 14 46.5 +/- 14 105 +/- 14 63 +/- 19 115+/- 18 87.9 +/- 10 0.99 0.93 0.80 1.03 1.05 1.11 1.21 1.17 1.02 1.08 1.03 1.11 1.06 1.20 0.93 1.06 1.19 1.19 1.24 June-03 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 No.

Analytics Calculated Results (a)

TBE Results (a)

TBE/Analytics Ratio Month/Year Medium Units Nucide June-03 E3777A-186 AP Filter AP Filter

!- f,..

June-03 E3778A-i86 pCi pCi pCi pCi pCi pCi pCi pCi pCi pCi Pai.

P, pCi pCi.

pCi pCi pCi pCi' pCi pCi pOi Ce-141 Cr-51 Cs-134 Cs-137 Co-S8 Mn-54 Fe-59 Zn-65 Co-60 Ce 141 Cr-51, Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 1-131 238 +/- 8 201 +/- 7 87 +/- 3 194* 7 78 +/- 3 156 +/- 5 83 +/- 3 153 +/- 5 Ill +/- 4 140 +/- 5 118 +/-C4 51 +/- 2 114 +/- 4 46 +/- 2 92+/- 3 49 +/- 2 89 f 3 65 +/- 2 66 +/- 2' 267 + 20 176+/- 112 91 +/- 8 219+/- 17 84.3 +/- 13 172 +/- 17 107 +/- 20 179 +/- 23 127+/- II 128 +/- 20 122'+/-' 89 53.7 +/- 6 112+/- 12 35+/- 10 96.2 +/-l I i 42.4 18 74.1 +/-18 69.6 +/- 7 73.9 +/- 3 1.12 0.88 1.05 1.13 1.08 1.10 1.29 1.17 1.14 (1) 0.91I 1.03' 1.05, 0.98 0.76 1.05' 0.87, 0.83, 1.07, 1.12 June-03 E3779-186 Charcoal Filter June-03 E3780-186 Charcoal Filter E3781-186 Charcoal Filter pCi pCi 1-131 1-131 59 +/- 2 51 +/- 2 68.6 +/- 3 61.6 +/- 4 1.16 1.21 June-03

.,. I I....

(a) Counting error is two standard deviations.

-1 i

.I J-30

.. "I I.1 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 No.

Analytics Calculated Results (a)

TBE Results (a)

TBE/Analylics Ratio Month/Year Medium Units Nuclide Scptcmber-03 Scptcmber-03 E3889-186 E3890-186 Milk Watcr pCi/i pCi/I pCi/i pCi/I pCi/i pCi/i pCi/I pCi/I pCi/I pCi/I pCi/I 1-131 Ce-141 Cr-51 Cs-134 Cs-137 Co-58 Mn-54 Fe-59 Zn-65 Co-60 H-3 75 +/- 2 188+/- 11 510 t 87 261 +/- 23 193 +/- 12 216 t 15 203 +/- 14 173 +/- 10 385 t 50 270 +/- 24 8000 +/- 300 65.9 +/- 8 171 11 429 +/- 48 212 +/- 5 181 :t 8 197 +/- 8 202 t 9 177 +/- 10 368 +/- 16 264 +/- 7 8240 +/- 222 0.88 0.91 0.84 0.81 0.94 0.91 1.00 1.02 0.96 0.98 1.03 December-03 E3981-186 Charcoal Filter December-03 E3982-186 Charcoal Filter December-03 F3983-186 Charcoal Filter (a) Counting error is two standard deviations.

('

pCi 1-131 pCi 1-13 77 +/- 3 68 t 2 86 +/- 3 83 +/- 3 73 +/- 2 92 :+/- 5 1.07 1.07 1.07 pCi 1-131 J-31

(,

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

(

COMMENTS High Bias identified. Evaluation of results requested by PPL via email on April 19, 2004.

i i,

i i

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 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 2 of 4)

[cation EML Known TBE T

D.

Medlum Units Nuclide Result Results C

Identill N,

[IE/EML Ratio MonthfYear March-03 Septem303 QAP-58 QAP 59 Water Bqnl Bqll Bq/l Bq/l Bq/l Bq/1 Bq/l.

Bq/1 Bq/l Bq/l AP Filter Bq Bq Bq,,

Bq "

Bq Bq Bq Bq Bq Bq Bq Am-241 Co-60 Cs-134 Cs-137 Gr-Alpha Gr-Beta H-3 Pu-238.

Pu-239 Sr-90 Mn-54 Co-60,,

Sr-90.

Cs-137 U-234 Pu-238 U-238 Pu-239 Am-241 Gr-Alpha Gr-Beta 2.13 234 31 64 378 628 390 3.3 3.9 4.3 58 55.1.

2.1, 54.8 0.4 0.2 0.4 0.4 0.4 3.1 3.9 2.4 252 31 72 484 821 418.

.4.0 io 4.6 3.6 54 53.3, 1.7 51.2.

0.4 0.2 0.4.

0.4 0.4 3.1 3.4 1.13 1.08 1.02 1.12 1.28 1.31 1.07 1.20.

1.16 0.84 0.93 0.97.

0.81-0.93.,

0.92 1.00 0.93 1.00 0.90 1.00 0.87 (4)

(4)

(3)

J-34

TABLE J-9 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP)

TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 3 of 4) i Jdentillcatlonl EML Known TBlE 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 DOE - ENVIRONMENTAL MEASUREMENTS LABORATORY (EML)

QUALITY ASSESSMENT PROGRAM (QAP) I TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES (Page 4 of 4) l c

1 2

3 4

COMMENTS Gas flow Proportional efficiencies are established using Am-241, industry standard for clieni EML requires an efficiency based on Th-230. Using Th-230 efficiency, the result of 1.18 is NCR 03-07 generated by Teledyne to investigate condition.

Incorrect bottle size used. Sampie'was placed into a smaller container and recounted. All re except Bi-212 which was acceptable with warning. Previously analyzed samples were exam sizes were noted. NCR 03-07 generated by Teledyne to investigate condition.

The electroplating cell was determined to have trace amounts of plutonium, causing an eievw has been taken out of service.

Acceptable with warning. Reported result falls within 0.70-0.80 or 1.20-1.30.

samples.

acceptable.

count results were acceptable ined and no other incorrect container ted h-e o.

activity..The electroplating cell

. 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