ML17263A543

Semiannual Radioactive Effluent Release Rept,Jul-Dec 1993. W/940301 Ltr

ML17263A543
Person / Time
Site:	Ginna
Issue date:	12/31/1993
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403110005
Download: ML17263A543 (43)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR 940CQQ.10005 DOC DATE 93 12 31 NOTARIZED NO DOCKET FACIL:50-24'4 Rob~!r:.t Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C.- Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept, Jul-Dec 1993." W/940301 ltr.

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TITLE: 50.36a(a)(2) Semiannual Effluent Release Reports NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA 3 3 PD1-3 PD 1 1 D JOHNSON,A 1 1 D

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zzzM ztzimz ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N. Y. '/4649-0001 ROBERT C MECREDY TELEPHOtr E Vice Prerident AitEn cooE me 546-2700 Clnna Nuclear Production March 01, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Semiannual Radioactive Effluent Release Report R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Sirs:

This Semiannual Radioactive Effluent Release Report is being submitted in accordance with the requirements of Technical Specification Section 6.9.1.4.

Very truly yours, Vice President rgy<

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9403ii0005 93i23i PDR ADOCKr05000244 PDR

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Copies to:

Mr. T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Resident NRC Inspector Ginna Station Ms. Donna Ross New York State Energy Office Empire State Plaza Albany, NY 12223 American Nuclear Insurers MAELU Suite 3005 29 S. Main St.

West hartford, CT 06107-2445 ATTN: Winthrop Hayes Central Records, Ginna Station Category 2.22.2

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SEMlANNUAL RADtOACTlVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 JULY - DECEMBER, 1993

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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 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 5.0 SOLID WASTE 6.0 LOWER LIMIT OF DETECTION NOT MET 7.0 RADIOLOGICAL IMPACT 8.0 METEOROLOGICAL DATA 9.0 LAND USE CENSUS CHANGES 10.0 ANNUALTABULATIONOF PERSONNEL EXPOSURE 11.0 LEAK TEST OF SEALED SOURCES 12.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL 13.0 CHANGES TO THE PROCESS CONTROL PROGRAM 14.0 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 4 Release Permits Not Meeting LLD Requirements Table 5A Radiation Dose to Nearest Individual Receptor from Gaseous Releases Table 5B Radiation Dose to Nearest Individual Receptor from Liquid Releases Table 6A Number of Personnel and Man-Rem by Work and Job Function Table 6B Standard Report of Personnel Whole Body Exposure

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1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report is for the Rochester Gas and Electric Corporation R.E. Ginna plant and is submitted in accordance with the requirements of Technical Specification Section 6.9.1.4. The report covers the period from July 1, 1993 through December 31, 1993.

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. G irma Technical Specifications.

2.0 SUPPLEMENTAL INFORIVIATION 2.1 Re ulator 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 ( 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.

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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 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 maximum permissible concentration values specified in 10CFR20, Appendix B, Table II, column'2 are used to calculate release rates and permissible concentrations at the unrestricted area boundary. A value 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 energy of the radionuclide mixture was 0.277 Mev.

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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 respect-,

ively.

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

Batch Releases 2.5.1 Liciuid 1 ~ Number of batch releases: 1.71 E+02

2. Total time period for batch releases: 3.86 E+04 min.

3. Maximum time period for a batch release: 2.67 E+03 min.

Average time period for batch releases: 2.25 E+02 min.

5. Minimum time period for a batch release: 3.6 E+01 min.

Average stream flow (LPM) during periods of release effluent into a flowing stream: 1.29 E+06 LPM 2.5.2 Gaseous 1 ~ Number of batch releases: 2.8E+ 01

2. Total time period for batch releases: 1.28E+ 04 min.

3. Maximum time period for a batch release: 2.57E+ 03 min.

Average time period for batch releases: 6.09E+ 02 min.

Minimum time period for a batch release: 6.0E+01 min.

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

3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and 18. All releases were considered to be elevated releases.

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 28.

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.

6.0 LOWER LIMIT OF DETECTION NOT MET There were no gamma emitting radionuclides that did not meet the required lower limit of detection for liquid releases.

