Text

1995 Annual Radioactive Effluent Release Rept for Re Ginna Nuclear Plant
	ML17264A457
Person / Time
Site:	Ginna
Issue date:	12/31/1995
From:	; ROCHESTER GAS & ELECTRIC CORP.
To:	;
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ML17264A455	List: ML17264A454; ML17264A456; ML17264A457; ML17264A458;
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	NUDOCS 9604260099
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1995 ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 9604260099 9604i9 PDR ADOCK 05000244 R

PDR

TABLE OF CONTENTS

1.0 INTRODUCTION

2.0 SUPPLEMENTAL INFORMATION 2.1 REGULATORY LIMITS 2.2 MAXIMUMPERMISSIBLE CONCENTRATIONS 2.3 RELEASE RATE LIMITS 2.4 MEASUREMENTS ANDAPPROXIMATIONSOF TOTALRADIOACTIVITY 2.5 BATCH RELEASES 2.6 ABNORMALRELEASES 3.0

SUMMARY

OF GASEOUS RADIOACTIVEEFFLUENTS 4.0

SUMMARY

OF LIQUID RADIOACTIVEEFFLUENTS 5.0 SOLID WASTE 6.0 LOWER LIMITOF DETECTION 7.0 RADIOLOGICALIMPACT 8.0 METEOROLOGICAL DATA 9.0 LAND USE CENSUS CHANGES 10.0 CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL 11.0 CHANGES TO THE PROCESS CONTROL PROGRAM 12.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases Table 1B Gaseous Effluents - Continuous and Batch Releases Table 2A Liquid Effluents - Summation of all Releases Table 2B Liquid Effluents - Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments Table 4A Radiation Dose to Nearest Individual Receptor from Gaseous Releases Table 4B Radiation Dose to Nearest Individual Receptor from Liquid Releases

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1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is for Rochester Gas and Electric Corporation R.E. Ginna plant and is submitted in accordance with the requirements ofTechnical Specification Section 6.9.1.4. The report covers the period from January 1, 1995 through December 31, 1995.

This is the first Annual Report established by Amendment 58 to R.E.

Ginna Technical Specifications.

This report includes a summary of the quantities of radioactive gaseous and liquid effluents and solid waste released from the plant presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R.E. Ginna Technical Specifications.

2.0 2.1 SUPPLEMENTAL INFORMATION Re ulato Limits The Technical Specification limits applicable to release of radioactive material in liquid and gaseous effluents are:

2.1.1 Fission and Activation Gases The instantaneous dose rate, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to a release rate which would yield < 500 mrem/yr to the total body and < 3000 mrem/yr to the skin if allowed to continue for a full year.

The air dose, as calculated in the ODCM, due to noble gases released in gaseous effluents from the site shall be limited to the following:

(i)

During any calendar quarter to < 5 mrad for gamma radiation and to <

10 mrad for beta radiation.

(ii)

During any calendar year to < 10 mrad for gamma radiation and to < 20 mrad for beta radiation.

2.1.2 Radioiodine Tritium and Particulates The instantaneous dose rate, as calculated in the ODCM, due to radioactive materials released in gaseous effluents from the site as radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days shall be limited to a release rate which would yield < 1500 mrem/yr to any organ ifallowed to continue for a full year.

The dose to an individual, as calculated in the ODCM, from radioiodine, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:

(i)

During any calendar quarter to < 7.5 mrem to any organ.

(ii)

During any calendar year to < 15 mrem to any organ.

The release of radioactive liquid effluents shall be such that the concentration in the circulating water discharge does not exceed the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20.

For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2 E-4 uCi/ml.

~

The dose or dose commitment to an individual as calculated in the ODCM from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

(i)

During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and (ii)

During any calendar year to < 3 mrem to the total body and to < 10 mrem to any organ.

