ML17251A252

Semiannual Radioactive Effluent Release Rept,Jan-June 1988. W/880829 Ltr

ML17251A252
Person / Time
Site:	Ginna
Issue date:	06/30/1988
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8809080175
Download: ML17251A252 (32)

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AC CELERATZD DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RXDS)

ACCESSION NBR:8809080175 'OC.DATE: 88/06/30 NOTARIZED: NO DOCKET g 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

SUBJECT:

"Semiannual Radioactive Effluent Release Rept,Jan-June 1988." W/880829 ltr.

R DXSTRIBUTION CODE XE48D COPIES RECEIVED:LTR ENCL SIZE-TITLE: 50.36a(a)(2) Semiannual Effluent Release Report )'

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244",g

,RECIPIENT COPIES RECIPIENT COPIES, II 8

ID'CODE/NAME" LTTR ENCL XD CODE/NAME LTTR ENCL PD1-3 LA 1 0 PD1-3 PD 5 5 STAHLE,C 1 1 INTERNAL: AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB 8D 1 1 NRR/J3REP/RPB 10 4 4 NUDOCS-ABSTRACT 1 1 1 1 RGN1 FILE 02 1 1 RGN2/DRSS/EPRPB 1 1 EXTERNAL BNL TICHLER i J03 1 1 LPDR 1 1 NRC PDR 1 1 D

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 21

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E.-GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 JANUARY - JUNE 1988 8

8809080i75 8>OOOZ44 PDR ADOCK 0 pDC R

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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 ' 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 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 Gaseous Summation of all Releases Effluents - Continuous and Batch Releases J

Table 1B Gaseous 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 Recpxirements

1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report is for Rochester Gas and Electric Company's 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 January 1, 1988 through June 30, 1988.

This report includes a summary of the cpxantities of radioactive gaseous and licpxid 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 SUPPLEMENTAL INFORMATION 2.1 Re ulator Limits The Technical Specification limits applicable to release of radioactive material in liquid and gaseous effluents are:

2.F 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 '.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.

I' 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 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 ' 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 ' ' For liquid effluents, the maximum permissible concen-tration values specified in 10CFR20, Appendix B, Table II, column 2 are used to calculate release permissible concentrations at the unrestricted area rates and boundary. A value of 2E-04 uCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.

2.3 Avera e Ener The average energy of the radionuclide mixture of fission and activation gases released during the time period of this report was 0.285 Mev.

2.4 Measurements and A roximations of Total Radioactivit Gamma spectroscopy was the primary analysis method used to determine the radionucl ide 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 release 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 ~Li uid 1~ Number of batch release: 4.51 E+02 2 ~ Total time period for batch releases: 3.80 E+04 min 3 ~ Maximum time period for a batch release: 3.63 E+03 min 4 ~ Average time period for batch releases: 8.4 E+01 min

5. Minimum time period for a batch release: 1.4 E+01 min 6 ~ Average stream flow (LPM) during periods of effluent releases into the flowing stream: 1.07 E+06 2.5.2 Gaseous 1~ Number of batch releases: 1.4E+01 2 ~ Total time period for batch releases: 6.28E+03 min 3 ~ Maximum time period for a batch release: 7.47E+02 min 4 ~ Average time period for batch releases: 4.48E+02 min

5. Minimum time period for a batch release: 2.47E+02 min

J 2 ' 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 lA 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.

6.0 LOWER LIMIT OF DETECTION NOT MET There were 5 liquid releases for which 1 or more gamma emitting radionuclide for which the LLD specification applies which did not meet the required lower limit for detection. These are listed by release number in table 4 ~

7 ' RADIOLOGICAL IMPACT An assessment, of doses to the maximally exposed indivi-dual from gaseous and liquid effluents will be performed and reported in the July - December, 1988 Semi-Annual Report for the year of 1988.

8.0 METEOROLOGICAL DATA Not applicable for this report.

9.0 LAND USE CHANGES Not applicable for this report.

10 ' ANNUAL TABULATION OF PERSONNEL EXPOSURE This data will be in the report issued for July-December, 1988.

C 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.

In the August 29, 1987 Semi-Annual Effluent Report, a change in the pH for solidification was noted without a negative impact statement. Tests had been conducted on the solidified product prior to that date and there has been no change in the integrity of the final solidified mass.

MAi7OR CHANGES TO RADWASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.

