ML17263A160

Semiannual Radioactive Effluent Release Rept Jul-Dec 1992

ML17263A160
Person / Time
Site:	Ginna
Issue date:	12/31/1992
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303040188
Download: ML17263A160 (30)

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ACCELERAT DOCUMENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTION 4/STEM (RIDS) lg ACCESSION NBR:9303040188 DOC.DATE: 92/12/31 NOTARIZED:

NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

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"Semiannual Radioactive Effluent Release Rept Jul-Dec 1992.'"

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Semiannual Effluent Release Reports NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 7 E S. E P N0 N E AREA CODE 7SSS 546-2700 February 26, 1993 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, Robert C.

Me redy Vice President 040OCB q808040188 8SS)88$

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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 The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 ATTN:

Winthrop Hayes Central Records, Ginna Station Category 2.22.2

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R.

E.

GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 JULY DECEMBER, 1992

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 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 ANNUAL TABULATION OF PERSONNEL EXPOSURE 11.0 LEAK TEST OF SEALED SOURCES 12 '

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 Table Table Table Table Table Table Table 5B Radiation Dose to Nearest Individual Receptor from Gaseous Releases Radiation Dose to Nearest Individual Receptor from Liquid Releases 1A Gaseous Effluents Summation of all Releases 1B Gaseous Effluents

- Continuous and Batch Releases 2A Liquid Effluents

Summation of all Releases 2B Liquid Effluents - Continuous and Batch Releases 3

Solid Waste and Irradiated Fuel Shipments 4

Release Permits Not Meeting LLD Requirements Table 6A Number of Personnel and Man-Rem by Work and Job Function Table 6B Standard Report of Personnel Whole Body Exposure

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 require-ments of Technical Specification Section 6.9.1.4.

The report covers the period from July 1,

1992 through December 31, 1992.

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

< 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.

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 calcu-lated 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 '.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 concen-tration 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 0.237 Mev.

2.4 Measurements and A

roximations of Total Radioactivit Gamma spectroscopy was the primary analysis method used to determine the radionuclide composition and concen-tration 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 deter-mined from the measured concentration of each radio-nuclide present and the total volume of effluents released.

2.5 Batch Releases 2.5.1 1.

2.

3.

5.

6.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for batch releases:

Minimum time period for a batch release:

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

1.32 E+02 2.07 E+04 min.

6.76 E+02 min.

1.57 E+02 min.

1.4 E+Ol min.

1.28 E+06 LPM 2.5.2 Gaseous l.

2.

3.

5.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for batch releases:

Minimum time period for a batch release:

2.1E+01 3.95E+04 min.

1.04E+04 min.

1.88E+03 min.

2.25E+02 min.

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 1B.

All releases were considered to be elevated releases.

4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS 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 types'.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 indivi-dual 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, inhala-tion, 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 SA and SB.

8.0 METEOROLOGICAL DATA 9.0 The annual summary of hourly meteorological data collected during 1992 is not included with this report, but can be made available at the RE E.

Ginna Plant as allowed by Technical Specifications.

LAND USE CENSUS CHANGES 10.0 There were no changes in critical receptor location for dose calculations during the reporting period.

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 12.0 13.0 14.0 No sealed sources were found to be leaking when smeared by both wet and dry smears.

CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

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

CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

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

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

OCHESTER GAS ELECTRIC CORPORAl N

Table 1A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JULY - DECEMBER 1992 A. Fission &activation ases

1. Total release

2. Avera e release rate for eriod

3. Percent of technical s eclfication limit Unit CI uCi/sec Quarter 3RD 4.03E+01 5.12E+00 8.13E-04 Quarter 4th Est. Total Error, %

5.95E+01 6.60E+00 7.57E+00 1.20E-03 B. Iodines

1. Total iodine-131 CI 1.65E-05 1.45E-05 1.80E+01

2. Avera e release rate for eriod uCi/sec 2.10E-06 1.85E-06

3. Percent oftechnical s ecification limit C. Particulates

1. Particulates with half-lives > 8da s CI 4.62E-03 4.06E-03 8.16E-08 8.43E-07 4.00E+01

2. Avera e release rate for eriod

3. Percent of technical s ecification limit

4. Gross ai ha radioactivit D. Tritium

1. Total release

2. Avera e release rate for eriod

3. Percent of technical s ecification limit E. Carbon-14 uCi/sec CI CI uCi/sec 1.04E-08 7.80E-07 7.42E+00 9.44E-01 1 ~11E-04 1.07E-07 8.06E-06 1.81E+01 2.30E+00 2.71E-04 3.20E+00

1. Total release

2. Avera e release rate for eriod

3. Percent of technical s ecification limit Ci uCi/sec 7.07E-01 6.07E-01 8.99E-02 7.72E-02 4.78E-06 4.1 1E-06 3.00E+01 Note:

Isotope for which no value is given were not identified in applicable releases.

