ML17265A648

1998 Annual Effluent Operating Rept for Re Ginna Npp.

ML17265A648
Person / Time
Site:	Ginna
Issue date:	12/31/1998
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17265A647	List: ML17265A646 ML17265A648 ML17265A651
References
NUDOCS 9905200133
Download: ML17265A648 (40)

Text

1998 Annual Effluent Operating Report R.E. Ginna Nuclear Plant Rochester Gas and Electric 9905200i33 9905i2 PDR ADGCK 05000244 Docket No. 50-244

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1998 ANNUALRADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244

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TABLE OF CONTENTS 1.0 Introduction 2.0 Supplemental Information 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Release Rate Limits 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0 Summary of Gaseous Radioactive Effluents 4.0 Summary of Liquid Radioactive Effluents 6.0 Solid Waste 6.0 Lower Limit of Detection 7.0 Radiological Impact 8.0 Meteorological Data 9.0 Land Use Census Changes 10.0 Changes to the Offsite Dose Calculation Manual 11.0 Changes to the Process Control Program 12.0 Major Changes to Radwaste Treatment Systems 13.0 Operational Discrepancies

LIST OF TABLES Table 1A Gaseous Effluents - Summation of all Releases Table 2A Liquid Effluents - Summation of all Releases Table 1B Gaseous Effluents - Continuous and Batch 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 Table 5 52 Week Totals for Noble Gases and I-131

1.0 INTRODUCTION

This Annual Radioactive Effluent Release Report is for the Rochester Gas and Electric Corporation R.E. Ginna Nuclear Power Plant and is submitted in accordance with the requirements of Technical Specification Section 5.6.3. The report covers the period from January 1, 1998 through December 31, 1998.

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.

1 All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R.E. Ginna Technical Specifications as defined in the Offsite Dose Calculation Manual (ODCM).

2.0 SUPPLEMENTAL INFORMATION 2.1 Re ulato Limits The ODCM limits applicable to the 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 if allowed 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.

2.1.3 Li uid Effluents 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 pCi/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 mrerri 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 effluerits, ten times'the effluent concentration values specified in 10CFR20, Appendix B, Table II, column 2, are used to calculate release rates

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and permissible concentrations at the unrestricted area boundary as permitted by Technical Specification 5.5.4.b. A value of 2E-04 pCi/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 1998 beta/gamma energy of the radionuclide mixture was 0.250 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 lab-oratory. Tritium and alpha analysis were performed 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 Liquid

1. Number of batch releases: 1.82 E+02

2. Total time period for batch releases: 4.01 E+04 min

3. Maximum time period for a batch release: 7.80 E+02 min

4. Average time period for batch releases: 2.20 E+02 min

5. Minimum time period for a batch release: 3.0 E+00 min

6. Average blowdown (LPM) during periods of eNuent release into the discharge canal. None 2.5.2 Gaseous

1. Number of batch releases: 2.0 E+01

2. Total time period for batch releases: 4.48 E+03 min

3. Maximum time period for a batch release: 4.53 E+02 min

4. Average time period for batch releases: 2.24 E+02 min

5. Minimum time period for a batch release: 1.22 E+01 min

2.6 Abnormal Releases There were no abnormal releases in 1998.

3.0

SUMMARY

OF GASEOUS RADIOACTIVEEFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and 1B. Plant vent and Containment Vent releases are modeled as mixed mode and Air Ejector is modeled as ground level release.

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 WASTE 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 There were no instances where the Lower Limit of Detection (LLD) 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 as defined in the ODCM.

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 4A and 4B.

8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1998 is not included with this report, but can be made available at the RGB E Ginna Plant.

9.0 LAND USE CENSUS 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. Additional new homes were built.

10.0 CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL There were minor changes to the Offsite Dose Calculation Manual (ODCM) in 1998.

These included the following changes as reported in Ginna procedure change notification (PCN).

The PCN no. 98-6300 documented the following change; The restrictions on a Gas Decay tank were clarified when process radiation monitor R-14 was inoperable and what alternatives were available.

I The PCN no. 98-6310 documented the following change; A clarification was made regarding the component cooling system.

These changes were reviewed as part of a 10 CFR 50.59 analysis and found not to affect nuclear safety, and did not involve an unreviewed safety question.

