ML17262A756

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991

ML17262A756
Person / Time
Site:	Ginna
Issue date:	12/31/1991
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9203040298
Download: ML17262A756 (50)

Text

ACCELERATED DI~)TPJBUTION DEMONSTjWTION SYSTEM

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REGULRT INFORMATION DISTRIBUTIONISTEM (RIDE) e ~

ACCESSION NBR:9203040298 DOC.DATE: 91/12/31 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

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

Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept" for Jul-Dec 19914W/920228 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 S

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r ROCHESTER GAS AND ELECTRIC CORPORATION o 8g EAST AVENUE, ROCHESTER, N.Y. 1464g-P001 TELEPHONE AREA CODE TIE 546.2700 February 28, 1992 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,

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Robert C. Mecredy Vice President V 0S040~SB-SSC S~

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E.'INNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO ~ 50-244 JULY DECEMBER, 1991

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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 7.0 RADIOLOGICAL IMPACT 8.0 METEOROLOGICAL DATA 9.0 LAND USE CENSUS CHANGES 10.0 ANNUAL TABULATION OF PERSONNEL EXPOSURE llew 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

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LIST OF TABLES Table Table Table Table Table Table Table lA 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 5A Radiation Dose to Nearest Individual Receptor from Gaseous Releases Table Table 5B Radiation'Dose to Nearest Individual Receptor from Liquid Releases 6A Number of Personnel and Man-Rem by Work and Job Function Table Table Table 6B Standard Report of Personnel Whole Body Exposure 7A Liquid Effluents Summation of All Releases (Corrected Table for January - June, 1991) 7B Liquid Effluents Continuous and Batch Releases (Corrected Table for January - June, 1991)

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INTRODUCTION This Semiannual Radioactive -Effluent Release'eport 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,

1991 through December 31, 1991.

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 1.2lg Revision 1, June 1974.

Corrected forms for liquid effluents released during the January-June 1991 period are included as Tables 7A and 7B to show data that was not available when the earlier report was prepared.

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

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

2'.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.

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~ 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

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2.1.3 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 id 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:

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(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.

Maximum Permissible Concentrations MPC 2 ~ 2 ~ 1 2 '

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.

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.

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elease Rate Limits 2 ~ 4 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 0.230 Mev.

-.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.

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Batch Releases 2 ~ 5 ~ 1

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Number of batch releases:

Total time period for batch releases:'aximum 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:

2'1 E+02 2.93 E+04 min.

6.70 E+02 min.

1.17 E+02 min.

1.9'+00 min.

1.29 E+06 LPM 2 '

Gaseous 1.

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Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for baCch releases:

Minimum time period for a batch release:

2.8E+Ol 1.10E+05 min.

5.17E+04 min.

3.92E+03 min.

1.49E+02 min.

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

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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..

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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 type.

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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 5A and 5B.

8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1991 is not included with this report, but can be made available at the R.E.

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.

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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

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according to work and gob function recpxired by Technical Specification 6.9.2.2 and 10CFR20.407 is included as Tables 6A and 6B.

LEAK TEST OF SEALED SOURCES 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.

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ROCHESTER GAS ELECTRIC CORPORATION Table 1A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JULY - DECEMBER 1991 A. Fission & activation ases

1. Total release

2. Avera e release rate for eriod

3. Percent of technical s ecification limit Unit Ci uCi/sec Quarter 3rd 1.84E+02 2.32E+01 3.68E-03 Quarter 4th 2.01E+02 2.53E+01 4.02E-03 Est. Total Error, %

1.50E+01 B. Iodines

1. Total iodine-131

2. Avera e release rate for eriod

3. Percent of technical s ecification limit Ci 3.01E-04 uCi/sec 3.79E-05 8.33E-02 4.97E-05 2.50E+01 6.25E-06 1.37E-02 C. Particulates

1. Particulates with half-lives > 8da s

2. Avera e release rate for eriod

3. Percent of technical s ecification limit

4. Gross al ha radioactivit Ci uCi/sec Ci 1.81E-06 2.27E47 1.71E-05 4.50E+01 D. Tritium

1. Total release Ci 1.81E+01 2.22E+01 3.20E+00

2. Avera e release rate for eriod

3. Percent of technical s ecification limit uCi/sec 2.27E+00 2.68E-04 2.79E+00 3.28E-04 E. Carbon-14

1. Total release

2. Avera e release rate for eriod

3. Percent of technical s ecification limit Ci uCi/sec 7.44E-01 4.34E-01 9.36E-02 5.46E-02 4.98E-06 2.90E-06 3.00E+01 Note:

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

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ROCHESTER GAS ELECTRIC CORPORATION Table 1B EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - ELEVATEDRELEASE Continuous Mode Batch Mode Nuclides released 1.

