ML17263A768

Semiannual Radioactive Effluent Release Rept for Jan-June 1994

ML17263A768
Person / Time
Site:	Ginna
Issue date:	06/30/1994
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9409130176
Download: ML17263A768 (19)

Text

P RIGRITY 1 ACCELERATED RIDS PROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

J4lh%t98 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

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

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000244

SUBJECT:

"Semiannual

'oactive effluent Release Rept for Jan-June 1994."

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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).

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g s(zpi I zzzzziz i,/j/IIjism/ ZXZZm ROCHESTER GAS AND ELECTRIC CORPORATION ROBERT C MECREDY Vice Prertdent Clnnn Nudeer Production Nkv L44r OWI ~ R o

89 EAST AVENUE, ROCHESTER N.K 1464S-0001 TELEPNONE AREACODE 71B 546 2700 August 30, 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, Robert C. Mecred Vice President 000'7 9409130176 940630 PDR ADOCK 05000244

. R PDR

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

SEMIANNUALRADIOACTIVEEFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 JANUARY - JUNE, 1994

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 ABNORMALRELEASES 3.0

SUMMARY

OF GASEOUS RADIOACTIVEEFFLUENTS 4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTE 6.0 LOWER LIMITOF DETECTION 7.0 RADIOLOGICALIMPACT 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 CALCULATIONMANUAL 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 Table 2A Liquid Effluents - Summation of all Releases 2B Liquid Effluents - Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments

1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report is for 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 January 1, 1994 through June 30, 1994.

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 < 5 mrad for gamma radiation and to < 10 mrad for beta radiation.

(ii)

During any calendar year to < 10 mrad for gamma radiation and to < 20 mrad for beta radiation.

2.1

~ 2 Radioiodine Tritium and Particulates The instantaneous dose

rate, as calculated in the ODCM, due to radioactive materials released in gaseous effluents from the site as radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days shall be limited to a release rate which would yield < 1500 mrem/yr to any organ if allowed to continue for a full year.

The dose to an individual, as calculated in the ODCM, from radioiodine, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days released with gaseous effluents from the site shall be limited to the following:

(i)

During any calendar quarter to ( 7.5 mrem to any organ.

(ii)

During any calendar year to ( 15 mrem to any organ.

2.1.3 Li uid Effluents The release of radioactive liquid effluents shall be such that the concentration in the circulating water, discharge does not exceed the limits specified in accordance with Appendix B, Table II, Column 2 and notes thereto of 10CFR20.

For dissolved or entrained noble gases the total activity due to dissolved or entrained noble gases shall not exceed 2 E-4 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 to 20.1-20.602, Table II, column 2,

1-1-93, 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 0.249 Mev.

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

'nd Fe-55 by a contract laboratory.

Tritium and alpha analysis were done using liquid scintillation and gas flowproportional 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.

2.5 Batch Releases 2.5.1 Li<iuid 1.

2.

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:

1.76 E+02 6.39 E+04 min.

7.39 E+03 min.

3.63 E+02 min.

1.6 E+01 min.

9.94 E+05 Ipm 2.5.2 Gaseous 1.

2.

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:

2.8 E+01 8.78 E+04 min.

3.83 E+ 04 min.

3.14 E+03 min.

8 E+00 min.

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 ground level releases.

4.0

SUMMARY

OF LIQUID RADIOACTIVEEFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 2B.

5.0 SOLID 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 LIMITOF DETECTION NOT MET All counting was done for time periods that met the required LLD for the equipment and the selected isotopes given in the Technical Specifications for each specific geometry used.

7.0 RADIOLOGICALIMPACT An assessment of doses to the maximally exposed individual from gaseous and liquid effluents will be performed and reported in the July-December, 1994 Semi-Annual Report.

8.0 METEOROLOGICAL DATA This data will be in the report issued for July - December, 1994.

9.0 10.0 11.0 LAND USE CHANGES This data will be in the report issued for July - December, 1994.

ANNUALTABULATIONOF PERSONNEL EXPOSURE This data will be in the report issued for July - December, 1994.