11.0 CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Process Control Program during the reporting period.

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

13.0 OPERATIONAL DISCREPANCIES Process Monitor R-14A was out of service in excess of 7 days. The unit was placed out of service on 7/1 3/98 at 0530 for preventative maintenance and calibrations. Due to other maintenance considerations, the repair of the process monitor exceeded the 7 day window. The unit was returned to service on 8/05/98. During that time, other systems were available to accurately monitor the noble gas, particulate and iodine releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY - JUNE 1998 Unit Quarter Quarter Est. Total A. Fission & activation ases 1st 2nd Error %

1. Total release Ci 8.50E+00 6.40E+00 6.70E+00

2. Avera e release rate for eriod uCi/sec 1.09E+00 8.14E-01

3. Percent of technical s ecification limit 1.74E-04 1.29E-04 B. Iodines

1. Total iodine-1 31 Ci 1.11E-05 1.11E-05 2.80E+01

2. Avera e release rate for eriod uCi/sec 1.43E-06 1.41E-06

3. Percent of technical s ecification limit 3.14E-03 3.10E-03 C. Particulates

1. Particulates with half-lives > 8da s Ci 3.00E+01

2. Avera e release rate for eriod uCi/sec

3. Percent of technical s ecification limit

4. Gross al ha radioactivit Ci 2.97E-07 8.28E-08 A

D. Tritium

1. Total release Ci 6.31E+00 6.73E+00 8.30E+00

2. Avera e release rate for eriod uCi/sec 8.11E-01 8.56E-01

3. Percent of technical s ecification limit 9.55E-05 1.01E-04 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES-JULY - DECEMBER 1998 Unit Quarter Quarter Est. Total A. Fission & activation ases 3rd 4th Error %

1. Total release Ci 7.04E+00 6.29E+00 6.70E+00

2. Avera e release rate for eriod uCi/sec 8.85E-01 7.92E-01

3. Percent of technical specification limit 1.41E-04 1.26E-04 B. Iodines

1. Total iodine-131 Ci 1.25E-05 1.13E-05 9.90E+00

2. Average release rate for eriod uCi/sec 1.57E-06 1.42E-06

3. Percent of technical specification limit 3.46E-03 3.11E-03 C. Particulates

1. Particulates with half-lives > 8da s Ci 9.26E-07 1.83E+01

2. Avera e release rate for eriod uCi/sec 1.16E-07

3. Percent of technical s ecification limit 8.76E-06

4. Gross alpha radioactivit Ci D. Tritium

1. Total release Ci 9.13E+00 7.27E+00 8.30E+00

2. Avera e release rate for eriod uCi/sec 1.15E+00 9.15E-01

3. Percent of technical s ecification limit 1.35E-04 1.08E-04 Note: Isotope for which no value is given were not identified in applicable releases.

i1 ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID'EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY - JUNE 1998 Unit Quarter Quarter Est. Total A. Fission and activation roducts 1st 2nd Error, %

1. Total release (not including tdtium, ases, al ha Ci 2.22E-04 4.86E-04 5.00E+00

2. Average diluted concentratiori durin eriod uCi/ml 1.43E-12 2.88E-12

3. Percent of a plicable limit , 2.33E-06 3.70E-06 B. Tritium

1. Total release Ci 1.11E+01 2.61E+01 '.40E+00

2. Average diluted concentration durin eriod'.

uCi/ml 7.17E-08 1.55E-07 Percent of a plicable limit 2.39E-03 5.16E-03 C. Dissolved and entrained gases

1. Total release Ci

2. Average diluted concentration durin eriod uCi/ml

3. Percent of a licable limit D. Gross al ha radioactivit

1. Total release Ci N/A N/A E. Vol. of waste released rior to dilution) Liters 2.77E+07 2.05E+07 F. Vol. of dilution water used durin eriod Liters 1.54E+11 1.69E+11 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JULY - DECEMBER 1998 Unit Quarter Quarter Est. Total A. Fission and activation roducts 3rd 4th Error %