Fission ases Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th ar on-41 kr ton-85 kr ton-85m kr ton-87 kr ton-88 xenon-131m xenon-133 xenon-133m xenon-135 xenon-135m xenon-138 others s eci Total for eriod Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 8.42E-02 2.68E-02 9.23E-02 1.13E+00 8.50E42 3.40E-02 1.51E-01 8.61E-01 1.27E-01 5.96E-02 3.70E+01 6.54E+01 3.34E-02 1.30E42 4.21E+01 1.97E+01 5.88E-01 2.16E-01 1.69E-01 6.54E-02 8.04E+01 8.76E+01 1.80E+00 1.78E+00 4.12E+00 1.22E+00 2.08E-01 2.05E-01 1.62E-02 1.76E-01 1.66E-01 1.57E+00 9.18E-01 9.14E+01 1.05E+02 1.91E+00 1.21E+00 2.78E+00 2.88E+00 1.04E+02 1.14E+02 2.

Iodines iodine-131 iodine-133 iodine-135 Ci 3.01E-04 4.97E-05 Ci 3.83E-04 1.33E-04 Ci 1.89E-08 5.53E-09 Total for eriod Ci 6.84E-04 1.83E-04 2.45E-08 3.

Particulates strontium-89 strontium-90 cesium-134 cesium-137 other s eci cobalt-58 cobalt-60 Total for eriod unidentified Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.81E-06 1.81E-06 1.19E-05 8.77E-06 Note:

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

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ROCHESTER GAS ELECTRIC CORPORATION Table 2A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES JULY - DECEMBER 1991 A. Fission and activation roducts Unit Quarter 3rd Quarter 4th Est. Total Error, %

1. Total release (not including tritium,

ases, al ha

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci 5.87E-02 uCi/ml 3.44E-10 2.29E42 2.79E-02 1.20E+01 1.63E-10 2.11E-03 B. Tritium 1 ~ Total release

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci 6.55E+01 6.07E+01 3.00E+00 uCi/ml 3.84E-07 3.56E-07 1.28E-02 1.19E-02 C. Dissolved and entrained ases

1. Total release Ci 2.22E-03 4.54E-03 2.60E+01

2. Average diluted concentration durin eriod

3. Percent of a licable limit uCi/ml 1.30E-11 2.66E-11 6.52E-06 1.33E-05 D. Gross al ha radioactivit

1. Total release Ci E. Vol. of waste released ( rior to dilution Liters 3.91E+07 2.47E+07 5.00E+00 F. Vol. of dilution water used durin eriod Liters 1.71E+11 1.71E+11 5.00E+00 Note:

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

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ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS Continuous Mode Batch Mode Nuclides Released chromium-51 man anese-54 iron-55 Unit Ci Ci Ci Quarter 3rd Quarter uarter 3rd Quarter 4.24E-05 iron-59 cobalt-58 cobalt-60 zinc-65 strontium-89 strontium-90 zirconium/niobium-95 mol odenum-99 silver-110m antinon -122 antinon -124 antinon -125 iodine-131 iodine-133 iodine-135 cesium-134 cesium-136 cesium-137 barium/lanthanum-140 cerium-141 other s eci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 9.17E-07 7.47E-04 5.50E-04 4.94E-05 1.12E-04 6.73E-05 5.04E-05 4.38E-05 1.36E-04 3.74E-06 2.52E-06 2.75E-04 1.48E-04 1.47E-04 7.64E-06 3.01E-04 2.55E-04 8.33E-08 4.23E-04 1.79E-05 1.20E-05 1.82E-03 6.58E-04 1.45E-04 8.35E-05 1.22E-04 7.53E-03 3.46E-04 4.56E-03 1.31E-06 1.85E-03 1.92E-02 1.29E-02 3.39E-03 1.67E-02 1.37E-02 1.96E-04 Total for eriod (above) unidentified Ci Ci 1.87E-03 3.12E-04 5.68E-02 2.76E-02 xenon-133 xenon-135 Ci Ci 1.82E-03 4.41E-03 4.02E-04 1.34E-04 Note:

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

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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) 6-month

( Est. Total Unit Period Error m

[1.37 E+Ol) 2.0E+00 Ci 3.02 E-03 2.0E+01 m

• I 1 ~ 48 E+Oll 2 ~ OE+00 Ci*

4.64 E-03 2.0E+Ol mCi mci

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

H-3 Zn-65 Cs-137 Co-60 Sb-124 Cs-134 Co-58 Fe-55

'i-63 Sb-125 Mn-54 b.Cs-137 Co-60 Ni-63 Co-58 Cs-134 Sr-90 Sb-125 4.76 E+Ol 9.25 E+00 8.85 E+00 8.06 E+00 7.07 E+00 6.24 E+00 4.03 E+00 3.42 E+00 2.32 E+00 1.04 E+00 1.35 E+00 1.94 E+Ol 1.55 E+Ol 1.32 E+01 7.08 E+00 6.71 E+00 2.23 E+00 1.16 E+00 Volume and activity buried'by waste processor during this period.

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

• • Shipped 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

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Table 4

RELEASE PERMITS NOT MEETING LLD REQUIREMENTS No.

None Date Isoto es Cause

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TABLE 5A RADIATION DOSES TO NE'%REST INDIVIDUALRECEPTOR FROM GASEOUS RELEASES IN REM 1991 QUARTER 1 Adult Teen Child Infant

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i iTotal Direction Bod Skin Th oid Bod Skin Th oid Bod Skin Th oid Bod Skin Th oid N

6.9E-8 1.2E-7 7.5E-8 7.1E-8 1.2E-7 7.8E-8 7.2E-8 1.2E-7 8.0E-8 6.2E-8 1.2E-7 6.9E-8 NNE 6.1E-8 8.8E-8 6.4E-8 6.2E-8 8.8E-8 6.'5E-8 6.0E-8 8.8E-8 6.4E-8 5.0E-8 8.8E-8 5.4E-8 NE 9.2E-8 1.4E-7 9.6E-8 9.3E-8 1.4E-7 9.8E-8 9.0E-8 1.4E-7 9.6E-8 7.7E-8 1.4E-7 6.2E-8 ENE 9.4E-8 1.4E-7 1.0E-7 9.5E-8 1.4E-7 1-1E-7 9.3E-8 1.4E-7 1.1E-7 7.8E-8 1.4E-7 9.0E-8 E

7.0E-7 1.5E-6 8.0E-7 7.1E-7 1.5E-6 8.4E-7 6.9E-7 1.5E-6 8.4E-7 6.0E-7 1.5E-6 7.3E-7 ESE 8.4E-7 1.6E-6 8-8E-7 8-5E-7 1.6E-6 9.0E-7 8.3E-7 1.6E-6 8.9E-7 7.1E-7 1.6E-6 7.7E-7 SE 3.7E-7 4.9E-7 3.9E-7 3.8E-7 4-9E-7 4.0E-7 3.7E-7 4.9E-7 3.9E-7 3.0E-7 4.9E-7 3.3E-7 SSE 3.7E-7 5.3E-7 3.8E-7 3.8E-7 5.3E-7 4.0E-7 3.8E-7 5.3E-7 4.0E-7 3.2E-7 5.3E-7 3.3E-7 S

7.1E-7 1.2E-6 8.1E-7 8.1E-7 1.2E-6 8.4E-7 8.1E-7 1.2E-6 8.4E-7 6.9E-7 1.2E-6 7.1E-7 SSW 6.9E-7 9.7E-7 7-1E-7 7.3E-7 9.7E-7 7.5E-7 7.4E-7 9.7E-7 7.6E-7 6.2E-7 9.7E-7 6.4E-7 SW 8.6E-7 1.2E-6 9-7E-7 8.8E-7 1.2E-6 1.0E-6 8.7E-7 1.2E-6 1.0E-6 7.4E-7 1.2E-6 8.9E-7 WSW 3.5E-7 5.2E-7 3-8E-7 3.6E-7 5-2E-7 4.0E-7 3-7E-7 5.2E-7 4.1E-7 3.2E-7 5-2E-7 3.5E-7 W