OCHESTER GAS ELECTRIC CORPORA N

Table 1B EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - ELEVATEDRELEASE Nuclides released 1 ~

Fission ases Unit Continuous Mode Batch Mode Quarter Quarter Quarter Quarter 4th 4th a

on-41 k

ton-85 k

ton-85m k

ton-87 k

ton-88 xenon-1 31m xenon-133 xenon-1 33m xenon-135 xenon-135m xenon-138 others s ecif Ci Ci CI Ci CI Ci Ci CI Ci CI CI CI Ci Ci CI 1.55E-01 8.70E-02 1.21E-01 1.62E-01 4.56E-02 1.58E+01 1.14E+00 3.09E+00 1.13E+00 4.10E-01 1.32E-01 7.16E-02 9.63E-02 1.44E-01 2.09E-02 1.46E+01 1.97E-02 5.76E+00 9.75E-01 3.68E-01 3.47E-01 4.18E-01 2.38E-02 1.96E-02 2.01E-01 1.65E+01 1.76E-01 4.28E-01 1.29E+00 1.83E-01 7.81E-02 8.09E-02 1.55E-01 3.37E+01 4.34E-01 1.41E+00 Total for eriod 2.

Iodines iodine-1 31 iodine-1 33 iodine-1 35 Total for eriod 3.

Particulates strontium-89 CI Ci Ci Ci Ci CI 2.21E+01 2.22E+01 1.65E-05 1.45E-05 1.41E-05 2.33E-05 3.06E-05 3.78E-05 1.81E+01 4.91E-09 4.91E-09 3.73E+01 strontium-90 cesium-134 cesium-137 other s ecif cobalt-58 cobalt-60 Total for eriod unidentified CI Ci CI Ci Ci CI CI Ci 8.16E-08 8.16E-08 1.18E-06 8.43E-07 8.43E-07 Note:

Isotope for which no value is given were not identified in applicable releases.

OCHESTER GAS ELECTRIC CORPORA N

Table 2A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES JULY-DECEMBER 1992 A. Fission and activation roducts Unit Quarter 3RD Quarter 4th Est. Total Error, %

1. Total release (not including tritium, ases, al ha Ci 1.66E-02 1.33E-02 7.00E+00

2. Average diluted concentration durin eriod

3. Percent of a licable limit B. Tritium uCi/ml 9.74E-11 1.13E-03 7.90E-11 2.10E-03

1. Total release

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci uCi/ml 2.30E+01 5.15E+01 1.35E-07 3.06E-07 4.49E-03 1.02E-02 3.20E+00 C. Dissolved and entrained ases

1. Total release

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci uCi/ml 9.25E-04 5.91E-04 5.42E-12 3.51E-12 2.71E-08 1.75E-06 4.00E+01 D. Gross al ha radioactivit

1. Total release N/A N/A E. Vol. of waste released rior to dilution Liters 2.85E+07 2.25E+07 5.00E+00 F. Vol. of dilution water used durin eriod Liters 1.71E+11 1.68E+11 5.00E+00 Note:

Isotope forwhich no value is given were not Identified in applicable releases.

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OCHESTER GAS ELECTRIC CORPORA N