1. Total release (not including tritium, ases, al ha) Ci 1.36E-03 2.18E-03 5.00E+00

2. Average diluted concentration durin eriod uCi/ml 7.99E-12 1.31E-11

3. Percent of a plicable limit 8.74E-06 1.37E-05 B. Tritium

1. Total release Ci 3.48E+01 6.02E+01 1.40E+00

2. Average diluted concentration durin eriod uCi/ml 2.04E-07 '.62E-07

3. Percent of a licable limit 6.80E-03 1.21E-02 C. Dissolved and entrained ases

1. Total release Ci 2.68E-04 9.60E+00

2. Average diluted concentration durin eriod uCi/ml 1.61E-12

3. Percent of a plicable limit 8.06E-07 D. Gross al ha radioactivit

1. Total release Ci N/A N/A E. Vol. of waste released prior to dilution Liters 4.02E+07 2.44E+07 F. Vol. of dilution water used durin period Liters 1.71E+11 1.66E+11 Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT Gaseous Effluents-Continuous and Batch Releases Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd

1. Fission gases argon-41 Ci 3.68E-02 4.34E-02 k ton-85 Ci 2.43E+00 2.36E-01 k ton-85m Ci k ton-87 Ci k ton-88 Ci xenon-1 31m Ci 1.04E-02 xenon-133 Ci 3.98E+00 4.03E+00 5.12E-02 7.23E-02 xenon-133m Ci 6.87E-01 6.65E-01 5.45E-04 xenon-135 Ci 1.31E+00 1.35E+00 3.16E-04 8.00E-05 xenon-1 35m Ci xenon-138 Ci others (s ecify Ci Ci Ci Ci Total for period Ci 5.98E+00 6.05E+00 2.53E+00 3.53E-01

2. Io dines iodine-1 31 Ci 1.11E-05 1.11E-05 iodine-1 33 Ci 1.25E-05 1.26E-05 iodine-1 35 Ci Total for eriod Ci 2.36E-05 2.37E-05

3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-1 37 Ci Nb-95 Ci cobalt-58 Ci cobalt-60 Ci Total for eriod Ci unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT Gaseous Effluents-Continuous and Batch Releases Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter Quarter Quarter 3rd 4th 4th

1. Fission gases-ar on-41 Ci 4.09E-02 4.12E-02 k ton-85 Ci 7.52E-02 1.00E-02 k ton-85m Ci k ton-87 Ci k ton-88 Ci xenon-131m Ci 1.10E-03 xenon-133 Ci 4.55E+00 4.08E+00 1.07E-01 1.22E-01 xenon-133m Ci 6.31E-04 3.64E-04 xenon-135 Ci 2.26E+00 2.04E+00 5.46E-04 2.52E-04 xenon-135m Ci xenon-138 Ci others specif Ci Ci Ci Ci Total for eriod Ci 6.81E+00 6.12E+00 2.24E-01 1.75E-01

2. Io dines iodine-1 31 Ci 1.25E-05 1.12E-05 6.15E-09 4.55E-08 iodine-133 Ci 4.31E-03 1.28E-05 iodine-135 Ci Total for eriod Ci 4.32E-03 2.40E-05 6.15E-09 4.55E-08

3. Particulates strontium-89. Ci strontium-90 Ci cesium-1 34 Ci cesium-1 37 Ci 9.26E-07 Nb-95 Ci cobalt-58 Ci cobalt-60 Ci Total for eriod Ci 9.26E-07 unidentified Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd chromium-51 Ci manganese-54 Ci iron-55 Ci iron-59 Ci cobalt-58 Ci 6.70E-05 5.88E-05 cobalt-60 Ci 6.02E-05 1.10E-05 zinc-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci 3.98E-06 mol bdenum-99 Ci silver-1 10m Ci 1.76E-05. 8.38E-06 antimon -122 Ci antimon -124 Ci antimon -125 Ci 6.37E-OS 3.81E-04 iodine-131 Ci iodine-1 33 Ci iodine-1 35 Ci cesium-134 Ci cesium-1 36 Ci cesium-1 37 Ci 6.59E-06 2.61E-06 2.59E-06 2.44E-05 barium/lanthanum-140 Ci cerium-141 Ci Te-123m Ci Ru-103 Ci Total for eriod above Ci 6.59E-06 2.61E-06 '.15E-04 4.83E-04 unidentified Ci xenon-133 Ci xenon-135 Ci Note: Isotope for which no value is given were not identified in applicable releases.

ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter 'uarter Quarter 4th 4th chromium-51 Ci man anese-54 Ci iron-55 Ci 9.66E-06 iron-59 Ci cobalt-58 Ci 1.48E-05 2.79E-06 1.57E-05 cobalt-60 Ci 8.07E-06 4.96E-05 1.10E-05 zinc-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci mol bdenum-99 Ci silver-110m Ci antimon -122 Ci antimon -124 Ci antimon -125 Ci 4.60E-04 8.00E-04 2.13E-03 iodine-1 31 Ci iodine-133 Ci iodine-1 35 Ci cesium-134 Ci cesium-136 Ci cesium-137 Ci 7.49E-06 4.87E-06 1.20E-05 1.71E-'05 barium/lanthanum-140 Ci cerium-1 41 Ci Ru-106 Ci Ru-103 Ci Total for eriod above Ci 4.91E-04 4.87E-06 8.74E-04 2.18E-03 unidentified Ci xenon-133 Ci 2.61E-04 xenon-135 Ci 6.84E-06 Note: Isotope for which no value is given were not identified in applicable releases.

Table 3 EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1998- December 31, 1998 I A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL - (Not irradiated fuel)

1. Type of waste Unit 12 month period Est. total Error%

a. Spent resins, filter sludges, nl 3.41 evaporator bottoms, etc. Ci 197

b. Dry compressible waste, m' 274.4, 7.0 E+00 contaminated equip, etc. Ci 4.32 7.0 E+00

c. Irradiated components, control m'i N/A N/A rods, etc. N/A N/A

d. Othei': Metal Spent Fuel Pool Racks nl 71.93 1.0E+01'1.0E+01 Ci 0.62 2.Estimate of major nuclide composition (by type of waste)

'a d.

Co-58 23.52 Co-58 36.18 Nb-95 . 23.88 Ni-63 22.46 Fe-55 23.71 Ce-144 17.37 Cs-134 18.24 Cr-51 14.12 Ru-106 13.96 Cs-137 15.99 "Co-60 7.41 Fe-55 7.88 Co-60 9.08 Ni-63 6.29 Co-60 7.80 Fe-55 8.66 1-131 3.09 Ni-63 7.06 Mn-54 1.21 Nb-95 2.11 Zr-95 6.20 Zr-95 '.52 Pu-241 4.71 Mn-54 1.26 Co-58 3.01 Cs-137 .87 Ru-103 2.53 Sb-125 .61 Sr-89 .97 Ce-141 .87 Sr-90 .74 Sb-125 .70 Total 99.16% Total 97.17% Total 97.68%

3. Solid Waste Disposition Nuriiber of:Shipme'nts. Ilode of Transportation ', ',

'Destination 10 Sole use truck Oak Ridge, TN Sole use truck Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments:. Mode of Transportation, '=

, Destination None 15

Table 4A Radiation Dose to Nearest Individual Individual Receptor From Gaseous Releases

- First Quarter 1998 (Units In rem)

