W3F1-2004-0033, Annual Radioactive Effluent Release Report - 2003

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Annual Radioactive Effluent Release Report - 2003
ML041200159
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/27/2004
From: Sen G
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2004-0033
Download: ML041200159 (48)
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Text

Entergy Operations, Inc.

17265 River Road

/ C 1E(ve1 by Killona, LA 70066 Tel 504 739 6650 W3Fl-2004-0033 April 27, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Annual Radioactive Effluent Release Report - 2003 Waterford Steam Electric Station, Unit 3 (Waterford 3)

Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

Attached is the Annual Radioactive Effluent Release Report for the period January 1 through December 31, 2003. This report is being submitted pursuant to the requirements of Technical Specification Section 6.9.1.8.

If you have any questions please contact Mark Louque (504) 464-3267.

There are no new commitments contained in this submittal.

Sincerely, G en Licensing Manager GS/OPP/TMM/ssf Attachment(s) an7

W3Fl-2004-0033 Page 2 cc: (w/Attachment)

Mr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop 0-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502

Attachment I W3F1I-2004-0033 Annual Radioactive Effluent Release Report - 2003

Ent January 1, 2003 -December 31, 2003

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Originator:

Date Reviewed By:

/5- Zoocf Date Approved By:

Glenn M. Pierce Chemistry Superintendent Date Waterford 3 SES

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table of Contents 1.0 Introduction ............................................................. 1 2.0 Supplemental Information ............................................................. 2 2.1 Regulatory Limits .......................................................................... 2 2.1.1 Fission and Activation Gases (Noble Gases) .......................................................................... 2 2.1.2 lodines, Particulates with Half Lives > Eight (8) Days, and Tritium ............................................................ 3 2.1.3 Liquid Effluents ......................................................................... 3 2.1.4 Uranium Fuel Cycle Sources ......................................................................... 4 2.2 Maximum Permissible Concentrations ......................................................................... 4 2.2.1 Fission and Activation Gases, lodines, and Particulates, With Half Lives > Eight (8) Days ....................... 4 2.2.2 Liquid Effluents ......................................................................... 4 2.3 Average Energy (E-Bar) .......................................................................... 4 2.4 Measurements and Approximations of Total Radioactivity ......................................................................... 5 2.4.1 Fission and Activation Gases (Noble Gases) ......................................................................... 5 2.4.2 lodines, Particulates, and Tritium ......................................................................... 5 2.4.3 Liquid Effluents ......................................................................... 6 2.5 Batch Releases ......................................................................... 6 2.6 Unplanned/Abnormal Releases ......................................................................... 7 2.6.1 Unplanned/Abnormal Gaseous Releases ......................................................................... 7 2.6.2 Unplanned/Abnormal Liquid Releases ......................................................................... 7 3.0 Gaseous Effluents ............................................................. 7 4.0 Liquid Effluents ............................................................. 7 5.0 Solid Wastes ............................................................. 7 6.0 Meteorological Data ............................................................. 8 7.0 Assessment of Doses .............................................................. 9 7.1 Dose Due to Gaseous Effluents ......................................................................... 9 7.1.1 Air Doses at the Site Boundary ......................................................................... 9 7.1.2 Maximum Organ Dose to the Critical Receptor ........................................................................ 10 7.2 Doses Due to Liquid Effluents ......................................................................... 11 7.3 4 CFR Part0 190 D Evaluation ose ........................................................................ 11 i

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table of Contents 7.4 Doses to Public Inside the Site Boundary ............................................ 12 8.0 Related Information ...................................... 13 8.1 Changes to the Process Control Program ............................................ 13 8.2 Changes to the Offsite Dose Calculation Manual ............................................ 13 8.3 Unavailability of REMP Milk Samples ............................................ 14 8.4 Report of Required Effluent Instrument Inoperability ............................................. 14 8.5 Activity Released Via Secondary Pathways ............................................ 15 8.6 Missed Effluent Samples ............................................ 15 8.7 Major Changes to Radioactive Waste Systems ............................................ 15 8.8 Biennial Land Use Census ............................................ 15 8.9 Gaseous Storage Tank Total Radioactivity Limit ............................................ 16 8.10 Unprotected Outside Tank Total Radioactivity Limit ............................................ 16 9.0 Additional Information ...................................... 16 9.1 Reactor Coolant System Average Energy (E-Bar) ............................................ 16 10.0 Tables ...................................... 17 11.0 Attachments ...................................... 18 ii

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 1.0 Introduction This Annual Radioactive Effluent Release Report is submitted as required by Waterford 3's Technical Specification 6.9.1.8. It covers the period from January 1, 2003 through December 31, 2003. Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21 and in Section 5.8.1 of the Offsite Dose Calculation Manual (UNT-005-014).

The information contained in this report includes:

  • A summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period.
  • A summary of the meteorological data collected during 2003.
  • Assessment of radiation doses due to liquid and gaseous radioactive effluents released during 2003.
  • A discussion of Unplanned/Abnormal releases that occurred during the reporting period.
  • A discussion of why required radioactive effluent monitoring instrumentation was not returned to service within the time specified.
  • A discussion of any instances in which effluent samples were not collected within the required frequency.

Page 1 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 2.0 Supplemental Information 2.1 Regulatory Limits The limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections. These limits are addressed by reference in UNT-005-014, Offsite Dose Calculation Manual, and directly in the Technical Requirements Manual (TRM).

2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to:

  • 500 mrem/yr to the total body; and,
  • 3000 mrem/yr to the skin.

The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:

  • During any calendar quarter, Less than or equal to:
  • 5 mrad for gamma radiation; and,
  • 10 mrad for beta radiation.
  • During any calendar year, Less than or equal to:
  • 10 mrad for gamma radiation; and,
  • 20 mrad for beta radiation.

Page 2 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 2.1.2 lodines, Particulates with Half Lives > Eight (8) Days, and Tritium The dose rate due to fodine-131 and 133, Tritium, and all radionuclides in particulate form with half lives greater than eight (8) days, released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to less than or equal to:

  • 1500 mremlyr to any organ.

The dose to a member of the public from lodine-1 31 and 133, Tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

  • During any calendar quarter, Less than or equal to:
  • 7.5 mrem to any organ.
  • During any calendar year, Less than or equal to:
  • 15 mrem to any organ.

2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-4 pCi/mI (Total Activity).

The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:

During any calendar quarter, Less than or equal to:

  • 1.5 mrem to the total body; and,
  • 5 mrem to any organ, and Page 3of38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station During any calendar year, Less than or equal to

  • 3 mrem to the total body; and,
  • 10 mrem to any organ.

2.1.4 Uranium Fuel Cycle Sources The dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel cycle sources over 12 consecutive months shall be limited to less than or equal to:

  • 25 mrem to the Total Body or any organ (except thyroid organ); and,
  • 75 mrem to the Thyroid 2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases, lodines, and Particulates, With Half Lives > Eight (8) Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.

2.2.2 Liquid Effluents Ten times the effluent concentration (EC) values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.OE-4 pCi/ml is used as the concentration limit for dissolved and entrained noble gases in liquid effluents.

2.3 Average Energy (E-Bar)

This is not applicable to Waterford 3's effluent specifications. E-Bar's are not required to be calculated from effluent release data. The average energy (E-Bar) for the Reactor Coolant System (RCS) is supplied as additional information in the report further below.

Page 4 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 4.1 1-1 and 4.11-2 of the Technical Requirements Manual (TRM).

2.4.1 Fission and Activation Gases (Noble Gases)

For continuous releases, a gas grab sample was analyzed monthly for noble gases. Each week a Gas Ratio (GR) was calculated according to the following equation:

GR= Average Weekly Noble Gas Monitor Reading Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch. In all cases, the total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.