1.3E-7 1.9E-7 1.5E-7 1.4E-7 1.9E-7 1.5E-7 1.3E-7 1.9E-7 1.5E-7 1.1E-7 1.9E-7 1.5E-7 WNW 5-OE-8 6-2E-8 6.3E-8 5-2E-8 6.2E-8 6.8E-8 5.1E-8 6.2E-8 6.9E-8 4.2E-8 6.2E-8 5.8E-8 NW 3.2E-8 4.3E-8 3.7E-8 3.2E-8 4.3E-8 3.8E-8 3.1E-8 4.3E-8 3.8E-8 2.6E-8 4.3E-8 3.2E-8 NNW 5.9E-8 8.0E-8 6.7E-8 6.0E-8 8.0E-8 6.9E-8 5.8E-8 8.0E-8 6.8E-8 4.7E-8 8.0E-8 5.7E-8

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TABLE 5A RADIATION DOSES TO NEAT%ST INDIVIDUALRECEPTOR FROM GASEOUS RELE'USES IN REM 1991 QUAEKZR 2

Adult, Teen Child Infant

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/Total Direction Bod Skin Th oid Bod Skin Th oid Bod Skin Th oid Bod Skin Th oid N

5.4E-8 4.5E-8 6.4E-8 5.5E-8 4.5E-8 6-9E-8 5.4E-8 4.5E-8 6.9E-8 4.1E-8 4.5E-8 5.4E-8 NNE 6.8E-8 6.2E-8 7.7E-8 7.0E-8 6.2E-8 8.1E-8 6.8E-8 6.2E-8 8.0E-8 5.2E-8 6.2E-8 6.3E-8 NE 6.7E-8 5.0E-8 7.7E-8 7.0E-8 5.0E-8 8.2E-8 6.9E-8 5.0E-8 8.2E-8 5.0E-8 5.0E-8 6.3E-8 ENE 5.3E-8 3.6E-8 6.0E-8 5.5E-8 3.6E-8 6-3E-8 5-2E-8 3.6E-8 6.1E-8 3.8E-8 3.6E-8 4.6E-8 E

1.3E-8 9.8E-7 1.5E-6 1.6E-8 1.2E-6 1.8E-6 2-5E-6 2.0E-6 2.8E-6 1.3E-8 1.2E-6 1.5E-6 ESE 9.2E-7 8.1E-7 1.0E-6 1.1E-6 9.6E-7 1.2E-6 1.8E-6 1.5E-6 2.0E-6 1.5E-6 1.4E-6 1.7E-6 SE 6.7E-7 6.9E-7 7.1E-7 7.8E-7 7.7E-7 8.3E-7 1.1E-6 1.1E-6 1.2E-6 9.2E-7 9.6E-7 1.0E-6 SSE 6'E-7 6.1E-7 6 'E-7 7 'E-7 7 'E-7 7.7E-7 1.1E-6 1-OE-6 1-2E-6 1.1E-6 1.1E-6 1.2E-6 S

1.3E-6 1.3E-6 1.5E-6 1.6E-6 1.5E-6 1.8E-6 2.6E-6 2.3E-6 2.9E-6 1.9E-6 1.9E-6 2.2E-6 SSW 1.3E-6 1.4E-6 1.4E-6 1.5E-6 1.6E-6 1-7E-6 2.4E-6 2.3E-6 2.6E-6 2.0E-6 2.1E-6 2.2E-6 SW 3.8E-6 3.7E-6 4.2E-6 5.2E-6 5.0E-6 5.6E-6 1.0E-5 9.7E-6 1.1E-5 1.5E-5 1.5E-5 1.6E-5 WSW 1.9E-6 1.7E-6 2.0E-6 2.4E-6 2.2E-6 2-6E-6 4.5E-6 4.1E-6 4.7E-6 5.8E-6 5.5E-6 6.0E-6 W