T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN N 1.1E-08 1.1E-08 6.9E-09 1.1E-08 1.1E-08 6.9E-08 1.0E-08 1.0E-08 6.9E-08 6.9E-08 7.0E-09 6.9E-08 NNE 1.2E-08 1.2E-08 6.7E-09 1.2E-08 1.2E-08 6.7E-09 1.1E-08 1.1E-08 6.7E-08 7.2E-09 7.4E-09 6.7E-09 NE 1.1E-08 1.1E-08 6.9E-09 1.1E-08 1.1E-08 6.9E-09 6.7E-09 1.0E-08 6.9E-09 6.7E-09 6.9E-09 6.9E-09 ENE 1.0E-08 1.0E-08 1.3E-08 1.0E-08 1.0E-08 1.3E-08 9.3E-09 9.6E-09 1.3E-08 6.4E-09 6.6E-09 1.3E-08 E 9.4E-08 9.5E-08 2.9E-07 9.4E-08 9.6E-08 2.9E-07 8.7E-08 8.9E-08 2;9E-07 6.3E-08 6.4E-08 2.9E-07 ESE 1.1E-07 1.1E-07 1.0E-07 1.1E-07 1.1E-07 1.0E-07 1.0E-07 1.0E-07 1.0E-07 7.2E-08 7.4E-08 1.0E-07 SE 5.8E-08 5.9E-08 . 6.2E-08 5.8E-08 5.9E-08 6.2E-08 5.4E-08 5.5E-08 6.2E-08 3.9E-08 4.0E-08 6.2E-08 SSE 5.5E-08 5.5E-08 5.7E-08 5.5E-08 5.6E-08 5.7E-08 5.0E-08 5.2E-08 5.7E-08 3.6E-08 3.7E-08 5.7E-08 S 4.4E-08 4.4E-08 4.0E-08 4.4E-08 4.5E-08 4.0E-08 4.1E-08 4.2E-08 4.0E-08 3.0E-08 3.1E-08 4.0E-08 SSW 8.9E-08 9.0E-08 6.1E-08 9.0E-08 9.0E-08 6.1E-08 8.2E-08 8.4E-08 6.1E-08 5.7E-08 5.8E-08 6.1E-08 SW 2.1E-07 2.1E-07 1.5E-07 2.1E-07 2.1E-07 1.5E-07 1.9E-07 1.9E-07 1.5E-07 1.3E-07 1.4E-07 1.5E-07 WSW 1.0E-07 1.0E-07 1.1E-07 1.0E-07 1.0E-07 1.1E-07 9.2E-08 9.4E-08 1.1E-07 6.5E-08 6.6E-08 1.1E-07 W 6.4E-08 6.5E-08 4.6E-08 6.4E-08 6.5E-08 4.6E-08 5.9E-08 6.0E-08 4.6E-08 4.1E-08 4.2E-08 4.6E-08 WNW 5.1E-09 5.2E-09 4.1E-09 5.2E-09 5.3E-09 4.1E-09 4.8E-08 4.9E-08 4.1E-09 3.4E-09 3.5E-09 4.1E-09 NW 6.9E-09 7.0E-09 3.8E-09 6.9E-09 7.0E-09 3.8E-09 6.3E-09 6.4E-09 3.8E-09 4.2E-09 4.3E-09 3.8E-09 NNW 8.9E-09 9.0E-09 5.4E-09 8.9E-09 9.1E-09 5.4E-09 8.1E-09 8.3E-09 5.4E-09 5.5E-09 5.7E-09 5.4E-09 2.1E-07 2.1E-07 2.9E-07 2.1E-07 2.1E-07 2.9E-07 1.9E-07 1.9E-07 2.9E-07 1.3E-07 1.4E-07 2.9E-07 Page 16

Gas Rel 2nd Qt Table 4A Radiation Dose to Nearest Individual Individual Receptor From Gaseous Releases Second Quarter 1998 (Units In rem)