2.4.2 Iodines, Particulates, and Tritium lodines and particulates discharged were sampled using a continuous sampler which contained a charcoal cartridge and a particulate filter. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using gamma spectroscopy. The determined radionuclide concentrations and effluent volumes discharged were used to calculate the previous week's activity released. The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Framatome ANP, Environmental). Particulate gross alpha activity was measured weekly using alpha scintillation or gas-flow proportional counting techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled analysis was performed.

Grab samples of continuous releases were analyzed at least monthly for tritium. Containment Purge batch releases are analyzed prior to release. The determined concentrations were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed.

Page 5 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentrations were used to determine radionuclide concentrations in the following week's releases. For batch releases, gamma analysis was performed on the sample prior to release.

For both continuous and batch releases, composite samples were analyzed quarterly by a contract laboratory (Framatome ANP, Environmental) for Sr-89, Sr-90, and Fe-55. Samples were composited and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow proportional counting techniques, respectively. For radionuclides measured in the composite samples, the measured concentrations in the composite samples from the previous month or quarter were used to estimate released quantities of these isotopes in liquid effluents during the current month or quarter when the analysis results became available.

The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent discharged.

2.5 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 1.

Page 6 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 2.6 UnplannedlAbnormal Releases 2.6.1 Unplanned/Abnormal Gaseous Releases There were no unplanned/abnormal gaseous releases during the reporting period.

2.6.2 Unplanned/Abnormal Liquid Releases There were no unplanned/abnormal liquid releases during this reporting period.

3.0 Gaseous Effluents The quantities of radioactive material released in gaseous effluents are summarized in Tables 1A, 1B, and 1C. Note that there were no elevated releases, since all Waterford 3 releases are considered to be at ground level. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.

4.0 Liquid Effluents The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.

The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.

5.0 Solid Wastes The summary of radioactive solid wastes shipped offsite for disposal is listed in Table 3. For certain waste forms, Waterford 3 uses volume reduction services provided by a contractor. These waste forms are included in Table 3 and the volumes reported reflect the volume of waste shipped offsite, not final disposal volumes. Final disposal volumes for wastes compacted offsite are available upon request. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.

Page 7 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 6.0 Meteorological Data In Table 4, the hourly meteorological data from January 1, 2003 through December 31, 2003, is presented in the form of a joint frequency distribution of wind speed, wind direction, and atmospheric stability (hourly data is also available upon request). The standard Pasquill classification scheme, as presented in Regulatory Guide 1.23, is used to determine stability class from differential temperature measurements.

The Waterford-3 data recovery results by parameter are as follows:

Differiential Temp. 99.99%

Wind Speed 100.00%

Wind Direction 100.00%

Overall 99.99%

  • - Simultaneous occurrence of valid data for all three parameters.

Dispersion and deposition values were determined from the 2003 data and used in the assessment of doses due to gaseous effluents released from site during the 2003 period.

Page 8 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 7.0 Assessment of Doses 7.1 Dose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundary Air doses from gaseous effluents were evaluated at the closest offsite location that could be occupied continuously during the term of plant operation and that would result in the highest dose.

This location was determined by examining the atmospheric dispersion parameters (X/Q's) at the closest offsite locations that could be continuously occupied during plant operation in each of the meteorological sectors surrounding the plant. The location that would have the highest dose would be that location having the most restrictive (largest) X/Q value.

Based on actual meteorological data collected during 2003, this location was determined to be in the NNE sector (X/Q = 2.1 E-05 sec/iM3 ) at a distance of 869 meters (0.54 miles) from the plant.

Doses were assessed at this location in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only beta and gamma exposures in air due to noble gas. The results of these assessments for the year 2003 are summarized as follows:

Beta air dose: 1.888 mrad Gamma air dose: 0.429 mrad The above Beta and Gamma air doses represent the following percentage of the Annual Dose limits:

9.44% of the Beta air dose limit (20 mrad).

4.29% of the Gamma air dose limit (10 mrad).

Dose calculation results are summarized by quarters in Table 5A. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.

Page 9 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 7.1.2 Maximum Organ Dose to the Critical Receptor The maximum organ dose to a MEMBER OF THE PUBLIC from 1-131,1-133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8)days in gaseous effluents released to areas at and beyond the site boundary was determined for 2003.

An assessment of the maximum organ dose was performed for the critical receptor. The critical receptor was assumed to be located at the nearest residence to the plant having the most restrictive atmospheric dispersion (X/Q) and deposition (DIQ) parameters. Furthermore, it was assumed that the receptor living at this residence consumed food products that were either raised or produced at this residence.

Using land use census and meteorological data for 2002, the residence with the highest X/Q and D/Q values (7.5E-06 sec/M 3 and 1.9E-08 m 2, respectively) was determined to be in the NE sector at a distance of 1432 meters (0.89 miles) from the plant. The dose calculation was performed in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering the inhalation, ground plane exposure, and ingestion pathways. The maximum organ dose'to the critical receptor was determined to be:

0.188 mrem to the infant thyroid.

This represents 1.25% of the Annual Organ Dose limit (15 mrem).

Dose calculation results are summarized by quarters in Table 5A. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.

Page 10 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 7.2 Doses Due to Liquid Effluents The annual doses to the maximum exposed individual, an adult, resulting from exposure to liquid effluents released during 2003 from Waterford 3 were:

0.002 mrem to the Total Body.

0.003 mrem to the maximum exposed organ (Liver).

The above doses represent the following percentage of the Annual Dose limits:

0.07% of the Total Body Dose Limit (3 mrem), and 0.03% of the Organ Dose Limit (10 mrem).

Dose calculation results are summarized by quarter in Table 5B. The doses were calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.

7.3 40 CFR Part 190 Dose Evaluation In accordance with Technical Requirements Manual (TRM), Specification 314.11.4, Total Dose, dose evaluations to demonstrate compliance with Surveillance Requirements 4.11.4.1 and 4.11.4.2 of the Technical Requirements Manual (TRM), dealing with dose from the uranium fuel cycle, need to be performed only if quarterly doses exceed 3 mrem to the total body (liquid releases), 10 mrem to any organ (liquid releases), 10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to any organ from radioiodines and particulates.

At no time during 2003 were any of these limits exceeded; therefore, the evaluation was not required.

Page 11 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 7.4 Doses to Public Inside the Site Boundary The Member of the Public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee at the Waterford 1 and 2 fossil fuel plants, located in the NW sector at a distance of approximately 670 meters (0.42 miles) from the plant.

The doses for such an individual were determined by scaling the full-time occupancy doses due to airborne effluents by the occupancy time due to a normal working year. Based on an assumed occupancy of 25% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week) and the fact that all employees are adults, the calculated doses were determined to be less than:

3.32E-03 mrem to the maximum exposed organ (Thyroid) 3.72E-02 mrem to the Total body 1.22E-01 mrem to the skin Additionally, residential quarters for members of the Louisiana National Guard are located within the site boundary in the S sector at a distance of approximately 500 meters (0.31 miles) from the plant. These personnel have been intermittently stationed at the facility since October 29, 2002, following the terrorist attacks that occurred in New York and Washington, D.C. on September 11, 2001. These personnel are considered to be occupationally exposed during the performance of their duties.

The doses for an off-duty Louisiana National Guard individual were determined by scaling the full-time occupancy doses due to airborne effluents by the off-duty time during a typical duty schedule. Based on an assumed occupancy of 50% (12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts) and the fact that all employees are adults, the calculated annual doses were determined to be less than:

1.82E-02 mrem to the maximum exposed organ (Thyroid) 2.05E-01 mrem to the Total body 6.73E-01 mrem to the skin All doses for receptors inside the site boundary were calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only the inhalation and ground plane exposure pathways.

Page 12 of 38

2003 Annual Radioactive Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 8.0 Related Information 8.1 Changes to the Process Control Program No changes were made to the Process Control Program (PCP), Procedure RW-105, Revision 1.