3.0E-7 2.3E-7 3.5E-7 3.6E-7 2.7E-7 4 3E-7 5.5E-7 4.2E-7 6.3E-7 3.9E-7 3.4E-7 4.7E-7 WNW 2.2E-7 2.3E-7 2.7E-7 2-4E-7 2.3E-7 3.0E-7 2.6E-7 2.4E-7 3.3E-7 2.1E-7 2.3E-7 2.8E-7 NW 2.2E-8 1.3E-8 2.5E-8 2.3E-8 1.3E-8 2.7E-8 2.3E-8 1.3E-8 2.7E-8 1.7E-8 1.3E-8 2.0E-8 NNW 2.6E-8 1.5E-8 3.1E-8 2.7E-8 1.5E-8 3-4E-8 2-6E-8 1.5E-8 3.4E-8 1.9E-8 1.5E-8 2.6E-8

1 4

r

~

lp e

v

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~

TABLE 5A RADIATION DOSES TO NEAEKST INDIVIDUALRECEPTOR FROM GASEOUS RELEASES IN REM 1991 QUARTER 3 Adult Teen Child Infant

)Total f

/

]Total J

f

]Total Direction Bod Skin Th oid Bod Skin Th oid Bod

/Total Skin Th oid Bod Skin Th oid N

1.7E-7 3.4E-7 1.7E-7 1.7E-7 3.4E-7 1.7E-7 1.7E-7 3.4E-7 1.7E-7 1.5E-7 3-4E-7 1.5E-7 NNE 1-3E-7 2.4E-7 1.3E-7 1.3E-7 2-4E-7 1.4E-7 1.3E-7 2.4E-7 1.3E-7 1.2E-7 2.4E-7 1.2E-7 NE 1-3E-7 2.4E-7 1.3E-7 1.3E-7 2.4E-7 1.3E-7 1-3E-7 2-4E-7 1-3E-7 1.2E-7 2.4E-7 1.2E-7 ENE 9-8E-8 1.7E-7 9.9E-8 1.0E-7 1.7E-7 1.0E-7 1-OE-7 1-7E-7 1.0E-7 8-8E-8 1.7E-7 9.0E-8 E

1-5E-6 2.2E-6 1.8E-6 1.9E-6 2.5E-6 2.1E-6 3-1E-6 3.6E-6 3-5E-6 1.6E-6 2.4E-6 2.1E-6 ESE 2.4E-6 3.0E-6 2.8E-6 3.1E-6 3.7E-6 3.6E-6 5.9E-6 6.3E-6 6.6E-6 3-6E-6 4.3E-6 4.4E-6 SE 1.2E-6 1.5E-6 1.3E-6 1-6E-6 1.9E-6 1.7E-6 3.0E-6 3.2E-6 3.2E-6 1.5E-6 1-9E-6 1.9E-6 SSE 1.7E-6 2.2E-6 1.8E-6 2.2E-6 2.7E-6 2.3E-6 4.0E-6 4.4E-6 4.3E-6 3.3E-6 3-9E-6 3.7E-6 S

2-9E-6 4.8E-6 3.1E-6 3.4E-6 5.3E-6 3.6E-6 5.3E-6 7.0E-6 5.8E-6 4.6E-6 6.5E-6 5.2E-6 SSW 1-2E-6 1.7E-6 1-2E-6 1.3E-6 1.9E-6 1.4E-6 2-1E-6 2.5E-6 2.2E-6 1.8E-6 2.3E-6 2.0E-6 SW 2.0E-6 3.2E-6 2.1E-6 2.3E-6 3.5E-6 2.5E-6 3.6E-6 4.6E-6 3.9E-6 3.2E-6 4.4E-6 3.7E-6 WSW 6.7E-7 8.4E-7 6.9E-7 8.3E-7 9.8E-7 8.5E-7 1.4E-6 1.5E-6 1.5E-6 1-3E-6 1.4E-6 1.4E-6 W

3-1E-7 3.8E-7 3.2E-7 3.9E-7 4.5E-7 4.0E-7 7.1E-7 7.3E-7 7.2E-7 4.3E-7 5.1E-7 4.6E-7 WNW 6-1E-8 1.2E-7 6.1E-8 6.2E-8 1.2E-7 6.2E-8 6.6E-8 1.2E-7 6.6E-8 5.8E-7 1.2E-7 5.8E-8 NW 8.6E-8 1.9E-8 8.6E-8 8.7E-8 1.9E-8 8.7E-8