7.0 RADIOLOGICAL IMPACT 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 upon actual meteorological conditions considering the noble gas exposure, inhalation, ground plane and ingestion pathways. The ingestion pathways considered were the produce, vegetable, goat's milk, cow's milk and meat pathway. The results of this assessment are presented in Tables 5A and 58.

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8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1993 is not included with this report, but can be made available at the R.E.

Ginna Plant as allowed by Technical Specifications.

LAND USE CENSUS CHANGES There were no changes in critical receptor location for dose calculations during the reporting period.

10.0 ANNUAL TABULATION OF PERSONNEL EXPOSURE The annual tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job function required by Technical Specification 6.9.2.2 and 10CFR20.407 is included as Tables 6A and 6B.

11.0 LEAK TEST OF SEALED SOURCES No sealed sources were found to be leaking when smeared by both wet and dry smears.

12.0 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the ODCM during the report period.

13.0 CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the PCP during the reporting period.

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

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CHESTER GAS ELECTRIC CORPORATI Table 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATION OF ALLRELEASES JULY - DECEMBER 1993 Unit Quarter Quarter Est. Total A. Fission 8 activation ases 3rd 4th Error, %

1. Total release Cl 1.97E+01 1.35E+01 6.60E+00

2. Avera e release rate for eriod uCi sec 2.48E+00 1.69E+00

3. Percent of technical s ecification limit 3.94E44 2.69E44 B. Iodines

1. Total iodine-131 CI 1.19E45 3.30E45 1.80E+01

2. Avera e release rate for erlod uCI sec 1.50E-06 4.16E46

3. Percent of technical s ecification limit 3.30E43 9.13E43 C. Particulates

1. Particulates with half-lives > 8da s CI 1.24E46 1.58E46 4.00E+01

2. Avera e release rate for eriod uCI sec 1.57E47 1.99E47

3. Percent of technical s ecification limit 1.18E45 1.50E45

4. Gross al ha radloactivit CI D. Tritium

1. Total release CI 1.15E+01 1.18E+01 3.20E+00

2. Avera e release rate for eriod uCI sec 1.44E+00 1.48E+00

3. Percent of technical s ecification limit 1.70E44 1.74E44 E. Carbon-14

1. Total release Ci 7.95E-01 7.17E-01 3.00E+01

2. Avera e release rate for eriod uCI sec 1.00E41 9.02E-02

3. Percent of technical s ecificatlon limit 5.32E46 4.80E46 Note: Isotope for which no value is given were not identified in applicable releases.

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CHESTER GAS ELECTRIC CORPORATI Table 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS ELEVATED RELEASE Continuous Mode Batch Mode Nuclldes released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th

1. Flsslon ases ar on41 CI 6.63E42 1.38E41 5.66E-02 4.76E42 k ton%5 Ci 2.73E41 1.99E41 k ton%5m CI 5.54E42 6.18E-02 7.53E44 3.35E43 k ton7 CI 7.43E42 7.21E42 1.35E-04 k ton@8 CI 7.35E42 1.02E41 3.07E44 xenon-131m Ci 1.39E42 4.64E42 xenon-133 Ci 1.42E+01 5.70E+00 1.31E+00 3.09E+00 xenon-133m Cl 1.46E42 1.85E42 1.04E42 1.61E42 xenon-135 CI 2.64E+00 2.87E+00 1.90E42 6.39E42 xenon-135m Ci 7.15E41 7.55E-01 1.50E44 xenon-138 Ci 2.58E41 2.76E-01 others s ec Ci CI CI Ci Total for erlod CI 1.81E+01 9.99E+00 1.69E+00 3.47E+00

2. Iodlnes iodine-131 CI 1.19E45 1.26E-05 1.54E48 2.04E45 iodine-133 Ci 1.32E45 1.32E-05 9.02E48 4.16E-05 Iodine-135 Ci Total for eriod CI 2.51E45 2.58E-05 1.06E-07 6.20E45

3. Particulates strontium%9 CI strontium-90 CI cesium-134 Ci cesium-137 Ci 1.24E46 1.58E46 Nb-95 CI cobalt-58 CI cobalt%0 CI Total for eriod CI 1.24E46 1.58E46 unidentified CI Note: Isotope for which no value is given were not Identified in applicable releases.