8.2 Changes to the Offsite Dose Calculation Manual No changes were made to UNT-005-014 which implements the Waterford 3 Offsite Dose Calculation Manual (ODCM); however, changes were made to the applicable sections of the Technical Requirements Manual (TRM) during the reporting period which is programmatically part of the ODCM. The changes are discussed below.

The following changes were made to the TRM in accordance with NUREG 1301/Branch Technical Position during 2003:

  • The reporting level for tritium was changed from 20,000 pCi/l to 30,000 pCi/l if no drinking water pathway exists.
  • The reporting level for 1-131 in water was changed from 2 pCi/A to 20 pCi/A if no drinking water pathway exists.

+ The Lower Limit of Detection (LLD) for tritium was changed from 2,000 pCi/A to 3,000 pCi/A if no drinking water pathway exists.

  • The LLD for 1-131 in water was changed from 1 pCiA to 15 pCiI if no drinking water pathway exists.
  • The LLD for Zr-95 was modified from 30 pCiA to 15 pCiI to be consistent with NUREG-1 301.
  • Ba-140 was modified from 60 pCi/l in water to 15 pCi/l in water and from 60 pCiA in milk to 15 pCi/l in milk.

TRM Table 3.12-2 provides reporting levels for radioactivity concentrations in environmental samples.

NUREG-1301 'Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors' defines reporting level requirements for radioactivity concentrations in environmental samples. The Waterford 3 ODCM was initially developed using previous guidance provided in NUREG-0472. As defined in NUREG-1301, the reporting level for tritium is 20,000 pCi/l in drinking water and 30,000 pCi/l in surface water. TRM Table 3.12-2 did not make the distinction that the 20,000 pCi/l reporting level identified on the table is for drinking water. This change added a notation to provide clarification that the tritium reporting level is 20,000 pCi/l for drinking water and 30,000 pCi/l for surface water, as per NUREG-1 301.

Page 13 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station During a comparison review of TRM Table 3.12-2 to guidance provided in Table 3.12-2 of NUREG-1301, it was identified that clarification was needed to make the distinction that the defined reporting level is for drinking water. This change added a notation to provide clarification that the lodine-131 reporting level is 2 pCiA for drinking water and 20 pCi/A for surface water.

During a comparison review of TRM Table 4.12-1 and NUREG-1301 Table 4.12-1 differences were identified in LLD levels in water and milk. TRM Table 4.12-1 is being revised to conform with the guidance provided in NUREG-1301 Table 4.12-1. This change added a notation to provide clarification that the tritium LLD level is 2000 pCi/I for drinking water and 3000 pCin for surface water. Note 'd' was modified to provide clarification that the lodine-131 LLD level is 1 pCi/A for drinking water and 15 pCiA for surface water. Zr-95 was modified from 30 pCiI to 15 pCiI to be consistent with NUREG-1301. Ba-140 was modified from 60 pCi/l in water to 15 pCi/i in water and from 60 pCi/l in milk to 15 pCiA in milk.

Copies of the affected TRM tables are included in this report in Attachment 11.1.

8.3 Unavailability of REMP Milk Samples Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with Technical Requirements Manual (TRM) Table 3.12-1. Milk is collected, when available, from the control location and one identified sampling location as indicated in UNT-005-014, Offsite Dose Calculation Manual, Attachment 7.13.

8.4 Report of Required Effluent Instrument Inoperability Technical Requirements Manual (TRM) Specifications 3.3.3.10 and 3.3.3.11 require reporting in the Annual Radioactive Effluent Release Report of why designated inoperable effluent monitoring instrumentation was not restored to operability within the time specified in the Action Statement.

During the reporting period, all instrumentation was restored to operability within the time specified.

Page 14 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 8.5 Activity Released Via Secondary Pathways The following secondary release paths were continuously monitored for radioactivity:

  • The Hot Machine Shop Exhaust (AH-35),
  • Decontamination Shop Exhaust (AH-34),
  • The RAB H&V Equipment Room Ventilation system Exhaust (E-41A and E-41 B); and,

. The Switchgear/Cable Vault Area Ventilation System (AH-25).

Continuous sampling for these areas is maintained in order to demonstrate the operability of installed treatment systems and to verify integrity of barriers separating primary and secondary ventilation systems.

Sampling for these areas was limited to continuous particulate and iodine sampling and monthly noble gas grab sampling. The activity released via these secondary pathways resulted from routine operations and remained below significant levels.

8.6 Missed Effluent Samples During the reporting period, no incident occurred for which effluent samples were not sampled and/or analyzed as required by the ODCM/TRM.

8.7 Major Changes to Radioactive Waste Systems During the reporting period, no major changes were made to any Radioactive Waste Systems. All major changes to Radioactive Waste Systems are included in Waterford 3's FSAR updates.

8.8 Biennial Land Use Census A land use census was last performed in 2002. The land use census performed in 2002 did not identify the need for any changes to locations being used for effluent dose calculations or radiological environmental sampling.

Page 15 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 8.9 Gaseous Storage Tank Total Radioactivity Limit Technical Specification 3/4.11.2.6 specifies that the quantity of radioactivity contained in each gas storage tank be maintained less than or equal to 8.5E+04 Curies noble gas (considered as Xe-1 33 equivalent). At no time during the reporting period was this value exceeded.

8.10 Unprotected Outside Tank Total Radioactivity Limit Technical Specification 3/4.11.1.4 specifies that the quantity of radioactive material contained in each unprotected outdoor tank be maintained less than or equal to 7.85E-04 Curies (excluding tritium and dissolved and entrained noble gases). During this reporting period, there were no instances in which this limit was exceeded.

9.0 Additional Information 9.1 Reactor Coolant System Average Energy (E-Bar)

The most recent Reactor Coolant System E-Bar calculation was 0.22 MeV/Disintegration from a sample obtained on December 15, 2003. Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.

Page 16 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 10.0 Tables Table 1, Batch Release Summary ...................................................................... 19 Table IA, Annual Summation of All Releases By Quarter, All Airborne Effluents .............. 20 Table IB, Annual Airborne Continuous Elevated and Ground Level Releases, Totals for Each Nuclide Released ...................................................................... 21 Table IC, Annual Airborne Batch Elevated and Ground Level Releases, Totals for Each Nuclide Released ...................................................................... 22 Table 2A, Annual Summation of All Releases by Quarter, All Liquid Effluents .................. 23 Table 2B, Annual Liquid Continuous and Batch Releases, Totals for Each Nuclide Released ...................................................................... 24 Table 3, Solid Waste Shipped Offsite for Burial or Disposal ................................................ 25 Table 4, Joint Frequency Distribution of Meteorological Data............................................. 32 Table 5A, Doses Due to Gaseous Radioactive Effluents ............................................... 36 Table 5B, Doses Due to Liquid Radioactive Effluents ................................................ 37 Page 17 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station 11.0 Attachments Attachment 11.1, Copy of Applicable Sections of the Technical Requirements Manual (TRM), which are programmatically part of the ODCM.

Page 18 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table I Batch Release Summary Batch Release Summary information for 2003 Report Period.

Report Category  : Batch Release Summary Release Point  : All Type of Release  : Batch Liquid and Gaseous Period Start Time : 01-jan-2003 00:00:00 Period End Time  : 31-dec-2003 23:59:59 Liquid Releases Number of Releases  : 140 Total Time for All Releases  : 39744.1 Minutes Maximum Time for a Release  : 471.0 Minutes Average Time for a Release  : 283.9 Minutes Minimum Time for a Release  : 148.0 Minutes Average Stream Flow  : 818489.3 GPM Gaseous Releases Number of Releases  : 3 Total Time for All Releases  : 1022.0 Minutes Maximum Time for a Release  : 600.0 Minutes Average Time for a Release  : 340.7 Minutes Minimum Time for a Release  : 8.0 Minutes Batch Release Summary information for 2003 by Quarter.