= 8.7E-8 1.9E-8 8-7E-8 8.1E-8 1-9E-8 8.2E-8 NNW 9.1E-8 1.7E-8 9.2E-8 9.4E-8 '1.7E-8 9.5E-8 9.5E-8 1.7E-8 9.6E-8 8.4E-8 1.7E-8 9.5E-8

TABLE 5A RADIATION DOSES TO NEAREST INDIVIDUALRECEPTOR FROM GASEOUS RELEASES IN REM 1991 QUARTER 4 Adult Teen Child Infant

/Total

/

/

/Total

/

/

(Total

/

/

/Total Direction Bod Skin Th oid Bod Skin Th oid Bod Skin Th oid Bod Skin Th oid N

1.5E-7 2-6E-7 1.5E-7 1.5E-7 2.6E-7 1.5E-7 1.5E-7 2.6E-7 1.5E-7 1.3E-7 2.6E-7 1.3E-7 NNE 1.6E-7 2.9E-7 1.6E-7 1.6E-7 2.9E-7 1.6E-7 1.6E-7 2.9E-7 1.6E-7 1.4E-7 2.9E-7 1.4E-7 NE 1.6E-7 3.0E-7 1.6E-7 1.6E-7 3.0E-7 1.6E-7 1.6E-7 3.0E-7 1.6E-7 1.4E-7 3.0E-7 1.5E-7 ENE 1.2E-7 2.3E-7 1.2E-7 1.2E-7 2.3E-7 1.2E-7 1.2E-7 2.3E-7 1.2E-7 1.1E-7 2.3E-7 1.1E-7 E

1.5E-6 2.5E-7 1.6E-7 1.6E-7 2.6E-7 1.7E-7 1.9E-6 2.8E-7 2.0E-7 1.4E-6 2-6E-7 1.5E-7 ESE 9.8E-7 1.5E-6 1.0E-6 1.0E-6 1.5E-6 1.1E-6 1.3E-6 1.7E-6 1.4E-6 8.6E-7 1.5E-6 1.0E-6 SE 1-2E-6 2.0E-6 1.2E-6 1.2E-6 2.1E-6 1.2E-6 1.3E-6 2.2E-6 1.4E-6 1.2E-6 2.2E-6 1.3E-6 SSE 4.5E-7 7.0E-7 4.6E-7 4.7E-7 7.1E-7 4.8E-7 5.3E-7 7.7E-7 5.5E-7 4.3E-7 7.3E-7 4.6E-7 S

9.6E-7 1.4E-6 1.0E-6 1.0E-6 1.5E-6 1.1E-6 1.3E-6 1.7E-6 1.4E-6 8.8E-7 1.5E-6 1.0E-6 SSW 5.9E-7 9.5E-7 6.1E-7 6.3E-7 9.8E-7 6.4E-7 7.3E-7 1.1E-6 7.7E-7 5.2E-7 9.6E-7 5.6E-7 SW 1.2E-6 2.2E-6 1.3E-6 1.3E-6 2.3E-6 1.4E-6 1.7E-6 2.6E-6 1.8E-6 1.1E-6 2-2E-6 1.2E-6 WSW 5.2E-7 7.3E-7 5.4E-7 6.2E-7 8.2E-7 6.5E-7 1.0E-6 1.2E-6 1.0E-6 4.8E-7 7.4E-7 5.6E-7 W

6.4E-7 1.2E-6 6.4E-7 6.7E-7 1.3E-6 6.8E-7 S.OE-7 1.4E-6 8.1E-7 6.3E-7 1.3E-6 6.5E-7 WNW 1.4E-7 2.9E-7 1.4E-7 1.5E-7 2.9E-7 1.5E-7 1.7E-7 3.1E-7 1.7E-7 1.2E-7 2.8E-7 1.2E-7 NW 8.1E-S 1-7E-7 8.2E-8 8.3E-8 1.7E-7 8.3E-8 8.3E-8 1.7E-7 8.4E-S 7.7E-8 1-7E-7 7.8E-8 NNW 1.1E-7 2.1E-7 1.1E-7 1.1E-7 2.1E-7 1.1E-7 1.1E-7 2.1E-7 1.1E-7 9.7E-8 2.1E-7 9.9E-8