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CHESTER GAS ELECTRIC CORPORATI Table 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES JULY - DECEMBER 1993 Unit Quarter Quarter Est. Total A. Fission and activation roducts 3rd 4th Error, %

1. Total release (not including tritium, ases,al ha Ci 1.78E42 5.38E-02 7.00E+00

2. Average diluted concentration durin eriod uCi ml 1.03E-10 3.18E-10

3. Percent of a Iicable limit 2.18E43 1.86E42 B. Tritium 1 Total release

~ CI 3.34E+01 5.05E+01 3.20E+00

2. Average diluted concentration durin erlod uCi ml 1.92E47 2.99E47

3. Percent of a licabie limit 6.40E43 9.97E43 C. Dissolved and entrained ases

1. Total release Ci 5.15E44 8.53E42 4.00E+01

2. Average diluted concentration durin erlod uCi ml 2.96E-12 5.05E-10

3. Percent of a licable limit 1.48E46 2.53E-04 D. Gross ai ha radloactivi

1. Total release Ci E. Vol. of waste released rior to dilution Liters 3.84E+07 2.65E+07 5.00E+00 F. Vol. of dilution water used durin erlod Liters 1.74E+11 1.69E+11 5.00E+00 Note: Isotope for which no value is given were not identified in applicable releases.

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h ROCHESTER GAS ELECTRIC CORPORATI Table 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclldes Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th chromium-51 Ci man anese-54 Ci

'.30E44 iron-55 CI iron-59 Ci cobalt-58 CI 7.08E45 3.70E44 cobalt%0 Ci 3.16E-07 4.95E45 7.74E%5 zincM Ci strontium-89 Ci 1.99E44 strontium-90 CI zirconium niobium-95 CI 7.44E46 4.42E-06 mol bdenum-99 Ci 4.05E45 2.02E45 silver-110m CI antinon -122 Ci antinon -124 CI 6.65E44 3.3?E44 antinon -125 Ci 6.87E44 1.29E43 iodine-131 Ci 5.07E46 5.06E-04 6.45E44 4.61 E43 Iodine-133 CI 1.86E44 2.92E-04 1.15E-04 9.23E-03 Iodine-135 Ci 4.25E45 5.30E45 7.13Ee3 cesium-134 CI 3.45E46 6.20E44 8.13E03 1.45E42 cesium-136 CI 1.49E44 cesium-137 CI 1.53E44 7.60E44 7.07E-03 1.33E<2 barium lanthanum-140 CI 9.59E45 cerium-141 Ci Ru-106 CI Ru-103 CI Total for erlod above Ci 3.90E44 2.27E43 1.74E42 5.15E-02 unidentified Ci xenon-133 Ci 4.85E-04 5.82E42 xenon-1 35 Ci 2.97E45 2.71E-02 Note: Isotope for which no value is given were not identified in applicable releases.

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Table 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Solid Waste and Irradiated Fuel Shipments July - December 1993 A. Solid waste shipped offsite for burial or disposal (NOT irradiated fuel)

TYPE OF WASTE UNIT 6 MONTH PERIOD EST. TOTAL ERROR Spent resins, filtersludges, m 8.04 E 0 7.0 E 0 evaporator bottoms, etc. Ci 1.97 E 1 7.0 E 0 Dry compressible waste, m 1.02 E 2 7.0 E 0 contaminated equipment, etc. Ci 1.1 E -1 7.0 E 0 c>> Irradiated components, control m rods, etc. Ci

d. Other {describe) m Ci

'. Estimate of major nuclide composition (by type of waste)

Fo-55 3.1 E 1 Fe-55 3.8 E 1 Co.60 3.0 E 1 Co-60 1.0 E 1 Ni-63 1.951 Nb-95 1.0E 1 Cs-137 7EO Cs-137 9.0 E 0 C-14 5EO Zr-95 7EO H-3 2EO Co-58 7EO Sb-125 2EO Cr-51 6EO Ce-144 5EO Ni-63 4EO Cs-134 2EO Mn.54 1EO

3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 2 Sole use truck Barnwell, SC 2 Sole use truck Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None N/A N/A