Report Category  : Batch Release Summary Release Point  : All Type of Release  : Batch Liquid and Gaseous Period Start Time : 01-jan-2003 00:00:00 Period End Time  : 31-dec-2003 23:59:59 Liquid Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Number of Releases  : 28 22 36 54 Total Time for All Releases  : 7647.0 6008.0 10482.0 15607.1 Minutes Maximum Time for a Release  : 307.0 319.0 336.0 471.0 Minutes Average Time for a Release  : 273.1 273.1 291.2 289.0 Minutes Minimum Time for a Release  : 178.0 185.0 198.0 148.0 Minutes Average Stream Flow  : 766783.1 861354.0 1000042.2 705389.1 GPM Gaseous Releases Qtr 1 Qtr 2 Qtr 3 Qtr 4 Number of Releases  : 0 0 0 3 Total Time for All Releases  : 0.0 0.0 0.0 1022.0 Minutes Maximum Time for a Release  : 0.0 0.0 0.0 600.0 Minutes Average Time for a Release  : N/A N/A N/A 340.7 Minutes Minimum Time for a Release  : N/A N/A N/A 8.0 Minutes Page 19 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 1A Annual Summation of All Releases by Quarter All Airborne Effluents Report Category  : Summation of All Releases Type of Activity  : All Airborne Effluents Period Start Time  : 01-jan-2003 00:00:00 Period End Time  : 31-dec-2003 23:59:59 Est.Total Type of Effluent Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Error %

A. Fission and Activation Gases

1. Total Release Curies 0.00e+00 1.58e+01 3.66e+02 1.89e+03 1.50e+01
2. Average Release Rate for Period uCi/sec 0.OOe+00 2.01e+00 4.61e+0l 2.37e+02
3. Percent of Applicable Limit n/a n/a n/a n/a B. Radioiodines
1. Total Iodine-131 Curies 4.74e-07 1.18e-07 0.00e+00 2.51e-04 1.50e+0l
2. Average Release Rate for Period uCi/sec 6.09e-08 1.50e-08 0.OOe+00 3.15e-05
3. Percent of Applicable Limit n/a n/a n/a n/a C. Particulates
1. Particulates (Half-lives > 8 Days) Curies O.OOe+00 0.OOe+00 1.62e-07 2.55e-05 l.50e+Ol
2. Average Release Rate for Period uCi/sec 0.00e+00 0.OOe+00 2.04e-08 3.20e-06
3. Percent of Applicable Limit  % n/a n/a n/a n/a
1. Gross Alpha Radioactivity Curies 1.12e-06 4.25e-07 5.08e-07 1.21e-06 1.50e+0l D. Tritium
1. Total Release Curies 4.19e+0l 9.70e+00 4.36e+00 1.26e+Ol 1.50e+01
2. Average Release Rate for Period uCi/sec 5.38e+00 1.23e+00 5.49e-01 1.58e+00
3. Percent of Applicable Limit  % n/a n/a n/a n/a Page 20 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 1B Annual Airborne Continuous Elevated and Ground Level Releases Totals for Each Nuclide Released Report Category Airborne Continuous Elevated and Ground Level Releases.

Totals for Each Nuclide Released.

Type of Activity Fission Gases, lodines, and Particulates Period Start Time : 01-jan-2003 00:00:00 Period End Time 31-dec-2003 23:59:59 Elevated Releases Ground Releases Nuclide Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Qtr 1 Qtr 2 Qtr 3 Qtr 4 Fission and Activation Gases Kr-85 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.70e+02 Xe-131m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.08e+01 Xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.58e+0l 3.57e+02 1.33e+03 Xe-133m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.22e+00 1.28e+01 Xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.03e+00 1.25e+00 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.58e+01 3.66e+02 1.85e+03 Radioiodines 1-131 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.34e-07 1.04e-07 0.00e+00 2.50e-04 I-132 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.40e-08 0.00e+00 0.00e+00 I-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.39e-07 0.00e+00 0.00e+00 9.45e-07 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.74e-07 1.18e-07 0.00e+00 2.51e-04 Particulates H-3 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.19e+01 9.70e+00 4.36e+00 1.24e+0l Co-58 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.37e-06 Nb-95 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.04e-06 Ru-103 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.82e-07 Cs-137 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.62e-07 2.52e-07 Os-185 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.01e-07 Os-191 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.12e-05 Gralpha Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.12e-06 4.25e-07 5.08e-07 1.21e-06 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.19e+0l 9.70e+00 4.36e+00 1.24e+0l Page 21 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table IC Annual Airborne Batch Elevated and Ground Level Releases Totals for Each Nuclide Released Report Category  : Airborne Batch Elevated and Ground Level Releases.

Totals for Each Nuclide Released.

Type of Activity  : Fission Gases, lodines, and Particulates Period Start Time : 01-jan-2003 00:00:00 Period End Time  : 31-dec-2003 23:59:59 Elevated Releases Ground Releases Nuclide Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Otr 1 Qtr 2 Qtr 3 Qtr 4 Fission and Activation Gases Ar-41 Curies 0.OOe+00 0.00e+00 0.00e+00 O.OOe+00 0.OOe+00 0.OOe+00 0.00e+00 7.24e-02 Kr-85 Curies 0.00e+00 0.OOe+00 0.00e+00 0.OOe+00 0.OOe+00 0.OOe+00 0.00e+00 1.33e+01 Xe-131m Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 5.00e-01 Xe-133 Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 2.68e+0l Xe-133m Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 1.27e-01 Xe-135 Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 8.63e-03 Total for Period Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 4.08e+Ol Radioiodines None Particulates H-3 Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 2.04e-01 Total for Period Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 0.OOe+00 2.04e-01 Page 22 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 2A Annual Summation of All Releases by Quarter All Liquid Effluents Report Category  : Summation of All Releases Type of Activity  : All Liquid Effluents Period Start Time  : 01-jan-2003 00:00:00 Period End Time  : 31-dec-2003 23:59:59 Est.Total Type of Effluent Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Error %

A. Fission and Activation Products

1. Total Release (Not Including Tritium, Gases, and Alpha Curies 9.80e-03 3.20e-03 6.16e-03 4.19e-02 l.50e+01
2. Average Diluted Concentration During Period uCi/sec 2.l6e-11 4.29e-12 8.90e-12 8.71e-11
3. Percent of Applicable Limit n/a n/a n/a n/a B. Tritium
1. Total Release Curies 3.91e+0l 8.60e+0l 1.04e+03 1.69e+02 l.50e+0l
2. Average Diluted Concentration During Period uCi/sec 8.63e-08 l.15e-07 1.51e-06 3.52e-07
3. Percent of Applicable Limit n/a n/a n/a n/a C. Dissolved and Entrained Gases
1. Total Release Curies 8.07e-03 2.02e-02 1.24e+00 3.58e-01 l.50e+0l
2. Average Diluted Concentration During Period uCi/sec 1.78e-11 2.71e-11 1.79e-09 7.45e-10
3. Percent of Applicable Limit  % n/a n/a n/a n/a D. Gross Alpha Radioactivity
1. Total Release Curies 0.00e+00 0.OOe+00 0.OOe+00 0.00e+00 l.50e+0l E. Waste Volume Released (Pre-Dilution) Liters 8.58e+06 1.03e+07 1.12e+07 1.47e+07 1.50e+0l F. Volume of Dilution Water Used Liters 4.53e+11 7.45e+11 6.93e+11 4.81e+ll 1.50e+0l Page 23 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 2B Annual Liquid Continuous and Batch Releases Totals for Each Nuclide Released Report Category  : Liquid Continuous and Batch Releases.

Totals for Each Nuclide Released.