Table 2B EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS Continuous Mode Batch Mode Nuclides Released chromium-51 man anese-54 iron-55 iron-59 Unit Ci Ci Ci Ci Quarter Quarter 4th Quarter 1.55E-05 Quarter 4th 3.47E-05 cobalt-58 cobalt-60 zino-65 strontium-89 strontium-90 zirconium/niobium-95 mol bdenum-99 silver-110m antinon -122 antinon -124 antinon -125 iodine-1 31 iodine-1 33 iodine-135 cesium-134 cesium-1 36 cesium-1 37 barium/lanthanum-140 cerium-141 Sn-117m Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.49E-07 2.64E-05 5.31E-05 6.60E-06 2.58E-05 3.39E-05 3.1 8E-05 3.65E-05 1.87E-06 5.05E-06 9.61E-05 1.27E-04 2.07E-05 5.94E-05 5.88E-06 1.82E-05 2.82E-04 1.90E-04 1.23E-04 8.06E-03 7.65E-03 1.75E-06 1.20E-06 9.64E-05 1.70E-04 6.09E-04 4.34E-04 2.97E-04 5.68E-03 5.74E-03 Te-131m Total for eriod above unidentified xenon-133 xenon-1 35 Ci Ci Ci Ci Ci 2.09E-04 2.36E-04 1.64E-02 1.31E-02 9.10E-04 5.14E-04 1.51E-05 7.62E-05 Note:

Isotope forwhich no value is given were not identiTied in applicable releases.

A.

i Table 3

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1.

T e of waste a.

Spent resins, filter sludges, eva orator bottoms etc.

b. Dry compressible

waste, con-taminated e i etc.

c. Irradiated components, control rods etc.

d. Other (describe)

Unit Ci mCi Ci 6-month Period 1,76 E+01 2.96 E+02 3.35 E+01 1.33 E+00 Est. Total Error 0

2.0E+00 2.0E+01 2.0E+00 2.0E+01 2

~ Estimate of major nuclide composition (by type of waste) a.

Co-60 Ni-63 Cs-137 Cs-134 Fe-55 Co-58 Mn-54 Sb-125 b.Fe-55 Cs-137 Cs-134 Co-60 Ni-63 Mn-54 2.83 E+01 2.83 E+01 1.61 E+01 1.09 E+01 7.4 E+00 6.1 E+00 1.0 E+00 8.0 E+00 4.88 E+01 2.30 E+01 1.06 E+01 8.3 E+00 5.2 E+00 2.0 E+00

• Volume and activity buried by waste processor duxing this period.

3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination Sole use truck Sole use truck

Barnwell, SC Oak Ridge, TN

• • Transported directly to Barnwell

• • • Transported to waste processor for volume reduction.

B.

IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi ments Mode of Trans ortation Destination None N/A N/A

RELEASE PERMITS NOT MEETING LLD REQUIREMENTS No.

Date Isoto es None Cause

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem First Quarter Direction Total Adult Skin Thyroid Total Teen Skin Thyroid Total Body Child Skin Thyroid Total Body Infant Skin Thyroid N

9.7E48 1.3E47 9.8E48 9.8E48 1.3E47 9.9E48 9.5E48 1.3E47 9.5E48 7.8E48 1.3E47 7.9E48 NE 7.9E48 7.1E48 1.1 E47 7.9E48 8.0E48 9.7E48 7.2E48 7.3E48 1.1E47 8.0E48 9.7E48 7.3E48 7.7E48 1.1E47 7.1 E48 9.7E48 7.7E48 6.5E48 7.1 E48 5.9E48 1.1E47 6.5E48 9.7E48 5.9E48 ENE 5.7E48 7.5E48 5.7E48 5.9E48 7.5E48 5.9E48 5.9E48 7.5E48 5.9E48 4.9E48 7.5E48 4.9E48 E

6.6E47 7.9E47 6.7E47 7.3E47 8.4E47 7.4E47 9.5E47 1.0E46 9.7E47 5.6E47 7.9E47 5.7E47 ESE SSE 1.2E48 9.7E47 4.2E47 1.3E46 1.2E46 1.6E48 5.3E47 4.3E47 4.8E47 1.2E46 9.8E47 1.2E46 1.7E46 1.6E46 1.4E46 1.2E46 5.7E47 4.8E47 3.2E46 3.2E46 2.1E46 2.3E48 6.6E47 7.2E47 2.1E46 6.5E47 6.7E47 4.3E47 3.2E46 5.8E47 7.7E47 6.1E47 9.4E47 6.7E47 5.8E47 4.5E47 S