1 Table 4 RELEASE PERMITS NOT MEETING LLD REQUIRElVIENTS No. Date Isotopes Cause None

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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem First Quarter ADULT CHILD T.BODY T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD N 7.60E-08 8.90E-OS 1.10E-07 7.80E48 9.50E-OS 1.10E-07 7.80E-08 9.60E-OS 1.10E-07 6.50E-OS 8.20E-OS 1.10E-07 7.20E-08 7.90E-OS 1.00E-07 7.50E48 8.30E-OS 1.00E-07 7.50E-08 8.50E-OS 1.00E-07 6.30E-OS 7.20E-08 1.00E-07 NE 6.10E48 6.60E-08 9.50E-OS 6.30E-08 6.90E-OS 9.50E-OS 6.40E48 7.10E-OS 9.50E-08 5.50E48 6.10E48 9.50E48 9.10E48 9.90E-08 1.70E-07 9.20E48 1.00E-07 1.70E47 9.10E48 1.00E-07 1.70E-07 8.10E48 9.10E-OS 1.70E-07 7.10E-07 7.50E-07 1.10E-06 7.20E-07 7.70E-07 1.10E46 7.20E-07 7.70E-07 1.10E-06 6.30E-07 6.80E-07 1.10E-06 ESE 7.70E-07 8.30E47 1.10E-06 7.90E-07 8.70E-07 1.10E46 8.00E-07 8.80E-07 1.10E-06 6.80E-07 7.60E-07 1.10E-06 SE 8.20E47 8.80E47 1.20E46 8.60E47 9.30E-07 1.20E46 S.SOE-07 9.50E-07 1.20E-06 7.50E-07 8.20E-07 1.20E-06 SSE 3.20E47 3.40E47 5.10E-07 3.20E47 3.50E-07 5.10E-07 3.20E-07 3.50E47 5.10E-07 2.80E47 3.10E47 5.10E-07 1.40E46 1.50E-06 2.40E-06 1.50E46 1.60E-06 2.40E-06 1.50E46 1.60E-06 2.40E-06 1.30E46 1.40E-06 2.40E-06 SSW 4.50E47 4.90E-07 6.60E-07 4.60E47 5.00E-07 6.60E-07 4.50E-07 5.00E-07 6.60E-07 3.90E-07 4.40E-07 6.60E-07 SW 5.80E-07 6.10E-07 6.30E-07 6.00E47 6.40E47 6.30E-07 5.90E-07 6.30E47 6.30E-07 4.80E47 5.10E47 6.30E-07 WSW 5.20E-07 6.00E-07 3.60E-07 5.40E47 6.40E47 3.60E47 5.30E-07 6.40E-07 3.60E-07 4.00E47 5.00E-07 3.60E-07 5.20E-07 6.00E-07 3.60E-07 5.40E47 6.40E-07 3.60E-07 5.30E-07 6.40E-07 3.60E-07 4.00E-07 5.00E-07 3.60E47 2.10E47 2.20E-07 3.20E-07 2.20E47 2.30E-07 3.20E-07 2.20E47 2.30E-07 3.20E-07 1.90E47 2.00E-07 3.20E-07 2.00E48 2.30E-OS 2.40E-OS 2.10E-08 2.40E4S 2.40E48 2.00E-OS 2.40E-OS 2.40E-OS 1.60E-OS 1.90E-08 2.40E48 4.70E-OS 5.60E-08 6.00E-OS 4.90E48 6.00E-OS 6.00E48 4.80E48 6.10E-08 6.00E-OS 4.00E-OS 5.10E-OS 6.00E-OS 1.40E46 1.50E-06 2.40E-06 1.50E-06 1.60E-06 2.40E46 1.50E46 1.60E-06 2.40E46 1.30E-06 1.40E-06 2.40E-06

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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Second Quarter ADULT CHILD INFANT T.BODY THYRD T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN N 3.90E48 4.00E-OS 2.30E-OS 4.00E-OS 4.10E-08 2.30E-OS 3.80E-08 3.90E-OS 2.30E-08 2.70E-OS 2.80E-08 2.30E-OS 3.90E-OS 4.00E48 2.30E48 4.00E48 4.10E-08 2.30E-08 3.80E-OS 3.90E-OS 2.30E-08 2.70E-OS 2.80E-OS 2.30E-OS NE 4.20E48 4.30E-08 2.50E48 4.30E48 4.40E-OS 2.50E48 4.10E-OS 4.20E48 2.50E-08 2.90E-OS 3.00E-OS 2.50E-OS 4.00E-OS 4.10E-OS 2.20E48 4.30E48 -