Type of Activity  : All Radionuclides Period Start Time : 01-jan-2003 00:00:00 Period End Time  : 31-dec-2003 23:59:59 Continuous Releases Batch Releases Nuclide Units Qtr 1 Qtr 2 Qtr 3 Otr 4 Qtr 1 Qtr 2 Qtr 3 Qtr 4 All Nuclides H-3 Curies 1.02e+00 3.99e-01 1.87e-01 3.16e-02 3.81e+0l 8.56e+01 l.04e+03 1.69e+02 Ar-41 Curies 0.00e+00 0.OOe+00 0.00e+00 0.00e+00 0.00e+0O 0.OOe+00 3.88e-06 0.00e+00 Cr-51 Curies 0.OOe+00 0.OOe+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.56e-04 Mn-54 Curies 0.OOe+00 0.00e+00 0.00e+00 0.00e+00 3.67e-04 2.00e-05 2.25e-04 3.87e-05 Fe-55 Curies 0.00e+00 0.OOe+00 0.00e+00 0.00e+00 1.20e-03 2.71e-03 3.64e-03 3.83e-03 Fe-59 Curies 0.00e+00 0.OOe+00 0.00e+00 0.00e+00 8.86e-06 0.OOe+00 0.OOe+00 1.67e-05 Co-57 Curies 0.OOe+00 0.00e+00 0.OOe+00 0.00e+00 1.24e-04 3.41e-06 9.71e-06 1.08e-04 Co-58 Curies 0.00e+00 0.00e+00 0.OOe+00 1.49e-06 4.37e-03 8.41e-05 2.59e-04 3.37e-02 Co-60 Curies 0.00e+00 0.OOe+00 0.00e+00 l.55e-05 1.20e-03 7.00e-05 1.21e-03 9.93e-04 Zn-65 Curies 0.00e+00 0.OOe+00 0.00e+00 0.00e+00 0.OOe+00 0.00e+00 1.13e-05 1.02e-05 Kr-85 Curies 0.OOe+00 0.OOe+00 0.OOe+00 0.00e+00 5.32e-03 1.75e-02 1.21e-01 1.67e-02 Kr-85m Curies 0.00e+00 0.00e+00 0.OOe+00 0.00e+00 0.OOe+00 0.OOe+00 2.81e-05 0.OOe+00 Kr-87 Curies 0.00e+00 0.OOe+00 0.00e+00 0.OOe+00 0.OOe+00 0.00e+00 l.OOe-05 0.00e+00 Zr-95 Curies 0.OOe+00 0.OOe+00 0.00e+00 0.OOe+00 3.12e-04 0.OOe+00 0.OOe+00 2.72e-05 Nb-95 Curies 0.OOe+00 0.00e+00 0.OOe+00 0.00e+00 6.03e-04 1.46e-05 3.50e-05 9.89e-06 Ag-110m Curies 0.00e+00 0.OOe+00 0.OOe+00 0.00e+00 1.65e-04 0.00e+00 1.36e-04 6.35e-05 Sn-113 Curies 0.00e+00 0.OOe+00 0.00e+00 0.00e+00 2.22e-05 0.00e+00 5.96e-05 4.41e-05 Sb-122 Curies 0.OOe+00 0.OOe+00 0.00e+00 0.00e+00 0.OOe+00 0.OOe+00 0.OOe+00 1.63e-05 Sb-124 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.OOe+00 0.00e+00 l.91e-04 Sb-125 Curies 0.00e+00 0.00e+00 0.OOe+00 0.00e+00 1.37e-03 2.6le-04 4.11e-04 2.60e-03 Sb-126 Curies 0.00e+00 0.OOe+O0 0.00e+00 0.00e+00 0.OOe+00 0.OOe+00 0.OOe+00 3.72e-06 1-131 Curies 0.OOe+00 0.OOe+00 0.00e+00 6.95e-05 6.68e-06 0.00e+00 0.OOe+00 0.00e+00 Xe-131m Curies O.00e+00 0.00e+00 0.OOe+00 0.OOe+00 0.00e+00 0.OOe+00 2.21e-02 6.06e-03 Xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.70e-03 2.6le-03 l.09e+00 3.35e-01 Xe-133m Curies 0.00e+00 0.OOe+00 0.00e+O0 0.OOe+OO 2.57e-05 2.00e-05 3.83e-03 1.07e-03 Xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.67e-06 4.29e-06 9.77e-04 3.12e-06 Xe-135m Curies 0.00e+00 0.00e+00 0.OOe+00 0.00e+00 2.19e-05 0.OOe+00 0.00e+00 0.00e+00 Cs-134 Curies 0.OOe+00 0.OOe+00 0.00e+00 4.80e-06 2.51e-05 1.55e-05 6.60e-05 0.00e+00 Cs-137 Curies 0.00e+00 0.00e+00 0.00e+00 4.47e-05 2.80e-05 l.99e-05 l.Ole-04 2.15e-06 Total for Period Curies 1.02e+00 3.99e-01 1.87e-01 3.17e-02 3.81e+01 8.56e+0l 1.05e+03 1.70e+02 Page 24 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal

SUMMARY

BY MAJOR WASTE TYPES Waste Stream: Resins, Filters, and Evap Bottoms.

Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 6.60E+02 1.87E+01 1.68E-03 +/- 25%

B 0.OOE+00 0.00E+00 O.OOE+00 +/- 25%

C O.00E+00 0.OOE+00 O.OOE+00 +/- 25%

All 6.60E+02 1.87E+01 1.68E-03 +/- 25%

Waste Stream Dry Active Waste 4 Waste Volume Curies %Error Class FtA3 MA3 Shipped (Ci)

A 7.94E+03 2.25E+02 4.04E-01 +/-25%

B 0.00E+00 O.OOE+00 0.00E+00 +/-25%

C 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

All 7.94E+03 2.25E+02 4.04E-01 +/-25%

Waste Stream : Irradiated Components Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

B 0.OOE+00 0.OOE+00 0.00E+00 +I-25%

C 0.OOE+00 0.00E+00 0.OOE+00 +I-25%

All 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

Waste Stream : Other Waste (Combined Packages)

Waste Volume Curies  % Error Class FtA3 M^3 Shipped (Ci)

A 4.89E+03 1.38E+02 4.44E+00 +/-25%

B O.OOE+00 0.OOE+00 0.OOE+00 +/-25%

C O.00E+00 0.OOE+00 0.OOE+00 +I-25%

All 4.89E+03 1.38E+02 4.44E+00 +/-25%

Waste Stream : Sum of All 4 Categories Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 1.35E+04 3.82E+02 4.84E+00 +/-25%

B 0.OOE+00 0.00E+00 0.00E+00 +I-25%

C 0.OOE+00 0.OOE+00 0.00E+00 +I-25%

All 1.35E+04 3.82E+02 4.84E+00 +1-25 4 Activity determined by estimations

  • Activity determined by measurements Page 25 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Estimate of major nuclide composition (by waste type)

Waste Stream: Resins, Filters, and Evap Bottoms Nuclide Percent Name Abundance Curies Mn-54 0.018% 2.94E-07 Fe-55 73.526% 1.24E-03 Co-60 10.996% 1.85E-04 Cs-134 7.005% 1.18E-04 Cs-137 8.456% 1.42E-04 Page 26 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Estimate of major nuclide composition (by waste type)

Waste Stream : Dry Active Waste Nuclide Percent Name Abundance Cures H-3 0.957% 3.87E-03 Mn-54 1.328% 5.37E-03 Fe-55 44.943% 1.82E-01 Co-57 0.061% 2.46E-04 Co-58 5.597% 2.26E-02 CO-60 5.015% 2.03E-02 Ni-63 13.283% 5.37E-02 Sr-89 0.007% 2.83E-05 Sr-90 0.020% 8.08E-05 Zr-95 0.203% 8.20E-04 Nb-95 0.090% 3.62E-04 Ag-1I0m 0.469% 1.90E-03 Sb-125 0.554% 2.24E-03 1-131 0.000% 2.75E-07 1-133 0.000% 8.69E-12 Xe-133 0.003% 1.05E-05 Xe-135 0.000% 2.13E-19 Cs-134 10.017% 4.05E-02 Cs-137 16.993% 6.87E-02 Ce-144 0.389% 1.57E-03 Pu-238 0.001% 3.76E-06 Pu-239 0.000% 2.45E-07 Pu-240 0.000% 1.06E-06 Pu-241 0.065% 2.63E-04 Am-241 0.000% 1.87E-06 Cm-242 0.002% 6.96E-06 Cm-243 0.000% 1.56E-06 Cm-244 0.003% 1 AOE-05 Page 27 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Estimate of major nuclide composition (by waste type)

Waste Stream : Irradiated Components N/A - None Shipped in 2003.