1.3E46 1.5E48 1.3E46 1.5E46 1.6E48 1.5E46 2.3E46 2.3E46 2.3E46 1.0E46 1.4E48 1.1E46 SSW SW WSW W

8.0E47 1.0E46 4.3E47 3.0E47 8.3E47 8.1 E47 9.3E47 1.2E46 1.0E46 1.1E46 5.2E47 4.3E47 4.9E47 4.1E47 3.0E47 3AE47 9.4E47 9.5E47 4.4E47 3.4E47 1.3E46 1.2E46 5.7E47 4.9E47 4.5E47 5.4E47 1.4E46 1.3E46 1.5E46 1.7E46 7.0E47 7.5E47 1.4E46 S.0E47 1.6E46 7.7E47 4.5E47 3.0E47 7.1 E47 3.5E47 5.2E47 4.4E47 3.7E47 3.0E47 7.3E4T 7.3E47 1.2E46 8.1E47 WNW NW NNW 2.1 E47 2.5E48 4.9E48 3.5E47 2.1 E47 2.2E47 2.8E48 2.5E48 2.5E48 6.5E48 4.9E48 5.0E48 2.8E48 2.5E48 6.5E48 5.0E48 3.5E47 2.2E47 2.3E47 3.5E47 2.4E48 2.8E48 4.8E48 6.5E48 2.3E47 2.4E48 4.8E48 1.9E47 1.9E48 4.0E48 2.8E48 1.9E48 6.5E48 4.0E48 3.5E47 1.9E47 1.3E48 1.5E46 1.3E46 1.6E46 1.7E46 1.6E46 3.2E46 3.2E46 3.2E46 1.0E46 1.4E46 1.1E46

4 ~

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Second Quarter Direction Total Adult Skin Thyroid Total Teen Skin Thyroid Total Child Skin Thyroid Total Infant Sldn N

3.0E48 3.3E48 2.6E48 2.3E48 3.8E48 4.3E48 3.6E48 2.7E48 4.9E48 4.0E48 3.8E48 3.1E48 2.3E48 3.9E48 4.3E48 5.3E48 3.3E48 4.1 E48 4.0E48 4.3E48 3.1E48 3.3E48 2.7E48 2.3E48 5.5E48 3.2E48 4.1E48 2.4E48 4.1 E48 2.1E48 2.3E48 3.3E48 4.3E48 4.6E48 3.3E48 3.4E48 ENE 5.8E48 1.2E47 6.7E48 5.9E48 1.2E47 7.1 E48 5.9E48 1.2E47 7.2E48 5.3E48 1.2E47 6.5E48 ESE SE SSE SSW SW 4.2E46 1.5E46 5.5E47 8.4E47 9.8E46 2.7E46 4.7E47 8.0E47 1.1E46 8.6E47 3.4E46 3.3E46 4.1 E46 9.5E46 4.7E46 4.5E46 1.8E46 1.6E46 7.9E47 6.4E47 1.1E46 1.0E46 1.4E46 1.3E46 3.7E46 4.8E46 4.5E46 4.4E46 9.7E46 4.8E46 1.0E45 5.0E46 2.8E46 2.0E46 5.2E47 9.3E47 9.2E47 1.3E46 1.0E46 1.7E46 4.7E46 5.2E46 5.3E46 2.1E46 9.0E47 1.1E45 3.2E46 7.3E47 1.5E46 1.4E46 2.0E46 1.6E46 9.9E46 9.7E46 5.4E46 1.1E45 1.3E46 7.5E47 1.9E46 9.8E47 2.5E46 9.1E47 1.0E45 4.5E46 5.9E46 3.9E46 6.0E46 4.1 E46 2.5E46 1.5E46 2.9E46 7.2E47 2.0E46 1.1 E46 1.0E46 1.4E46 8.8E47 1.4E46 4.5E46 4.1E46 9.5E46 4.5E46 9.9E46 4.8E46 WSW W

1.3E46 1.2E46 2.3E46 2.2E46 2.6E46 3.1E46 1.5E46 1.8E46 1.7E46 2.1 E46 3.0E46 3.5E46 6.2E46 6.0E46 3.5E46 3.3E46 6.8E46 3.8E46 4.6E46 2.5E46 2.4E46 2.8E46 4.6E46 5.3E46 WNW 2.4E47 2.1E47 2.9E47 2.9E47 2.5E47 3.5E47 4.6E47 4.0E47 5.4E47 1.2E47 1.4E47 1.8E47 NW 9.5E49 8.2E49 1.1 E48 9.8E49 8.2E49 1.2E48 9.6E49 8.2E49 1.2E48 7.3E49 8.2E49 9.6E49 NNW 1.9E48 1.5E48 2.5E48 2.0E48 1.5E48 2.7E48 2.1 E48 1.5E48 2.9E48 1.6E48 1.5E48 2.3E48 4.2E46 9.8E46 4.7E46 4.8E46 1.0E45 5.2E46 9.9E46 1.1 E45 1.0E45 4.6E46 9.9E46 5.3E46