4.30E-OS 2.20E-OS 4.20E-OS 4.30E48 2.20E-OS 3.00E48 3.10E-08 2.20E-08 2.50E-06 2.60E-06 2.30E46 3.60E46 3.60E-06 3.20E-06 7.20E-06 7.30E-06 6.70E-06 3.00E-06 3.10E-06 2.80E-06 ESE 2.50E-06 2.60E-06 2.20E-06 3.50E46 3.50E-06 3.10E-06 7.00E-06 7.20E46 6.50E-06 4.80E-06 5.00E46 4.60E-06 SE 5.50E47 5.70E-07 5.20E-07 6.50E47 6.90E-07 6.10E-07 1.00E-06 '1.10E46 9.50E47 1.00E-06 1.10E46 9.70E-07 SSE 3.70E-07 3.80E-07 3.90E-07 4.50E-07 4.60E47 4.50E-07 7.10E-07 7.30E-07 6.80E-07 8.20E-07 8.40E47 8.00E47 6.20E-07 6.40E47 5.70E47 7.10E-07 7.30E-07 6.40E47 1.00E-06 1.00E-06 9.00E-07 1.10E-06 1.10E-06 1.00E-06 SSW 5.40E47 5.50E47 5.90E47 6.20E47 6.30E-07 6.60E-07 9.20E-07 9.40E-07 9.20E-07 1.20E-06 1.30E-06 1.20E-06 SW 1.20E-06 1.20E46 1.40E46 1.50E-06 1.50E-06 1.60E46 2.40E46 2.40E46 2.40E-06 3.60E46 3.60E46 3.40E46 WSW 1.00E-06 1.00E-06 7.50E47 1.30E46 1.30E-06 9.30E-07 2.00E-06 2.10E-06 1.60E-06 2.10E46 2.10E46 1.80E-06 W 5.50E47 5.50E-07 4.50E47 6.80E-07 6.90E-07 5.50E-07 1.10E-06 1.20E-06 9.50E-07 8.30E-07 8.30E-07 7.50E-07 3.00E47 3.10E-07 2.40E47 3.20E47 3.20E-07 2.40E47 3.20E-07 3.20E-07 2.40E47 2.50E47 2.50E-07 2.30E-07 1.40E48 1.50E-OS 7.40E49 1.50E48 1.50E-08 7.40E49 1.40E48 1.50E4S 7.40E49 1.00E-OS 1.00E4S 7.40E49 2.60E-OS 2.60E-08 1.40E-OS 2.70E48 2.70E-OS 1.40E-OS 2.60E-08 2.70E-OS 1.40E-OS 1.90E-OS 1.90E48 1.40E-OS 2.50E-06 2.60E-06 2.30E-06 3.60E-06 3.60E-06 3.20E46 7.20E46 7.30E-06 6.70E46 4.80E46 5.00E46 4.60E-06