Page 28 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Estimate of major nuclide composition (by waste type)

Waste Stream : Other Waste (Combined Packages)

Nuclide Percent Name Abundance Cures H-3 0.894% 3.97E-02 Cr-51 1.197% 5.31E-02 Mn-54 2.569% 1.14E-01 Fe-55 54.751% 2.43E+00 Fe-59 0.074% 3.27E-03 Co-57 0.068% 3.02E-03 Co-58 10.625% 4.71E-01 Co-60 4.968% 2.20E-01 Ni-63 6.705% 2.97E-01 Sr-90 0.068% 3.02E-03 Zr-95 1.798% 7.98E-02 Nb-95 2.617% 1.16E-01 Ag-110m 0.003% 1.54E-04 Sn-113 0.105% 4.65E-03 Sb-i125 0.539% 2.39E-02 Cs-134 4.941% 2.19E-01 Cs-1 37 7.560% 3.35E-01 Ce-144 0.449% 1.99E-02 Pu-238 0.001% 3.52E-05 Pu-239 0.000% 1.06E-07 Pu-240 0.000% 1.11 E-05 Pu-241 0.062% 2.77E-03 Am-241 0.000% 1.65E-05 Cm-242 0.002% 8.93E-05 Cm-243 0.000% 6.78E-07 Cm-244 0.003% 1.47E-04 Page 29 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 3 Solid Waste Shipped Offsite for Burial or Disposal Estimate of major nuclide composition (by waste type)

Waste Stream : Sum of All 4 Categories Nuclide Percent Cu.

Name Abundance unes H-3 0.899% 4.35E-02 Cr-51 1.096% 5.31E-02 Mn-54 2.465% 1.19E-01 Fe-55 53.939% 2.61E+00 Fe-59 0.067% 3.27E-03 Co-57 0.067% 3.27E-03 Co-58 10.201% 4.94E-01 Co-60 4.974% 2A1E-01 Ni-63 7.252% 3.51E-01 Sr-89 0.001% 2.83E-05 Sr-90 0.064% 3.1 0E-03 Zr-95 1.664% 8.06E-02 Nb-95 2.405% 1.16E-01 Ag-11 Om 0.042% 2.05E-03 Sn-113 0.096% 4.65E-03 Sb-125 0.540% 2.61E-02 1-131 0.000% 2.75E-07 1-133 0.000% 8.69E-12 Xe-1 33 0.000% 1.05E-05 Xe-135 0.000% 2.13E-19 Cs-134 5.365% 2.60E-01 Cs-137 8.348% 4.04E-01 Ce-144 0.444% 2.15E-02 Pu-238 0.001% 3.90E-05 Pu-239 0.000% 3.51 E-07 Pu-240 0.000% 1.21E-05 Pu-241 0.063% 3.03E-03 Am-241 0.000% 1.84E-05 Cm-242 0.002% 9.62E-05 Cm-243 0.000% 2.24E-06 Cm-244 0.003% 1.61E-04 Page 30 of 38

Annual Radioactive 2003 Effluent Refease Report Waterford 3 Steam Electric Station Table 3 Table 3 Solid Waste Shipped Offslte for Burial or Disposal Solid Waste Disposition Number of Mode of Transportation Destination 3 Hittman Transport Services Duratek Bear Creek, Oak Ridge, TN 4 Hittman Transport Services RACE lic, Memphis, TN 4 R&R Transport RACE lic, Memphis, TN 1 Tag Transport Studsvik Processing Facility, Erwin, TN Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination None N/A NIA Page 31 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 4 Joint Frequency Distribution of Meteorological Data JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASC2UILL CLASS A Wind Speed (M/S) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 Total N 0 0 0 0 O 2 3 0 3 0 0 0 8 NNE 0 0 0 0 0 4 9 3 0 0 0 0 16 NE 0 0 0 0 0 7 72 17 0 0 0 0 96 ENE 0 0 0 1 0 2 3 2 0 0 0 0 8 E 0 0 0 0 0 0 0 0 0 0 0 O 0 ESE 0 0 0 0 0 0 1 0 0 0 0 0 1 SE 0 0 0 0 0 1 7 2 0 0 0 O 10 SSE 0 0 0 0 0 1 9 3 0 0 0 0 13 S 0 0 0 0 O 1 6 40 18 0 0 0 65 SSW 0 0 0 0 0 2 7 10 0 0 0 0 19 SW 0 0 0 0 0 6 34 6 0 0 0 0 46 WSW 0 0 0 0 0 4 7 0 0 0 0 0 11 W 0 0 0 0 0 1 6 0 0 0 0 0 7 WNW 0 0 0 0 0 1 0 0 0 0 0 0 1 NW 0 0 0 0 0 0 4 2 1 0 0 0 7 NNW 0 0 0 0 0 2 8 4 1 0 0 0 15 Total 0 0 0 1 0 34 176 89 23 0 0 0 323 Number of calms for A Stability class: 0 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASQUILL CLASS B Wind Speed (MIS) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 Total N 0 0 0 0 0 8 6 0 2 0 0 0 16 NNE 0 0 0 0 0 12 11 1 0 0 0 0 24 NE 0 0 0 1 0 25 57 7 0 0 0 0 90 ENE 0 0 0 0 0 3 5 0 0 0 0 0 8 E 0 0 0 0 0 0 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 3 0 0 0 0 3 SE 0 0 0 0 0 1 14 5 0 0 0 0 20 SSE 0 0 0 0 0 ' 6 14 7 1 0 0 0 28 S 0 0 0 0 0 3 11 1S 5 0 0 0 37 SSW 0 0 0 0 0 5 17 6 0 0 0 0 28 SW 0 0 0 0 2 8 16 4 0 0 0 0 30 WSW 0 0 0 0 0 10 8 0 0 0 0 0 18 W 0 0 0 1 0 4 6 1 0 0 0 0 12 WNW 0 0 0 0 0 5 9 3 0 0 0 0 17 NW 0 0 0 0 1 2 3 0 1 0 0 0 7 NNW 0 0 0 0 1 5 13 7 1 0 0 0 27 Total 0 0 0 2 4 97 190 62 10 0 0 0 365 Number of calms for B stability class: 0 Page 32 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 4 Joint Frequency Distribution of Meteorological Data JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASQUILL CLASS C Wind Speed (M/S) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 Total N 0 0 0 2 6 14 12 1 2 0 0 0 37 NNE 0 0 0 1 0 22 8 1 0 0 0 0 32 NE 0 0 0 0 2 29 71 12 0 0 0 0 114 ENE 0 0 0 0 0 2 6 3 0 0 0 0 11 E 0 0 0 0 0 2 0 1 0 0 0 0 3 ESE 0 0 0 1 2 2 4 0 0 0 0 0 9 SE 0 0 0 1 1 2 9 1 0 0 0 0 14 SSE 0 0 0 0 2 5 20 12 0 0 0 0 39 S 0 0 0 0 1 7 21 7 10 0 0 0 46 SSW 0 0 0 1 3 8 14 5 0 0 0 0 31 SW 0 0 0 0 2 14 21 7 0 0 0 0 144 WSW 0 0 0 2 2 17 13 1 0 0 0 0 35 W 0 0 0 0 0 14 8 4 0 0 0 0 26 WNW 0 0 0 0 0 2 7 3 0 0 0 0 12 NW 0 0 0 0 1 4 7 5 1 0 0 0 18 NNW 0 0 0 0 0 8 12 11 5 0 0 0 36 Total 0 0 0 8 22 152 233 74 18 0 0 0 507 Number of calms for C Stability class: 0 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASQUILL CLASS D Wind Speed (M/S) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 Total N 0 0 1 10 29 80 106 43 9 0 0 0 278 NNE 0 0 2 11 23 93 129 24 0 0 0 0 282 NE 0 1 0 7 20 117 193 43 0 0 0 0 381 ENE 0 0 2 4 8 21 55 14 4 0 0 0 108 E 0 0 0 7 7 7 19 0 1 0 0 0 41 ESE 0 1 0 1 6 9 41 16 1 0 0 0 75 SE 0 0 2 3 5 19 81 28 1 0 0 0 139 SSE 0 0 0 8 12 53 100 31 2 0 0 0 206 S 0 0 0 4 12 49 97 55 13 0 0 0 230 SSW 0 0 0 7 12 46 42 19 4 0 0 0 130 SW 0 0 0 9 17 36 50 4 0 0 0 0 116 WSW 0 0 0 12 19 52 36 14 2 0 0 0 135 W 0 0 1 12 21 49 29 10 0 0 0 0 122 WNW 0 0 1 3 15 34 33 1 0 0 0 0 87 NW 0 0 1 4 11 21 48 15 2 0 0 0 102 NNW 0 1 0 2 15 40 104 84 23 0 0 0 269 Total 0 3 10 104 232 726 1163 401 62 0 0 0 2701 Page 33 of 38