II 4

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Third Quarter Direction Total Adult Skin Thyroid Total Teen Skin Thyroid Total Body Child Sldn Thyroid Total Infant Skin Thyroid N

3.7E48 5.1E48 3.7E48 3.8E48 5.1E48 3.8E48 3.8E48 5.1E48 3.8E48 3.2E48 5.1E48 3.3E48 NNE 3.2E48 5.4E48 3.3E48 3.3E48 6.0E48 1.1E47 6.0E48 6.1E48 1.1E47 5.4E48 6.1E48 6.0E48 3.3E48 3.3E48 1.1E47 6.1 E48 5.4E48 3.3E48 5.5E48 2.9E48 1.1 E47 5.4E48 5.5E48 3.0E4S ENE 2.4E48 3.7E48 2.4E48 2.4E48 3.7E48 2.4E48 2.4E48 3.7E48 2.4E48 2.1 E48 3.7E48 21E48 ESE 1.3E46 1.6E46 1.4E46 1.SE46 1.4E46 1.7E46 1.5E46 1.SE46 2.0E46 2.1 E46 1.9E46 3.6E46 1.9E46 3.4E46 3.7E46 3.7E46 3.6E46 3.5E46 1.1 E46 1.1E46 1.4E46 1.5E46 1.2E46 1.3E46 SE 9.5E47 1.3E46 9.9E47 1.2E46 1.5E46 1.2E46 2.0E46 2.2E46 20E46 8.5E47 1.3E46 9.5E47 SSE 7.2E47 9.1E47 7.5E47 9.4E47 1.1E46 9.6E47 1.7E46 1.9E46 1.8E46 7.0E47 9.4E47 7.8E47 SSW SW 1.3E46 1.7E46 1.4E48 1.6E46 3.1E46 3.5E46 3.2E46 4.5E48 9.2E47 1.1 E46 9.6E47 1.2E46 4.9E46 1.4E48 2.0E46 4.6E46 9.8E48 1.2E46 2.2E46 1.7E46 2.8E46 1.0E45 2.4E46 9.9E48 2.3E46 3.1E46 2.9E46 1.2E46 1.7E46 3.6E46 4.1E46 5.7E47 8.7E47 3.7E48 6.2E47 1.4E46 WSW 7.9E47 9.4E47 8.1E47 1.0E46 1.2E46 1.0E46 1.8E46 1.9E46 1.9E46 9.3E47 1.2E46 1.0E46 W

WNW 1.5E-06 1.7E46 1.6E46 2.2E46 4.4E47 5.4E47 4.5E47 6.3E47 2.4E46 7.2E47 6.3E47 1.3E46 2.2E46 4.8E46 4.8E46 4.8E48 1.4E46 1.3E46 21E46 2.3E46 1.4E46 2.4E47 2.1 E46 1.4E47 NW 9.2E49 12E48 9.2E49 9.7E49 1.2E48 9.8E49 1.0E4S 1.2E4S 1.0E48 8.3E49 1.2E48 8.4E49 NNW 1.7E48 2.2E48 1.7E48 1.8E48 2.2E48 1.8E48 1.9E48 2.2E48 1.9E48 1.6E48 2.2E48 1.6E48 3.1 E46 3.5E46 3.2E46 4.5E46 4.9E46 4.6E46 9.8E46 1.0E45 9.9E46 3.6E46 4.1E46 3.7E46

~

~

k lw~

II

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Fourth Quarter Direction Total Adult Skin Thyroid Total Teen Thyroid Total Child Skin Total Infant SMn Thyroid N