H I

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TABLE 5B RADIATION DOSE TO NEAREST 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 3.9E-5 2.8E-5 5.7E-6 2.0E-5 1.4E-5 1.3E-6 6 'E-5 4.7E-5 4 'E-6

4. 5E-5 3.3E-5 9.0E-7 Teen 2 'E-5 3.0E-5 4 'E-6

1. 1E-5 1.5E-5 1.0E-6 3 'E-5 4.9E-5 3 'E-6 2 'E-5 3.5E-5 6.7E-7 Child 1.1E-5 3 'E-5 8.0E-6 5.3E-6 1.9E-5 1.8E-6 1.6E-5 6 'E-5 6 'E-6

1. 1E-5 4 'E-5 1 ~ 2E-6 Infant 2 'E-6 5 'E-7 8 'E-6

1. 1E-6'

'E-7 1.7E-6 1.3E-6 1 ~ 5E-6 6 'E-6 9 'E-7 5.8E-4 1.2E-6

V

Table 6A PROG:

RDHS002

[28A]

DATE: 92/02/10 ROCHESTER GAS & ELECTRIC CORPORATION GINNA STATION NUMBER OF PERSONNEL AND HAH-REM BY WORK AND JOB FUNCTION FOR 91/01/01. 91/'l2/31 PAGE:

1 TIME: 11:36:53 ACTUAL WHOLE BODY DOSE HO.

OF PERSOHHEL (> or =

100)

TOTAL MAN-REM WORK PERMIT CATERGORY REACTOR OPERATIONS & SURV WORK GROUP MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHY.

PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL CONTRACT WORKERS 172 3

54 27 9

38 25 12 17 1

82 2

4 12 1

STATION UTILITY EMPLOYEES ENPLOYEES CONTRACT WORKERS 1.314 1.349 17.264 0.654 0.102 STATION EMPLOYEES 1.476 5.642 2.226 2.817 0.030 UTILITY EMPLOYEES 0.134 0.466 0.288 0.297 0.000 ROUTINE MAIN'IEHANCE MAINTENANCE PERSONNEL OPERATING PERSOHNEL, HEALTH PHY.

PERSOHHEL SUPERVISORY PERSONNEL EHGINEERIHG PERSONNEL 248 2

52 26 7

41 21 9

17 1

164 1

4 12 1

45.933 0.014 8.296 2.096 0.312 9.170 0.578 1 ~ 206 1.772 0.001 16.504 0.005 0.174 2.733 0.000 INSERVICE INSPECTION MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHY.

PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL 33 0

4 10 0

4 2

, 0 6

0 39 0

0 10 0

1 '55 0 ~ 000 0.086 0.727 0.000 0.178 0.042 0.000 0.713 0.000 3.034 0.000 0.000 0.875 0.000 SPECIAL MAINTENANCE MAINTEHANCE PERSONNEL OPERATING PERSONNEL HEALTH PHY.

PERSOHNEL SUPERVISORY PERSONNEL ENGINEERING PERSOHNEL 258 2

30 21 8

39 20 5

15 161 2

2 12 1

74.011 0.008 1.162 5.148 0.788 6.795 0.668 0.089 0.550 0.000 52.814 0.167 0.125 3.123 0.014 WASTE PROCESSING MAINTENANCE PERSOHHEL OPERATING PERSONNEL HEALTH PHY.

PERSONNEL SUPERVISORY PERSOHHEL ENGIHEERIHG PERSONNEL 12 0

5 2

0 0.500 0.000 0'71 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.008 0.000 0.000 0.000 0.000 REFUELIHG MAINTENANCE PERSOHNEL OPERATING PERSOHHEL HEALTH PHY.