Annual Radioactive 2003 Effluent Release Renort Waterford 3 Steam Electric Station Table 4 Joint Frequency Distribution of Meteorological Data Number of calms for D Stability class: 0 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASQUILL CLASS E Wind Speed (M/S) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1- 18.0 >18.0 Total N 0 1 7 16 23 109 81 3 0 0 0 0 240 NNE 0 0 4 22 34 93 82 a 0 0 0 0 243 NE 0 1 3 16 22 85 150 20 0 0 0 0 297 ENE 0 1 2 14 11 25 66 13 0 0 0 0 132 E 1 0 2 8 13 26 31 8 0 0 0 0 89 ESE 0 1 4 12 14 27 82 9 0 0 0 0 149 SE 0 2 5 5 8 76 95 6 0 0 0 0 197 SSE 1 0 7 13 46 156 77 11 0 0 0 0 311 S 2 3 9 40 59 85 63 7 0 0 0 0 268 SSW 0 6 12 42 38 44 31 3 0 0 0 0 176 SW 0 5 8 36 37 60 25 2 0 0 0 0 173 WSW 1 4 11 43 41 34 12 0 0 0 0 0 146 W 2 8 14 24 11 9 17 0 0 0 0 0 85 WNW 4 2 6 23 17 15 8 1 0 0 0 0 76 NW 1 2 4 18 10 29 21 1 0 0 0 0 86 NNW 1 3 2 18 23 70 56 3 0 0 0 0 176 Total 13 39 100 350 407 943 897 95 0 0 0 0 2844 Number of calms for E Stability class: 0 JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASQUILL CLASS F Wind Speed (M/S) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 Total N 0 1 3 13 16 15 1 0 0 0 0 0 49 NNE 0 0 2 12 11 26 2 0 0 0 0 0 53 NE 0 1 6 9 11 22 12 0 0 0 0 0 61 ENE 0 4 2 3 2 10 3 0 0 0 0 0 24 E 0 2 1 6 2 2 3 1 0 0 0 0 17 ESE 0 2 0 2 3 2 5 0 0 0 0 0 14 SE 0 0 3 4 2 16 9 0 0 0 0 0 34 SSE 0 6 1 12 51 95 9 0 0 0 0 0 174 S 1 3 6 47 51 23 8 0 0 0 0 0 139 SSW 0 8 32 115 43 12 4 0 0 0 0 0 214 SW 2 12 32 59 20 3 2 0 0 0 0 0 130 WSW 5 18 22 74 24 7 0 0 0 0 0 0 150 W 1 19 25 37 6 0 0 0 0 0 0 0 88 WNW 0 12 14 24 15 3 0 0 0 0 0 0 68 NW 1 5 7 18 10 5 0 0 0 0 0 0 46 NNW 1 3 5 24 8 10 1 0 0 0 0 0 52 Total 11 96 161 459 275 251 59 1 0 0 0 0 1313 Number of calms for F Stability class: 0 Page 34 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 4 Joint Frequency Distribution of Meteorological Data JOINT FREQUENCY DISTRIBUTION OF WIND SPEED AND DIRECTION IN HOURS 01/01/2003 00:00:00 TO 12/31/2003 23:59:59 PASCMUILL CLASS G Wind Speed (M/S) at 10-m Level Wind Direction .22-.50 .51-.75 .76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10. 10.1-13 13.1-18.0 >18.0 Total N 2 3 2 3 1 1 0 0 0 0 0 0 12 NNE 1 4 2 2 3 0 0 0 0 0 0 0 12 NE 0 2 5 1 3 2 0 0 0 0 0 0 13 ENE 0 0 0 2 0 0 0 0 0 0 0 0 2 E 1 0 1 0 0 0 0 0 0 0 0 0 2 ESE 0 2 2 0 0 0 0 0 0 0 0 0 4 SE 2 0 1 1 1 0 4 0 0 0 0 0 9 SSE 1 3 2 10 12 28 1 0 0 0 0 0 57 S 1 3 5 28 25 4 0 0 0 0 0 0 66 SSW 5 8 13 37 28 6 0 0 0 0 0 0 97 SW 2 20 23 35 13 0 0 0 0 0 0 0 93 WSW 7 27 25 31 3 0 0 0 0 0 0 0 93 W 9 39 31 35 1 0 0 0 0 0 0 0 115 WNW 6 24 18 10 4 0 0 0 0 0 0 0 62 NW 3 13 16 6 0 0 0 0 0 0 0 0 38 NNW 2 3 8 15 2 0 0 0 0 0 0 0 30 Total 42 151 154 216 96 41 5 0 0 0 0 0 705 Number of calms for G Stability class: 1 Total valid hours for all stabilities - 8759 Total invalid hours for all stabilities - 1 Page 35 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 5A Doses Due to Gaseous Radioactive Effluents Doses due to Noble Gases (mRad or mrem)

Age Group : All Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Total-body 0.0000e+00 3.0903e-03 7.7700e-02 2.7687e-01 3.5766e-01 Skin 0.0000e+00 7.2979e-03 1.8391e-01 1.0938e+00 1.2850e+00 Air Beta 0.0000e+00 1.1037e-02 2.6267e-01 1.6144e+00 1.8881e+00 Air Gamma 0.0000e+00 3.7104e-03 9.2331e-02 3.3265e-01 4.2869e-01 Doses due to Radioiodines/Particulates/Tritium (mrem)