LEAK TEST OF SEALED SOURCES 1 2.0 1 3.0 No sealed sources were found to be leaking when smeared by both wet and dry smears.

CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL (ODCM)

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

CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

The PCP was completely rewritten during this report period. A copy of the new PCP is attached.

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

OCHESTER GAS ELECTRIC CORPORATI Table 1A EFFLUENT,ANDNASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY-JUNE 1994 A. Fission &activation gases Unit Quarter 1st Quarter 2nd Est. Total Error,%

1. Total release

2. Avera e release rate for eriod Cl 2.05E+01 7.79E+00 uCi sec 2.64E+00 9.90E41 9.50E+00

3. Percent of technical s ecification limit B. Iodlnes

1. Total iodine-131 CI 9.71E45 2.33E45 4.19E44 1.57E44 3.50E+01

2. Avera e release rate for eriod

3. Percent of technical s ecification limit C. Particulates uCi sec 1.25E45 2.74E42 2.96E46 6.51E43

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 D. Tritium Ci uCI sec Ci 1.52E46 2.47E46 4.00E+01 1.95E47 3.15E47 1.47E45 2.37E45

1. Total release

2. Avera e release rate for eriod

3. Percent of technical s ecification limit Cl 9.88E+00 6.79E+00 uCi sec 1.27E+00 8.63E41 1.49E44 1.02E-04 3.20E+00 E. Carbon-14

1. Total release

2. Avera e release rate for erlod

3. Percent of technical s ecification limit Ci 9.59E41 uCI sec 1.23E41 6.56E-06 1.23E+00 3.00E+01 1.56E41 8.31E46 Note:

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

OCHESTER GAS ELECTRIC CORPORAT Table 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - ELEVATEDRELEASE Nuclides released 1.

Fission gases ar on41 Unit Ci 1.66E41 1.31E41 1.82E41 3.30E-02 Continuous Mode Batch Mode Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd k

ton%5 k

ton%5m Ci Ci 2.77E42 1.69E-02 9.53E42 6.52E44 8.07E42 k

ton%7 k

ton%8 xenon-131m Cl 4.18E42 Cl 5.26E42 CI 2.80E42 3.37E42 1.32E42 1.53E43 2.10E43 8.38E42 5.68E-03 xenon-133 CI 6.89E+00 4.50E+00 1.09E+01 2.69E-01 xenon-1 33m xenon-135 xenon-135m CI 6.79E43 CI 1.18E+00 Ci 4.75E41 8.49E44 2.23E+00 3.21E41 9.97E42 6.86E42 1.75E42 2AOE44 5.40E43 xenon-138 others s eci Total for eriod 2.

Iodlnes Ci Ci CI Ci CI Ci 1.76E41 9.02E+00 1.16E41 7.39E+00 6.40E43 1.15E+01 3.93E41 iodine-131 Iodine-133 Iodine-135 Total for eriod 3.

Particulates strontium%9 strontium-90 CI CI Ci Ci Ci CI 8.72E45 1.02E44 1.89E44 1.45E-05 1.98E45 3.44E45 1.85E47 9.92E46 8.78E46 1.46E-05 2.65E45 2.45E45 3.53E45 cesium-134 cesium-137 Nb-95 cobalt-58 cobalt%0 Total for eriod unidentified Ci Ci Ci CI CI CI Ci 1.52E46 2.29E46 1.52E46 2.47E46 Note:

Isotope forwhich no value is given were not identified In applicable releases.