T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN 9.5E-09 9.6E-09 5.2E-09 9.5E-09 9.7E-09 5.2E-09 8.7E-09 8.8E-09 5.2E-09 5.8E-09 6.0E-09 5.2E-09 NNE 1.0E-08 1.0E-08 6.0E-09 1.0E-08 1.1E-08 6.0E-09 9.5E-09 9.7E-09 6.0E-09 6.4E-09 6.4E-09 6.0E-09 NE 1.0E-08 1.0E-08 6.1E-09 1.0E-08 1.0E-08 6.1E-09 9.2E-09 9.5E-09 6.1E-09 6.3E-09 6.5E-09 6.1E-09 ENE 8.8E-09 8.9E-09 4.9E-09 8.8E-09 9.0E-09 4.9E-09 8.0E-09 8.2E-09 4.9E-09 5.4E-09 5.6E-09 4.9E-09 2.3E-07 2.8E-07 9.5E-08 2.5E-07 2.9E-07 9.5E-08 3.0E-07 3.8E-07 9.5E-08 1.4E-07 2.2E-07 9.5E-08 ESE 1.6E-07 1.9E-07 7.0E-08 1.7E-07 1.7E-07 7.0E-08 2.0E-07 2.6E-07 7.0E-08 1.1E-07 1.8E-07 7.0E-08 SE 5.2E-08 5.8E-08 2.1E-08 5.7E-08 6.5E-08 2.1E-08 7.5E-08 8.8E-08 2.1E-08 7.4E-08 9.6E-08 2.1E-08 SSE 3.1E-08 3.3E-08 1.4E-08 3.4E-08 3.7E-08 4.1E-07 4.3E-08 4.9E-08 1.4E-08 4.6E-08 5.6E-08 1.4E-08 S 4.0E-08 4.8E-08 2.0E-08 4.3E-08 5.2E-08 2.0E-08 5.2E-08 6.7E-08 2.0E-08 4.4E-08 6.2E-08 2.0E-08 SSW 6.6E-08 6.9E-08 3.2E-08 6.9E-08 7.4E-08 3.2E-08 7.7E-08 8.5E-08 3.2E-08 7.0E-08 8.5E-08 3.2E-08 SW - 74E 08 7.7E-08 2.0E-08 8.3E-08 8.7E-08 2.0E-08 1.1E-07 1.2E-07 2.0E-08 1.3E-07 1.5E-07 2.0E-08 WSW 1.1E-07 1.2E-07 2.1E-08 1.3E-07 1.4E-07 2.1E-08 1.8E-07 2.0E-07 2.1E-08 1.9E-07 2.4E-07 2.1E-08 W 2.8E-08 2.8E-08 5.1E-09 3.1E-08 3.2E-08 5.1E-09 4.4E-08 4.6E-08 5.1E-09 2.8E-08 3.1E-08 5.1E-09 WNW 6.2E-09 7.2E-09 2.6E-09 6.6E-09 7.5E-09 2.6E-09 8.1E-09 9.4E-09 2.6E-09 2.2E-09 2.3E-09 2.6E-09 NW 6.1E-09 6.2E-09 3.6E-09 6.1E-09 6.2E-09 3.6E-09 5.6E-09 5.7E-09 3.6E-09 3.8E-09 3.9E-09 3.6E-09 NNW 9.5E-09 9.6E-09 5.3E-09 9.5E-09 9.7E-09 5.3E-09 8.7E-09 8.9E-09 5.3E-09 5.8E-09 6.0E-09 5.3E-09 2.3E-07 2.8E-07 9.5E-08 2.5E-07 2.9E-07 4.1E-07 3.0E-07 3.8E-07 9.5E-08 1.9E-07 2.4E-07 9.5E-08 Page 17

Gas Rel 3rd Qt Table 4A Radiation Dose to Nearest Individual Individual Receptor-From Gaseous Releases Third Quarter 1998 (Units In rem)