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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Third Quarter ADULT CHILD T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY N 4.00E-08 4.00E-OS 4.10E-08 4.10E-OS 4.10E-08 4.10E-OS 3.90E-OS 3.90E-OS 4.10E-OS 3.00E-OS 3.00E-08 4.10E-OS 5.60E48 5.70E-OS 6.20E-OS 5.70E-OS 5.80E-OS 6.20E48 5.50E-OS 5.60E-OS 6.20E48 4.40E48 4.40E-OS 6.20E-OS NE 5.70E-08 5.70E-OS 5.30E-OS 5.90E-OS 5.90E48 5.30E-08 5.80E-08 5.80E-08 5.30E48 4.40E48 4.50E-OS 5.30E-OS 3.30E4S 3.30E-OS 2.50E48 3.50E-OS 3.50E-08 2.50E-08 3.60E-OS 3.70E-OS 2.50E-OS 2.70E-OS 2.80E-OS 2.50E-08 2.40E-06 2.40E-06 2.30E46 3.60E-06 3.60E46 3.50E-06 8.00E46 S.OOE-06 7.70E46 3.00E46 3.00E-06 2.90E46 ESE 1.90E-06 1.90E-06 1.70E-06 2.60E-06 2.70E-06 2.40E-06 5.50E-06 5.60E-06 5.10E-06 3.20E-06 3.30E-06 3.20E-06 SE 7.90E-07 8.30E47 7.70E47 9.80E-07 1.00E46 9.30E47 1.70E-06 1.70E-06 1.50E-06 7.40E-07 8.10E-07 8.30E-07 SSE 5.80E-07 6.00E-07 5.80E47 7.20E-07 7.50E-07 7.10E-07 1.30E-06 1.30E-06 1.20E-06 S.OOE-07 8.40E-07 8.30E47 2.50E-06 2.60E46 2.60E46 3.40E-06 3.50E-06 3.50E-06 6.60E-06 6.80E-06 6.50E-06 5.10E-06 5.20E-06 5.40E-06 SSW 9.00E-07 9.40E47 S.60E47 1.20E-06 1.20E-06 1.10E-06 2.40E-06 2.40E-06 2.20E46 1.90E-06 2.00E46 2.00E-06 SW 2.00E-06 2.00E-06 2.00E-06 2.70E-06 2.80E-06 2.70E-06 5.70E-06 5.80E-06 5.60E46 7.40E-06 7.50E-06 7.50E46 WSW 2.30E46 2.30E-06 2.20E46 3.50E46 3.50E-06 3.30E-06 7.80E-06 7.90E-06 7.60E-06 3.60E46 3.70E-06 3.50E-06 1.10E-06 1.20E-06 1.10E46 1.70E-06 1.70E-06 1.60E-06 3.70E-06 3.70E-06 3.50E46 1.60E-06 1.60E-06 1.50E-06 6.10E47 6.10E47 6.40E47 9.40E-07 9.40E47 9.50E47 2.10E46 2.10E-06 2.10E46 8.20E48 8.20E-08 1.20E-07 1.70E-OS 1.70E48 1.40E4S 1.70E-OS 1.70E48 1.40E-OS 1.70E-08 1.70E-OS 1.40E48 1.30E-OS 1.30E-OS 1.40E-OS 1.90E-OS 1.90E48 1.70E-08 2.00E-OS 2.00E48 1.70E48 2.00E-OS 2.00E-OS 1.70E-OS 1.50E-OS 1.50E-OS 1.70E-08 2.50E-06 2.60E-06 2.60E-06 3.60E-06 3.60E-06 3.50E46 8.00E-06 S.OOE-06 7.70E-06 7.40E-06 7.50E-06 7.50E-06

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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Fourth Quarter ADULT CHILD T.BODY THYRD SKIN T.BODY THYRD SKIN T.BODY THYRD T.BODY TIN'RD SKIN N 3.60E-OS 3.60E48 2.60E48 3.70E-OS 3.80E-08 2.60E-OS 3.50E-OS 3.60E-OS 2.60E-08 2.60E-OS 2.70E-OS 2.60E-OS 4.30E-08 4.40E-OS 3.20E-OS 4.40E-OS 4.60E48 3.20E-OS 4.40E-OS 4.50E-OS 3.20E-OS 3.30E-08 3.40E-OS 3.20E-OS NE 2.30E48 2.30E48 1.50E-OS 2.30E-OS 2.40E48 1.50E-08 2.30E-OS 2.30E-08 1.50E-08 1.70E48 1.70E48 1.50E48 1.70E-OS 1.80E-08 1.00E-08 1.80E-OS 1.80E-OS 1.00E-OS 1.80E-08 1.80E-OS 1.00E-OS 1.30E-08 1.30E-08 1.00E-OS 6.40E-07 6.70E-07 6.60E47 7.90E-07 8.20E-07 8.10E-07 1.30E46 1.40E-06 1.30E-06 1.10E-06 1.10E-06 1.20E-06 ESE ~