0 v

I OCHESTER GAS ELECTRIC CORPORATI Table 2A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY-JUNE 1994 A. Fission and activation roducts Unit Quarter 1st Quarter 2nd Est. Total Error, %

1. Total release (not including tritium, ases,ai ha

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci uCi ml 2.83E42 2.82E-10 1.32E42 2.71E42 1.80E+01 1.90E-10 1.10E42 B. Tritium

1. Total release

2. Average diluted concentration durin eriod

3. Percent of a licable limit Ci 5.39E+01 4.65E+01 3.20E+00 uCi ml 5.38E47 3.26E47 1.79E42 1.09E42-C. Dissolved and entrained gases

1. Total release

2. Average diluted concentration durin eriod

3. Percent of a Ilcable limit Ci uCI ml 4.52E43 4.51E-11 2.25E45 2.15E43 2.80E+01 1.51E-11 7.54E46 D. Gross al ha radioactivit

1. Total release Ci N A E. Vol. ofwaste released riorto dilution Liters 3.44E+07 2.80E+07 5.00E+00 F. Vol. of dilution water used durin eriod Liters 1.00E+11 1.43E+11 5.00E+00 Note:

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

OCHESTER GAS ELECTRIC CORPORATI Table 2B EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS Nuclides Released Unit Continuous Mode Quarter Quarter Batch Mode Quarter Quarter chromium-51 Ci 1st 2nd 1st 2nd 4.10E46 man anese-54 iron-55 iron-59 cobalt-58 cobalt%0 zinc~

strontium%9 strontium-90 zirconium niobium-95 mol bdenum-99 silver-110m antinon -122 antinon -124 antinon -125 CI Ci Ci Ci CI Ci CI Ci CI CI CI Ci CI CI 3.52E47 9.89E45 2.56E46 4.31E44 6.38E45 6.44E-04 4.86E-05 4.39E-05 1.54E-05 6.46E45 7.44E44 6.22E-04 8.05E-05 1.11E44 1.95E44 2.80E44 5.38E-06 5.50E45 5.46E46 3.16E-05 4.00E45 2.00E44 2.74E-03 1.24E%3 2.09E%3 Iodine-131 Iodine-133 iodine-135 cesium-134 cesium-136 cesium-137 barium lanthanum-1 40 cerium-1 41 Te-123m Ru-103 CI CI Ci Ci Ci CI Ci Ci CI CI 1.14E44 1.20E-04 9.64E45 1.32E44 2.91E45 3.24E45 2.01E44 1.43E44 1.84E-04 2.63E44 2.17E45 1.82E%3 1.57E43 2.54E43 4.74E43 2.79E-03 5.45E43 8.83E43 3.52E43 4.00E43 4.24E%3 3.51E43 9.64E45 2.58E-04 8.42E44 Total for eriod above unidentified Ci Ci 1.18E-03 1.45E43 2.71E-02 2.57E-02 xenon-133 xenon-1 35 Ci Ci 6.97E45 3.87E43 9.88E44 5.78E44 1.16E43 Note:

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

'C a j I

V

Table 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January - June 1994 A.

SOLID WASTE SHIPPED OFFSITE FOR BURIALOR DISPOSAL -

(Not irradiated fuel) 1

~

Type of waste Unit 6 month period Est. total Error a.

Spent resins, filter sludges, evaporator bottoms, etc.

b.

Dry compressible waste, contaminated equip, etc.

m Ci m'i 3.66 E+01 8.73 E+01 1.88 E+02 1.27 E+00 7.0 E+00 7.0 E+00 7.0 E+00-7.0 E+00 C.

Irradiated components, control rods, etc.

m Ci None d.

Other (describe) rn Ci None

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

Co-58 Ni-63 Cs-137 Cs-134 Co-60 Mn-54 Fe-55 Sb-124 Ni-59 Ce-144 Sb-125 4.32 E+01 1.17 E+01 1.05 E+01 1.00 E+01 7.30 E+00 3.9 E+00 3.7 E+00 3.2 E+00 2.2 E+00 1.3 E+00 1

~ 1 E+00 b.

Fe-55 Co-60 Nb-95 Cs-137 Zr-95 Co-58 Cr-51 Ce-144 Ni-63 Cs-134 Pu-241 Mn-54 3.83 E+01 1.01 E+01 1.00 E+00 8.6 E+00 7.3 E+00 6.6 E+00 5.9 E+00 4.6 E+00 4.0 E+00 1.7 E+00 1.2 E+00 1.1 E+00

3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Sole Use Truck Sole Use Truck Destination SEG Barnwell B.

IRRADIATEDFUEL SHIPMENTS (Disposition)

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