Text

Semiannual Radioactive Effluent Release Rept, Re Ginna Nuclear Plant
	ML17263A382
Person / Time
Site:	Ginna
Issue date:	06/30/1993
From:	Mecredy R; ROCHESTER GAS & ELECTRIC CORP.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9309090075
	Download: ML17263A382 (19)
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ACCELg$PgF+DQQJMENT DIS'fRIRUTION SYSTEM ALCESSION NBR:9309090075 DOC.DATE: 93/06/30 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

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION D

SUBJECT:

"Semiannual Radioactive Effluent Release Rept,"

RE Ginna Nuclear Plant.W/930827 ltr.

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IE48D COPIES RECEIVED:LTR g ENCL i SIZE:

TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports S

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 TELEPHONE AREA CODE. Tle 546-2700 August 27, 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 ruly yours, Robert C.

Mec edy Vice President 080084 9309090075 930630 PDR ADQCK 05000244 R

PDR

H 1

q t'

~,

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

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R.

E.

GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 JANUARY - JUNE, 1993

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 LIMITS OF DETECTION 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 12.0 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 Table Table Table Table Table 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

1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report is for Rochester Gas and Electric Corporation R.E.

Ginna Nuclear Power Plant and is submitted in accordance with the requirements of Technical Specification Section 6.9.1.4.

The report covers the period from January 1,

1993 through June 30, 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. Ginna Technical Specifications.

2.0 2.1 SUPPLEMENTAL INFORMATION 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 c 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.

2.1.3 (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 2.2.1 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 0.215 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 analyses 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 Liciu id 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:

1.70 E+02 4.51 E+04 min.

3.65 E+03 min.

2.66 E+02 min.

1.5 E+01 min.

9.94 E+05 lpm 2.5.2 Gaseous 1.

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:

1.9 E+01 5.97 E+04 min.

2.22 E+04 min.

3.14 E+03 min.

1.53 E+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.

Plant vent and containment vent releases are considered to be elevated while air ejector releases are considered to be ground level.

During the 1993 annual outage, the integrated leak rate test (ILRT) was performed.

During the

test, all radiation monitoring equipment associated with contain-ment building releases was removed from service to prevent it from being damaged.

While the excess pressure was being released, a small stream was run to a CAM for measurement of the release and grab samples were obtained to verify the CAN readings.

The quantity of radioactive gas released was calculated from the concentration and volume of the containment vessel prior to the pressurization.

The ILRT was performed late in the shutdown when there was very little activity remaining in the containment building.

4.0

SUMMARY

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

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

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

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

6.0 LOWER LIMIT OF DETECTION NOT MET One or more gamma emitting radionuclides did not meet the required lower limit of detection for 13 liquid releases.

These are listed by release number in Table

7.0 RADIOLOGICAL IMPACT 8.0 An assessment of doses to the maximally exposed indivi-dual from gaseous and liquid effluents will be performed and reported i.n the July

December, 1993 Semi-Annual Report.

METEOROLOGICAL DATA These data will be in the report issued for July-

December, 1993.

9.0 10.0 LAND USE CHANGES These data will be in the report issued for July-

December, 1993.

ANNUAL TABULATION OF PERSONNEL EXPOSURE These data will be in the report issued for July-

December, 1993.

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 report period.

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

ROCHESTER GAS ELECTRIC CORPORA ON Table 1A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY-JUNE 1993 A. Fission 8 activation ases Unit Quarter 1st Quarter 2nd Est. Total Error %

1. Total release