NNE NE 1.6E47 3.5E47 1.0E47 2.1E47 6.7E48 1.2E47 1.7E47 1.7E47 1.0E47 1.0E47 7.1E48 6.9E48 2.1E47 1.1E47 1.2E47 7.4E48 3.5E47 1.7E47 1.6E47 1.0E47 3.5E47 2.1 E47 7.0E48 1.2E47 1.7E47 1.1 E47 1.5E47 9.3E48 7.5E48 6.2E48 2.1E47 9.6E48 1.2E47 6.7E48 3.5E47 1.6E47 ENE ESE 1.3E47 3.2E46 2.3E46 2.8E47 7.5E46 4.1E46 1.3E47 1.3E47 3.3E46 3.2E46 2.6E46 24E46 7.5E46 4.1E46 3.4E46 2.7E46 2.8E47 1.4E47 1.3E47 3.2E46 2.8E47 7.5E46 2.4E46 4.1E46 3.4E46 2.7E46 3.1E46 2.2E46 1.4E47 1.2E47 2.8E47 1.3E47 4.1 E46 2.5E46 7.5E46 3.2E46 SE 3.3E46 6.3E46 3.5E46 3.3E46 6.3E46 3.6E46 3.3E46 6.3E46 3.6E46 3.1E46 6.3E46 3.4E46 SSE SSW 2.2E46 4.7E46 1.2E46 2.7E46 1.6E46 3.3E46 1.7E46 1.6E46 2.2E46 2.2E46 1.3E46 1.3E46 4.7E46 2.2E46 2.7E46 1.3E46 3.3E46 1.7E46 2.2E46 1.3E46 4.7E46 2.7E46 1.6E46 3.3E46 2.2E46 1.3E46 2.1E46 1.2E46 1.7E46 1.5E46 4.7E46 2.1E46 2.7E46 1.2E46 3.3E46 1.6E46 SW 9.0E47 2.0E46 9.0E47 9.1E47 2.0E46 9.2E47 9.2E47 2.0E46 9.2E47 8.8E47 2.0E46 8.8E47 WSW W

1.5E46 3.6E46 8.6E47 2.2E46 8.9E47 8.7E47 1.5E46 1.5E46 2.2E46 3.6E46 9.0E47 1.5E46 8.8E47 2.2E46 1.5E46 3.6E46 9.1E47 8.5E47 1.5E46 1.4E46 2.2E46 8.8E47 3.6E46 1.4E46 WNW 9.8E47 2.7E46 9.9E47 9.8E47 2.7E46 1.0E46 9.8E47 2.7E46 1.0E46 9.7E47 2.7E46 9.9E47 NW 4.6E48 9.5E48 4.6E48 4.7E48 9.5E48 4.7E48 4.7E48 9.5E48 4.8E48 4.3E48 9.5E48 4.3E48 NNW 1.0E47 2.0E47 1.1 E47 1.0E47 2.0E47 1.1 E47 1.0E47 2.0E47 1.1E47 9.3E48 2.0E47 9.8E48 3.3E46 7.5E46 3.5E46 3.3E46 7.5E46 3.6E46 3.3E46 7.5E46 3.6E46 3.1E46 7.5E46 3.4E46

Table 5B RADIATION DOSE TO NEdLREST INDIVIDUAL FROM LIQUID RELEASES IN REM First Quarter Total Body Bone Thyroid Second Quarter Total Body Bone Thyroid Third Quarter Total Body Bone Thyroid Fourth Quarter Total Body Bone Thyroid Adult 9.7E-06 7.2E-06 1.4E-07 2.1E-05 1.7E-05 1.6E-06 1.3E-OS 9.8E-06 3.9E-08 7.3E-OS 5.4E-05 1.5E-05 Teen 5.5E-06 7.6E-06 1.3E-07 1.2E-OS 1.8E-05 1.5E-06 7.6E-06 1.5E-OS 3.5E-08 4.2E-05 5.7E-OS 1.3E-OS Child 2 'E-06 9.4E-06 2.2E-07 4.9E-06 2.2E-OS 2.5E-06 2.9E-06 1.3E-OS 5.7E-08 1.6E-05 7.0E-05 2.2E-05 Infant 1.6E-08 1.3E-07 2.2E-07 2.2E-06 1.8E-06 2.6E-06 2.2E-08 1.7E-07 5.8E-08 1.6E-07 1.0E-06 2.3E-OS

TABLE 6A ROCHESTER GAS & ELECTRIC CORPORATIOH GIHNA STATIOH NUMBER OF PERSOHHEL AND MAH-REM BY WORK AND JOB FUHCTIOH FOR 92/01/01

- 92/12/31 WORK PERMIT CATERGORY WORK GROUP ACTUAL WHOLE BODY DOSE HO.