Age Group : Adult Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Bone 1.3027e-06 1.1916e-06 3.2798e-06 6.5092e-05 7.0867e-05 Liver 2.4325e-02 5.6388e-03 2.5371e-03 7.3936e-03 3.9895e-02 Total-body 2.4327e-02 5.6410e-03 2.5382e-03 7.3571e-03 3.9864e-02 Thyroid 2.4362e-02 5.6501e-03 2.5353e-03 3.4577e-02 6.7124e-02 Kidney 2.4325e-02 5.6389e-03 2.5359e-03 7.4510e-03 3.9951e-02 Lung 2.4325e-02 5.6388e-03 2.5355e-03 7.3085e-03 3.9808e-02 Gi-lli 2.4328e-02 5.6412e-03 2.5371e-03 7.3310e-03 3.9837e-02 Skin 1.4175e-06 1.3519e-06 2.2294e-06 5.7383e-06 1.0737e-05 Age Group : Teen Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Bone 1.3517e-06 1.2067e-06 4.2432e-06 1.0288e-04 1.0968e-04 Liver 2.7537e-02 6.3833e-03 2.8729e-03 8.4089e-03 4.5203e-02 Total-body 2.754le-02 6.3868e-03 2.8736e-03 8.3447e-03 4.5146e-02 Thyroid 2.7589e-02 6.3993e-03 2.8698e-03 4.6869e-02 8.3727e-02 Kidney 2.7538e-02 6.3834e-03 2.8709e-03 8.5010e-03 4.5293e-02 Lung 2.7537e-02 6.3833e-03 2.8702e-03 8.2735e-03 4.5064e-02 Gi-lli 2.7537e-02 6.3833e-03 2.8699e-03 8.2996e-03 4.5090e-02 Skin 1.4175e-06 1.3519e-06 2.2294e-06 5.7383e-06 1.0737e-05 Age Group : Child Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Bone 1.5214e-06 1.2591e-06 7.4446e-06 2.3372e-04 2.4395e-04 Liver 3.8112e-02 B.8342e-03 3.9764e-03 1.1676e-02 6.2599e-02 Total-body 3.8119e-02 8.8410e-03 3.9772e-03 1.1574e-02 6.2511e-02 Thyroid 3.8210e-02 8.8645e-03 3.9711e-03 8.4732e-02 1.3578e-01 Kidney 3.8112e-02 8.8342e-03 3.9728e-03 1.1813e-02 6.2732e-02 Lung 3.8111e-02 8.8341e-03 3.9717e-03 1.1448e-02 6.2365e-02 Gi-lli 3.8111e-02 8.8341e-03 3.9711e-03 1.1467e-02 6.2384e-02 Skin 1.4175e-06 1.3519e-06 2.2294e-06 5.7383e-06 1.0737e-05 Age Group : Infant Organ Qtr 1 Qtr 2 Otr 3 Qtr 4 Year Total Bone 1.7785e-06 1.3384e-06 6.9716e-06 4.2398e-04 4.3407e-04 Liver 1.7222e-02 3.9924e-03 -1.8013e-03 5.6684e-03 2.8684e-02 Total-body 1.7233e-02 4.0032e-03 1.8042e-03 5.3884e-03 2.8428e-02 Thyroid 1.7435e-02 4.0584e-03 1.7954e-03 1.6444e-01 1.8773e-01 Kidney 1.7222e-02 3.9925e-03 1.7969e-03 5.7430e-03 2.8754e-02 Lung 1.7221e-02 3.9922e-03 1.7960e-03 5.1762e-03 2.8185e-02 Gi-lli 1.7221e-02 3.9922e-03 1.7954e-03 5.1921e-03 2.8201e-02 Skin 1.4175e-06 1.3519e-06 2.2294e-06 5.7383e-06 1.0737e-05 Page 36 of 38

Annual Radioactive 2003 Effluent Release Report Waterford 3 Steam Electric Station Table 5B Doses Due to Liquid Radioactive Effluents Age Group : Adult Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Bone 1.1136e-04 6.2676e-05 2.6869e-04 1.3022e-04 5.7295e-04 Liver 1.0383e-03 1.6419e-04 l.1533e-03 3.6942e-04 2.725le-03 Total-body 9.8457e-04 1.3471e-04 1.0260e-03 3.3724e-04 2.4825e-03 Thyroid 8.3425e-04 6.3395e-05 6.9747e-04 2.0669e-04 1.8018e-03 Kidney 8.9718e-04 9.4697e-05 8.4698e-04 2.2215e-04 2.0610e-03 Lung 8.5422e-04 7.7194e-05 7.4997e-04 1.8795e-04 1.8693e-03 Gi-lli 9.9673e-04 7.3268e-O5 7.5589e-04 7.1028e-04 2.5362e-03 Page 37 of 38

ATTACHMENT 11.1 Copy of Applicable Technical Requirements Manual (TRM) Sections Page 38 of 38

-4 (DRN 02-216, Am. 51)

TABLE 3.12-2 (See note below)

+- (DRN 02-216, Am. 51)

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels AIRBORNE FOOD PARTICULATE FISH PRODUCTS WATER OR GASES (pCi/kg, MILK (pCi/kg, ANALYSIS (pC/I) (pCi/M3 ) wet) il) wet)

-* (DRN 03-255. AM 73)

H-3 20,000* l Q-0/3 4- (ORN 03-255, Am 73)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-95 400 Nb-95 400 I (DRN 03-255, Am.73)

I-131 2** 0.9 3 100 1IO03 1- (DRN 03-255. Am.73)

Cs-1 34 30 10 1,000 60 1,000 Cs-1 37 50 20 2,000 70 2,000 Ba-140 200 300 La-140 200 300

-4 (DRN 02-216, Am. 51)

NOTE: TRM Table 3.12-2 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14.

- (DRN 02-216, AmI.51)

- (DRN 03-2 AM73)

  • For drinking water samples. This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pC/I may be used. O513/o
    • If no drinking water pathway exists, a value of 20 pCiI may be used.

4-(DRN 03-2 Am 7) 3/4 12-10 AMENDMENT NO. 54,73

- (ORN 02-216, Am. 51)

TABLE 4.12-1 (See note below)

+- (DRN 02-216. Am. 51)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS

-4 (DRN 03-255, Am. 73)

LOWER LIMITS OF DETECTION (LLD)a bc e 4- (DRN 03-255, Am. 73)

AIRBORNE FOOD PARTICULATE FISH PRODUCTS SEDIMENT WATER OR GASES (pCi/kg, MILK (pCi/kg, (pCi/kg, ANALYSIS (pCUI) (pCVM 3) wet) (pCVI wet) dry Gross 4 0.01 Beta

- (DRN 03-255 An 73)

H-3 2,000O 103/03 4- (DRN 03-25a Am 73)

Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260

- (DRN 03-25 Arm 73)

Zr-95 15 103/03

- (DRN 03-25. An. 7)

Nb-95 15 1-131 0.07 1 60 Cs-134 15. 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180

- (DRN 03-25& Aam 73)

Ba-140 15 15 1l63/03 4 (DRN 03-25. Am,.73)

La-140 15 15

-1 (DRN 02-216. Am. 51)

NOTE: TRM Table 4.12-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14.

4- (ORN 02-216. Am. 51) 3/4 12-11 AMENDMENT NO. 02,64,73

-l (DRN 02-216, Am. 51)

TABLE 4.12-1 (See note below)

+- (DRN 02-216, Am. 51)

TABLE NOTATIONS

a. This list does not mean that only these nuclides are to be considered Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
c. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.

-4 (DRN 03-255 Am 73)

d. LLD for drinking water samples. If no drinking water pathway exists, a value of 15 pCiI may l 03/°3 be used.

+- (ORN 03-2 An73)

e. The LLD is defined in the ODCM.

+ (DRN 03-256, Am. 73)

f. If no drinking water pathway exists, a value of 3000 pCi/i may be used. I 05/03 v- (DRN 03-255, APA73)

-4 (DRN 02-216. Am. 51)

NOTE: TRM Table 4.12-1 is part of the Offsite Dose Calculation Manual (ODCM), reference UNT-005-014. Revision of this TRM Table requires the approval of the General Manager Plant Operations (GMPO) in accordance with Technical Specification 6.14.

1- (DRN 02-216. Anr51) 3/4 12-12 AMENDMENT NO. A 73

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