2.2 Maximum Permissible Concentrations MPC 2.2.1 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary.

2.2.2 For liquid effluents, the ten times the effluent concentration values specified in 10CFR20, Appendix B to 20.1-20.602, Table II, column 2, 1-1-93, are used to calculate release rates and permissible concentrations at the unrestricted area boundary. Avalue of 2E-.04 uCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.

2.3 Release Rate Limits The release rate limits for fission and activation gases from the R.E. Ginna plant are not based on the average energy of the radionuclide mixture in gaseous effluents; therefore, this value is not applicable.

However, the average beta/gamma energy of the radionuclide mixture was 0.249 Mev.

2.4 Measurements and A roximations of Total Radioactivit Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concentration of gaseous and liquid effluents.

Composite samples were analyzed for Sr-89, Sr-90 and Fe-55 by a contract laboratory.

Tritium and alpha analysis were done using liquid scintillation and gas flow proportional counting respectively.

The total radioactivity in effluent releases was determined from the measured concentration of each radionuclide present and the total volume of effluents released.

2.5 Batch Releases 2.5.1 Liciuid 1.

Number of batch releases:

2. Total time period for batch releases:

3.

Maximum time period for a batch release:

4. Average time period for batch releases:

5.

Minimum time period for a batch release:

6. Average stream flow (LPM) during periods of release effluent into a flowing stream:

2.97 E+02 5.59 E+04 min 9.30 E+03 min 1.88 E+02 min 1.5 E+01 min 1.58 E+02 2.5.2 Gas'eous 1.

Number of batch releases:

2. Total time period for batch releases:

3.

Maximum time period for a batch release:

4. Average time period for batch releases:

5.

Minimum time period for a batch release:

2.0 E+01 4.93 E+03 min 4.79 E+02 min 2.46 E+02 min 3.8 E+01 min

26 Abnormal Releases There were no abnormal releases of liquid or gaseous effluents during the reporting period.

3.0

SUMMARY

OF GASEOUS RADIOACTIVEEFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and 1B. All releases were considered to be ground level releases.

4.0

SUMMARY

OF LIQUID RADIOACTIVEEFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.

5.0 SOLID WASTES The quantities of radioactive material released in shipments of solid waste transported from the site during the reporting period are summarized in table 3.

Principal nuclides were determined by gamma spectroscopy and non-gamma emitters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste type.

The majority of Dry Active Waste is processed utilizing an off-site processor who reduces the volume and then sends the waste for burial.

6.0 LOWER LIMITOF DETECTION NOT MET There were no liquid or gaseous releases for which the LLD for specified gamma emitting nuclides was not met.

7.0 RADIOLOGICALIMPACT An assessment of doses to the maximally exposed individual from gaseous and liquid effluents was performed for locations representing the maximum dose.

In all cases, doses were well below Technical Specification limits.

Doses were assessed based upon actual meteorological conditions considering the noble gas exposure, inhalation, ground plane and ingestion pathways.

The ingestion pathways considered were the fruit, vegetable, fish, drinking water, goat's milk, cow's milk and meat pathway.

The results of this assessment are presented in Tables 5A and 5B.

8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1995 is not included with this report, but can be made available at the RG8E Ginna Plant as allowed by Technical Specifications.

9.0 LAND USE CHANGES There were no changes in critical receptor location for dose calculations during the reporting period. There were no large changes in land use within 5 miles of the plant, other than several new homes being built.

10.0 CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL (ODCM)

The ODCM was totally rewritten for the implementation of Amendment 61 to R.E. Ginna Technical Specifications.

The change did not become effective until 2/24/96; however, the new ODCM is attached to this report.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

The change to the PCP for the implementation of Amendment 61 was the removal of the reference to R.E. Ginna Technical Specifications.

12.0 MAJOR CHANGES TO RADWASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.

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HESTER GAS ELECTRIC CORPORAT Table 1A EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES

- JANUARY-JUNE 1995 A. Fission 8 activation ases Unit Quarter 1st Quarter 2nd Est. Total Error, %

1. Total release Ci 1.48E+01 9.00E+00 9.50E+00