3.00E-07 3.20E-07 3.20E-07 3.40E-07 3.60E-07 3.70E-07 5.10E-07 5.40E-07 5.30E-07 2.50E-07 2.80E-07 3.20E-07 SE 3.20E-07 3.40E-07 3.50E-07 3.60E-07 3.80E47 3.90E47 5.00E47 5.30E-07 5.30E-07 2.40E47 2.60E-07 3.10E-07 SSE 3.10E-07 3.20E47 3.10E-07 3.70E-07 3.80E-07 3.70E-07 5.80E47 6.00E-07 5.90E-07 7.40E-07 7.60E47 7.80E47 8.70E-07 9.00E47 1.10E-06 1.00E-06 1.10E-06 1.30E46 1.70E46 1.70E-06 1.90E-06 9.50E47 1.00E46 1.30E46 SSW 1.70E-07 1.80E-07 1.50E-07 1.90E-07 1.90E-07 1.60E-07 2.40E47 2.50E-07 2.20E-07 1.20E-07 1.20E-07 1.30E-07 SW 2.50E-07 2.60E-07 2.60E-07 2.80E-07 2.90E-07 2.80E-07 3.50E47 3.70E47 3.40E-07 3.00E47 3.20E-07 3.30E-07 WSW 1.50E-07 1.60E47 1.70E47 1.80E-07 1.90E47 1.80E-07 2.40E47 2.60E-07 2.40E-07 1.80E47 2.00E47 2.00E47 W 2.40E47 2.50E47 2.60E-07 2.70E-07 2.80E-07 2.80E-07 3.70E-07 3.80E-07 3.70E-07 2.50E47 2.60E-07 2.80E-07 1.40E-07 1.50E-07 1.80E-07 1.50E-07 1.70E-07 1.90E-07 1.90E47 2.10E-07 2.30E-07 1.10E-07 1.20E47 1.70E-07 8.40E49 8.50E-09 4.70E-09 8.90E-09 9.10E49 4.70E-09 8.90E-09 9.10E-09 4.70E49 6.50E49 6.60E49 4.70E-09 1.70E-08 1.70E-08 1.20E-OS 1.80E-OS 1.80E-08 1.20E-08 1.80E-OS 1.80E-OS 1.20E-OS 1.40E48 1.40E48 1.20E-OS 8.70E-07 9.00E47 1.10E-06 1.00E-06 1.10E-06 1.30E-06 1.70E-06 1.70E-06 1.90E-06 1.10E-06 1.10E-06 1.30E-06

Table 5B Radiation Dose To Nearest Individual From Liquid Releases In REM ADULT TEEN CHILD INFANT First Quarter T.BODY 9.10E-06 5.20E-06 2.00E-06 1.60E-08 BONE 6.90E-06 7.20E-06 9.00E-06 1.20E-07 THYRD 5.10E-07 4.60E-07 7.80E-07 8.00E-07 Second Quarter T.BODY 6.80E-06 3.90E-06 1.50E-06 1.10E-08 BONE 4.90E-06 5.20E-06 6.40E-06 8.50E-08 THYRD 2.80E-08 2.50E-08 4.10E-08 4.10E-08 Third Quarter T.BODY 9.90E-06 5.60E-06 2.20E-06 1.60E-08 BONE 7.10E-06 7.40E-06 9.30E-06 1.20E-07 THYRD 1.10E-07 9.70E-08 1.60E-07 1.60E-07 Fourth Quarter T.BODY 1.40E-05 8.20E-06 3.10E-06 2.50E-08 BONE 1.10E-05 1.10E-05 1.40E-05 1.80E-07