OF CONTRACT WORKERS PERSOHHEL (P

STATION EMPLOYEES 100)

UTILITY EHPLOYEES CONTRACT WORKERS STAT IOH EMPLOYEES UTILITY EMPLOYEES TOTAL MAH-REM REACTOR OPERATIONS & SURV MAIHTEHANCE PERSOHNEL OPERATING PERSONNEL HEALTH PHY.

PERSONNEL SUPERVISORY PERSONNEL ENGIHEERIHG PERSONNEL 121 3

43 17 9

47 30 15 16 2

64 1

1 18 6

0'98 0.048 8.756 0.704 0.118 1.874 5.382 3.174 3.521 0 ~ 015 0.182 0.019 0.000 1.577 0.169 ROUT I HE MAINTENANCE MAIHTEHAHCE PERSOHHEL OPERATIHG PERSONNEL HEALTH PHD PERSONNEL SUPERVISORY PERSOHNEL ENGIHEERIHG PERSOHHEL 208 0

35

'l6 13 47 26 15 16 2

135 0

2 17 5

20.626 0.000 5.552 1.183 2.612 8.944 0.352 3.585 0.898 0.563 9.146 0.000 0.238 1.619 2.804 INSERVICE INSPECTION MAINTEHAHCE PERSOHHEL OPERATING PERSONNEL HEALTH PHY.

PERSONNEL SUPERVISORY PERSONNEL EHGIHEERIHG PERSONNEL 70 0

5 10 0

18 0

0 6

0 19.346 0.000 0.155 1.112 0.000 0'40 0.012 0.020 0.451 0.000 0.953 0.000 0.000 0.471 0.000 SPECIAL MAINTENAHCE MAINTENANCE PERSOHHEL OPERATING PERSONHEL HEALTH PHY.

PERSONHEL SUPERVISORY PERSONHEL EHGIHEERIHG PERSOHHEL 196 0

19 12 4

4'I 25 11 15 1

135 0

0 15 53.567 0.000 1.122 2.447 1.290 4.827 1.916 2 ~ 110 1.553 0.225 45.958 0.000 0.000 0.645 0.085 WASTE PROCESSING MAINTENANCE PERSONNEL OPERATING PERSOHHEL HEALTH PHY.

PERSOHNEL SUPERVISORY PERSONNEL EHGINEERIHG PERSOHNEL 22 0

1 0

0 0.169 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 REFUELIHG MAIHTEHAHCE PERSOHHEL OPERATING PERSONNEL HEALTH PHY.

PERSONNEL SUPERVISORY PERSONHEL ENGINEERING PERSONNEL 56 0

2 2

1 21 9

2 3

2 22 0

0 5

0 8.893 0.000 0.009 0.005 0.000 0.883 2.522 0.164 0.420 0.308 2.408 0 F 000 0.000 0.065 0.000 MODIFICATIONS TOTAL MAINTENANCE PERSOHHEL OPERATING PERSONNEL HEALTH PHY.

PERSOHHEL SUPERVISORY PERSONNEL EHGIHEERIHG PERSOHHEL MAINTENANCE PERSOHHEL OPERATIHG PERSONNEL HEALTH PHY.

PERSOHHEL SUPERVISORY PERSONHEL ENGIHEERIHG PERSONNEL 69 0

1 7

0 221 3

44 18 14 48 30 15 17 2

139 1

2 18 6

8.554 0.000 0.000 0.349 0.000 111.753 0.048 15.594 4.799 4.020 0.008 0.038 0.000 0.095 0.000 16.776 10.222 9.054 6.938 1 '11 0.370 0.000 0.000 0.995 0.010 59.017 0.019 0.238 5.372 3.069 44.101 67.715 GRAND TOTAL 294 109 163 137.214

Table 6B STANDARD REPORT OF PERSONNEL WHOLE BODY EXPOSURE 1992 DOSE REM NUMBER OF PEOPLE 00.000 00.001 00.101 00.251 00.501 00.751 01.001 02.001 03.001 04.001 00 F 000 00.100 00.250 00.500 00.750 01.000 02.000 03.000 04.000 05.000 818 288 165 185 108 56 30 0

0 0

Total number of personnel monitored 1650 The total collective dose for 1992 is 260.947 person-rem based on the sum of all personnel TLD badge readings.

FIVE HIGHEST EXPOSURES FOR THE YEAR A

B C

D E

1.573 rem 1.432 rem 1.430 rem 1.404 rem 1.403 rem This report contains all personnel mon'itored during 1992.