PERSOHHEL SUPERVISORY PERSOHHEL ENGIHEERING PERSOHHEL 79 0

3 9

0 17 6

2 2

0 27 1

0 1

9.418 0.000 0.143 0.282 0.000 0.850 1.780 0.040 0.258 0.000

'.427 0.034 0.000 0.179 0.283 MODIFICATIONS MAINTENANCE PERSOHHEL OPERATING PERSONNEL HEALTH PHY. PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL 109 0

0 19 5

12 1

0 4

1 18.970 0.000 0.000 1.762 0.188 0.095 0.000 0.000 0.348 0.072 0.662 0.000 0.000 0.184 0.000 TOTAL MAINTENANCE PERSONNEL OPERATING PERSONHEL HEALTH PHD PERSOHHEL SUPERVISORY PERSOHHEL EHGIHEERIHG PERSONNEL 273 3

54 30 9

41 25 12 18 1

164 2

4 12 1

151.700 1.371 27.122 10.670 1.390 18.564 8.711 3.561 6.458 0.103 75.582 0.672 0.587 7.391 0.297 GRAND TOTAL 367 94 192.253 37.397 84.529

i, r

Table 6B STANDARD REPORT OF PERSONNEL WHOLE BODY EXPOSURE 1991 DOSE REM NUMBER OF PEOPLE 00.000 - 00.000 00.001 - 00.100 00.101 - 00.250 00.251 - 00.500 00.501 - 00.750 00.751 01.000 01.001 02.000 02.001 03.000 03.001 04.000 04.001 - 05.000 05.001 06.000 06.001 07.000 07.001 - 08.000 08 F 001 09.000 09.001 10.000 10.001 - 11.000 11.001 12.000 12.001 99.999 889 320 182 198 113 71 63 0

0 0

0 0

0 0

0 0

0 0

Total number of personnel monitored 1836 The total collective dose for 1991 is 328 person-rem based on the sum of all personnel TLD badge readings.

FIVE HIGHEST EXPOSURES FOR THE YEAR A

B C

D E

1.990 1.902 1.892 1.862 1.735 This report contains all personnel monitored during 1991.

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ll I

ROCHESTER GAS ELECTRIC CORPORATION Table 7A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT CORRECTEDREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY-JUNE 1991 A. Fission and activation roducts Unit Quarter 1st Quarter 2nd Est. Total Error

1. Total release (not including tritium,

ases, al ha

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci uCi/ml 4.27E-02 2.30E-02 3.23E-10 1.95E-10 2.41E-02 4.14E-03 5.60E+00 B. Tritium

1. Total release

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci uCi/ml 1.75E+02 7.47E+01 1.32E-06 6.36E-07 4.41E-02 2.12E-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

'Ci/ml 8.53E-02 6.46E-10 3.23E-04 2.14E-02 6.00E+00 1.82E-10 9.11E-05 D. Gross al ha radioactivit

1. Total release Ci E. Vol. of waste released ( rior to dilution Liters 3.10E+07 2.26E+07 F. Vol. of dilution water used durin eriod Liters 1.32E+11 1.17E+11 Note:

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

~la

ROCHESTER GAS ELECTRIC CORPORATION Table 7B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS CORRECTED REPORT Continuous Mode Batch Mode Nuclides Released Unit Quarter 1st Quarter 2nd Quarter 1st Quarter 2ild chromium-51 man anese-54 iron-55 iron-59 cobalt-58 cobalt-60 zinc-65 strontium-89 strontium-90 zirconium/niobium-95 mol bdenum-99 silver-110m antinon -122 antinon -124 antinon -125 iodine-131 iodine-133 iodine-135 cesium-134 cesium-136 cesium-137 barium/lanthanum-140 cerium-141 other s eci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.43E-05 1.13E-07 7.05E-05 7.82E-05 2.72E-04 7.40E-05 1.69E-04 3.57E-05 2.16E-05 2.27E-05 1.30E-04 1.61E-04 1.79E-04 2.41E-04 2.82E-04 6.79E-05 7.77E-05 2.31E-06 3.89E-03 5.07E-03 1.05E-03 1.45E-03 6.31E-07 1.06E-04 4.08E-05 1.03E-05 5.65E-05 6.70E-05 1.73E-05 2.11E-04 1.49E-03 2.03E-04 1.22E-03 2.78E43 8.27E-05 2.39E-04 7.62E-03 9.15E-04 3.09E-03 5.79E-04 9.88E-03 5.15E-03 2.58E-04 1.22E-02 5.83E-03 1.76E-04 7.40E-05 Total for eriod (above) unidentified Ci Ci 7.72E-04 6.97E-04 4.20E-02 2.23E-02 xenon-133 xenon-135 Ci Ci 2.74E-05 8.17E-02 2.14E-02 3.61E-03 Note:

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

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