T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN 1.9E-08 1.9E-08 6.4E-09 1.9E-08 1.9E-08 6.4E-09 1.7E-08 1.7E-08 6.4E-09 1.1E-08 1.1E-08 6.4E-09 NNE 3.60E-08 3.6E-08 1.2E-08 3.6E-08 3.6E-08 1.2E-08 3.2E-08 3.3E-08 1.2E-08 2;1E-08 2.1E-08 1.2E-08 NE 3.3E-08 3.3E-08 1.2E-08 3.3E-08 3.4E-08 1.2E-08 3.0E-08 3.0E-08 1.2E-08 1.9E-08 1.9E-08 1.2E-08 ENE 1.7E-08 1.7E-08 6.5E-09 1.7E-08 1.7E-08 6.5E-08 1.6E-08 1.6E-08 6.5E-09 9.9E-09 1.0E-08 6.5E-09 1.6E-07 1.8E-07 3.1E-08 1.8E-07 2.0E-07 3.1E-08 2.4E-07 2.7E-07 3.1E-08 1.3E-07 1.6E-07 3.1E-08 ESE 3.8E-07 4.3E-07 9.2E-08 4.2E-07 4.7E-07 9.2E-08 5.3E-07 6.2E-07 9.2E-08 2.3E-07 3.4E-07 9.2E-08 SE 2.8E-07 2.8E-07 7.4E-08 3.0E-07 3.3E-07 7.4E-08 3.7E-07 4.2E-07 7.4E-08 1.8E-07 2.5E-07 7.4E-08 SSE 9.1E-08 9.9E-08 1.4E-08 1.0E-07 1.1E-07 1.4E-08 1.4E-07 1.6E-07 1.4E-08 1.1E-07 1.5E-07 1.4E-08 2.1E-07 2.5E-07 5.2E-08 2.4E-07 2.7E-07 5.2E-08 3.1E-07 3.8E-07 5.2E-08 1.4E-07 2.3E-08 5.2E-08 SSW 2.6E-07 2.8E-07 4.8E-08 2.8E-07 3.1E-07 4.8E-08 3.7E-07 4.2E-07 4.8E-08 1.5E-07 2.0E-07 4.8E-08 SW 2.9E-07 3.1E-07 4.6E-08 3.2E-07 3.5E-07 4.6E-08 4.3E-07 4.8E-07 4.6E-08 2.4E-07 3.1E-07 4.6E-08 WSW 1.9E-07 2.0E-07 1.9E-08 2.2E-07 2.2E-07 1.9E-08 3.1E-07 3.2E-07 1.9E-08 1.9E-07 2.1E-07 1.9E-08 W 1.5E-07 1.5E-07 8.6E-09 1.8E-07 1.8E-07 8.6E-09 2.6E-07 2.6E-07 8.6E-09 1.3E-07 1.3E-07 8.6E-09 WNW 3.0E-09 3.2E-09 4.8E-10 3.3E-09 3.4E-09 4.8E-10 4.3E-09 4.6E-09 4.8E-1 0 7.0E-10 7.1E-10 4.8E-10 NW 7.2E-09 7.2E-09 2.5E-09 7.2E-09 7.3E-09 2.5E-09 6.5E-09 6.6E-09 2.5E-09 4.1E-09 4.2E-09 2.5E-09 NNW 7.6E-09 7.7E-09 2.7E-09 7.7E-09 7.8E-09 2.7E-09 6.9E-09 7.0E-09 2:7E-09 4.4E-09 4.5E-09 2.7E-09 3.8E-07 4.3E-07 9.2E-08 4.2E-07 4.7E-07 9.2E-08 5.3E-07 6.2E-07 9.2E-08 2.4E-07 3.4E-07 9.2E-08

Gas Rel 4th Qt Table 4A Radiation Dose to Nearest Individual Individual Receptor From Gaseous Releases Fourth Quarter 1998 (Units In rem) gfLD)'P. xy~~4 Mc T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN N 1.6E-08 1.6E-08 8.4E-09 1.6E-08 1.6E-08 8.4E-09 1.4E-08 1.5E-08 8.4E-09 9.7E-09 9.9E-09 8.4E-09 NNE 1.6E-08 1.6E-08 8.6E-09 1.6E-08 1.6E-08 8.6E-09 1.4E-08 1.5E-08 8.6E-09 9.6E-09 9.9E-09 8.6E-09 NE 1.7E-08 1.7E-08 9.1E-09 1.7E-08 1.7E-08 9.1E-09 1.6E-08 1.6E-08 9.1E-09 1.0E-08 1.1E-08 9.1E-09 ENE- 2.0E-08 2.0E-08 1.1E-08 2.0E-08 2.0E-08 1.1E-08 1.8E-08 1.8E-08 1.1E-08 1.2E-08 1.2E-08 1.1E-08 9.1E-08 9.6E-08 5.3E-08 9.4E-08 9.9E-08 5.3E-08 1.0E-07 1.1E-07 5.3E-08 6.0E-08 7.0E-08 5.3E-08 ESE 1.2E-07 1.3E-07 6.9E-08 1.2E-07 1.4E-07 6.9E-08 1.3E-07 1.6E-07 6.9E-08 7.2E-08 1.1E-07 6.9E-08 SE 1.3E-07 1.5E-07 7.6E-08 1.4E-07 1.5E-07 7.6E-08 1.4E-07 1.7E-07 7.6E-08 8.1E-08 1.2E-07 7.6E-08 SSE 3.4E-08 3.7E-08 1.6E-08 3.6E-08 3.9E-08 1.6E-08 3.9E-08 4.6E-08 1.6E-08 2.5E-08 3.5E-08 1.6E-08 S 9.6E-08 1.1E-07 4.3E-08 1.0E-07 1.2E-07 4.3E-08 1.2E-07 1.5E-07 4.3E-08 6.1E-08 .1.1E-07 4.3E-08 SSW 7.8E-08 9.1E-08 3.7E-08 8.3E-08 9.7E-08 3.7E-08 9.8E-08 1.2E-07 3.7E-08 5.1E-08 8.0E-08 3.7E-08 SW 6.7E-08 7.8E-08 3.0E-08 7.2E-08 8.3E-08 3.0E-08 8.5E-08 1.0E-07 3.0E-08 4.0E-08 6.5E-08 3.0E-08 WSW 4.1E-08 4.4E-08 1.5E-08 4.4E-08 4.8E-08 1.5E-08 5.5E-08 6.2E-08 1.5E-08 2.8E-08 3.9E-08 1.5E-08 W 3.4E-08 3.5E-08 1.4E-08 3.7E-08 3.5E-08 1.4E-08 4.4E-08 4.6E-08 1.4E-08 2.3E-08 2.5E-08 1.4E-08 WNW 2.3E-09 2.3E-09 8.2E-10 2.5E-09 2.8E-09 8.2E-10 3.1E-09 3.5E-09 8.2E-10 7.7E-10 7.9E-10 8.2E-10 NW 4.2E-09 4.2E-09 2.4E-09 4.2E-09 4.3E-09 2.4E-09 3.8E-08 3.9E-09 2.4E-09 2.6E-09 2.7E-09 2.4E-09 NNW 7.0E-09 7.1E-09 3.9E-09 7.0E-09 7.1E-09 3.9E-09 6.4E-09 6.5E-09 3.9E-09 4.3E-09 4.4E-09 3.9E-09 1.3E-07 1.5E-07 7.6E-08 1.4E-07 1.5E-07 7.6E-08 1.4E-07 1.7E-07 7.6E-08 8.1E-08 1.2E-07 7.6E-08 Page 19 Page 4