'IKYRD 6.30E-07 5.70E-07 9.70E-07 1.00E-06

ROCHESTER GAS 8 ELECTRIC CORPORATION GINNA STATION, NUMBER OF PERSONNEL AHD HAN-REH BY lRRK AND JOB FUNCTION FOR 93/01/01 . 93/12/31 ACTUAL MHOLE BODY DOSE NO. OF PERSONNEL (> 100) TOTAL MAN REH COHTRACT STATION UTILITY CONTRACT STATION UTILITY MORK PERMIT CATERGORY WORK GROUP QRKERS EMPLOYEES EMPLOYEES MORKERS EMPLOYEES EMPLOYEES REACTOR OPERATIONS t, SURV MAINTENANCE PERSOHHEL 110 43 50 1.040 1.052 0.182 OPERATING PERSONNEL 0 27 0 0.000 4.728 0.000 HEALTH PHY. PERSONNEL 48 13 0 2.233 1.136 0.000 SUPERVISORY PERSONNEL 12 14 16 0.284 '1.179 0.637 ENGINEERING PERSOHHEL 4 1 2 0.202 0.041 0.'143 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 141 43 75 7.305 5.994 3.630 OPERATING PERSONNEL 0 , 20 0 0.000 0.249 0.000 HEALTH PHY. PERSONNEL 51 13 3 14.109 4.378 0.330 SUPERVISORY PERSONNEL 13 14 15 0.345 1.480 0.677 ENGINEERING PERSONNEL 3 1 2 0 ~ 562 0.162 0.054 INSERVICE INSPECTION MAINTENANCE PERSONNEL 54 27 44 4.464 1.511 2.617 OPERATING PERSONHEL 0 6 0 0.000 0.228 0.000 HEALTH PHY. PERSONNEL 28 8 1.377 0.173 0.000 SUPERVISORY PERSONNEL '0 11 14 0

1.224 0.870 3.346 ENGINEERIMG PERSONNEL 1 0 2 0.020 0.000 0.056 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 132 42 77 12.567 8.672 8.857 OPERATING PERSONNEL 0 22 0 5.000 1.419 0.000 HEALTH PHY. PERSOHNEL 34 11 3 2.651 1.267 0.015 SUPERVISORY PERSOHHEL 9 5 14 0.667 0.513 0.632 ENGINEERING PERSONNEL 2 1 1 0.149 0.035 0.000 llASTE PROCESSING MAINTENANCE PERSONNEL 24 14 0.452 0.291 0.106 OPERATING PERSONNEL 0 0 ~ 000 0.093 0.000 HEALTH PHD PERSOHHEL 18 5 0.634 0.261 0.131 SUPERVISORY PERSONNEL 1 1 0.018 0.021 0.111 ENGINEERING PERSONNEL 0 0 0.000 0.000 0.000 REFUELING MAINTENANCE PERSONNEL 33 18 27 9.426 0.609 2.160 OPERATING PERSOHNEL 0 8 0 0.000 2.143 0.000 HEALTH PHD PERSONNEL 13 2 0 0.754 0.339 0.000 SUPERVISORY PERSONNEL 3 2 5 0.100 0.285 0.120 EHGIHEERIHG PERSOHHEL 1 1 0 O.128 O.448 0 ~ 000 MODIFICATIONS HAINTENAMCE PERMNNEL 87 14 12 8.142 0.447 0.216 OPERATING PERSONNEL 0 0 0 0.000 0.000 0.000 HEALTH PHY. PERSONHEL 21 3 0 1.769 0.079 0.000 SUPERVISORY PERSONNEL 5 4 4 0.331 0.083 0.012 ENGIHEERING PERSONNEL 1 0 1 0.000 0.000 0.015 TOTAL MAINTENANCE PERSOHHEL 172 43 77 43.397 18.576 17.768 OPERATING PERSONNEL 0 27 0 0.000 8.859 0.000 HEALTH PHD -PERSOHHEL 53 13 3 23.527 7.634 0.476 SUPERVISORY PERSOHHEL 14 14 16 2.968 4.431 5.535 ENGINEERING PERSONHEL 1 2 1.061 0.686 0.268 GRAND TOTAL RRSSSRSRRkRRRSSSSNSIR 241 97 98 70.953 40.186 24.047

Table 6B STANDARD REPORT OF PERSONNEL WHOLE BODY EXPOSURE 1993 DOSE REM NUMBER OF PEOPLE 00.000 - 00.000 759 00.001 - 00.100 370 00.101 - 00.250 224 00.251 - 00.500 153 00.501 - 00.750 58 00.751 - 01.000 31 01.001 - 02.000 20 02.001 - 03.000 0 03.001 - 04.000 0 04.001 - 05.000 0 Total number of personnel monitored 1615 The total collective dose for 1993 is 193.13 person-rem based on the sum of all personnel TLD badge readings.

FIVE HIGHEST EXPOSURES FOR THE YEAR A 1.838 rem B 1.452 rem C 1.441 rem D 1.436 rem E 1.338 rem This report contains all personnel monitored during 1993.