Liquid Release Page 4B Radiation Dose To Nearest Individual Receptor From Liquid Release 1998 (Units in rem)

Adult Teen Child Infant First Quarter T. Bod 1.40E-11 7.80E-11 3.30E-12 1.50E-13 Bone 1.50E-11 1.60E-11 2.10E-11 2.70E-13 Th roid 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Second Quarter T. Body 1.40E-11 7.80E-12 3.30E-12 1.50E-13 Bone 1.50E-11 1.60E-11 2.10E-11 2.70E-13 Th roid 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 Third Quarter T. Bod 2.70E-11 1.50E-11 . 6.10E-12 1.30E-13 Bone 3.00E-11 3.20E-11 4.10E-11 5.40E-13 Th roid 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Fourth Quarter T. Bod 3.20E-11 1.80E-11 6.90E-12 7.50E-14 Bone 3.60E-11 3.80E-11 4.80E-11 6.40E-13 Th roid 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 Page 20

ROCHESTER GAS AND ELECTRIC

[52] WEEK RUNNING TOTALS FOR '998 MONTH NOBLE GAS NOBLE GAS [ 52 ] WEEK I-131 I-131 ., [52] WEEK OF 1995 1998 NOBLE GAS 1995 1998 1-131 CURIES CURIES RUNNING uCi uCi RUNNING TOTAL Ci. .TOTAL uCi LAST YEARS TOTAL 44.902 LAST YEARS TOTAL 72.702 JANUARY 3.67 4.08 45.30 5.03 3.93 71.59 FEBUARY 3.37 2.27 44.20 4.90 3.41 70.10 MARCH 7.73 2.16 38.63 8.41 3.78 65.48 APRIL 1.53 2.17 39.26 9.83 3.66 59.31 MAY 3.02 2.16 38.40 5.02 3.78 58.06 JUNE 4,44 2.07 36.03 3.57 3.66 58.15 JULY 3.77 0.09 32.35 4.19 0.01 53.97 AUGUST 2.54 2.09 31.90 3.88 3.66 53.74 SEPTEMBER 3.18 2.81 31.53 3.54 5.07 55.28 OCTOBER 3.28 2.08 30.34 13.10 3.78 45.96 NOVEMBER 4.04 2.06 28.35 5.52 3.66 44.10 DECEMBER 4.32 2.15 26.18 5.70 3.82 42.22 YEARLY 44.89 26.18 72.69 42.22 TOTALS CURIES CURIES uCi uCI NOTE: The 52 week running total is not to exceed 25,000 curies for noble gases.