Table 1A XPlXOENT AND HASTE DISPOSAL SEKDZNU2LL REPORT GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January 1 - June 30, 1988 Unit )Quarter ]Quarter )Est. Total)

Error 4 A. Fission & activation gases

1. Total release Ci 1.90E+01 5.45E+00 7. OE+00

2. Avera e release rate for eriod uCi sec 2.42E+00 6.93E-01

3. Percent of technical s ecification limit 0 2.3 E-04 6.5 E-05 B. Iodines

1. Total iodine-131 Ci 2.64E-03 1.77E-04 4.3E+01

2. Avera e release rate for eriod uCi sec 3.36E-04 2.25E-05

3. Percent of technical s ecification limit > 5.9 E-01 3.1 E-01 C. Particulates

1. Particulates with half-lives ) 8 da s Ci 1.28E-05 2.73E-06 4.3E+01

2. Avera e release rate for eriod uCi sec 1.63E-06 3.47E-07

3. Percent of technical s ecification limit > 1.2 E-04 2.6 E-05

4. Gross al ha radioactivit Ci 4.51E-07 3.23E-08 D. Tritium

1. Total release Ci 3.84E+01 5.86E+Ol 3.2E+00

2. Avera e release rate for eriod uCi sec 4.88E+00 7.45E+00

3. Percent of technical s ecification limit 4 5.7 E-04 8.8 E-04

Table lB EFEXZlENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS ELEVATED RELEASE CONTINUOUS MODE BATCH MODE Nuclides Released Unit uarter arter uarter arter

1. Fission gases ton-85 Ci ton-85m Ci 1. 63E-02 3. 63E-02 ton-87 Ci 2.49E-02 5.92E-02 k ton-88 Ci 3.40E-02 7.91E-02 xenon-133 Ci 7.14E+00 2.15E+00 2.42E+00 1.87E-01 xenon-135 Ci 8.51E+00 1.54E+00 6.91E-02 3.84E-03 xenon-135m Ci 2.79E-01 5.92E-01 xenon-138 Ci 1.11E-01 2.07E-01 Others s ecif ar on-41 Ci 2.10E-Ol 4.58E-Ol 8.95E-02 6.27E-02 xenon-131m Ci 3.21E-02 7.71E-02 1.61E-03 xenon-133m Ci 2.10E-02 Total for eriod Ci 1.64E+Ol 5.20E+00 2.58E+00 2.54E-Ol

2. Iodines iodine-131 Ci 9.86E-06 1.08E-05 1.44E-05 iodine-133 Ci 2.40E-03 1.66E-04 2.20E-04 iodine-135 Ci Total for eriod Ci 2.41E-03 1.77E-04 2.34E-04

3. Particulates strontium-89 Ci strontium-90 cesium-134 Ci cesium-137 Ci barium-lanthanum-140 Ci Others s ecif Ci Ci Ci unidentified Ci Note: Isotopes for which no value is given were not identified in applicable releases.

• Sample sent out for analysis but results not yet received. Data for identified isotopes will be included with next semi-annual report for July December, 1988.

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Table 2A EFFIDENT AND MSTE DISPOSAL ZZQUID 1WKIJ1WIS - SUMMATION OF ALL REZZASES January 1 - June 30, 1988 J

Unit )Quarter [Quarter JEst.Total[

A. Fission and activation products

( 1. Total release (not including tritium, ses al ha Ci 9.86E-03 1.45E-02 l.lE+Ol (2. Average diluted concentration I I I dur iod uCi ml 8.57E-ll 8.73E-ll

3. Percent of a licable limit 3.6 E-03 1.2 E-02 B. Tritium

1. Total release Ci 1.69E+02 4.53E+Ol 3.2E+00

[2. Average diluted concentration I I I I dur iod uCi ml 1.47E-06 2.72E-07

3. Penent of a licable limit 4.9 E-02 9.1 E-03 C. Dissolved and, entrained gases

1. Total release Ci 1.93E-04 2.33E-03 3.4E+01

) 2. Average diluted concentration I I I I dur iod uCi ml 1.68E-12 1.40E-ll

3. Percent of a licable limit 1.7 E-06 1.4 E-05 D. Gross alpha radioactivity

l. Total release Ci E. Volume of waste released rior to dilution liters 2.41E+07 2.59E+07 5.0E+00 F. Volume of dilution water used dur'od liters 1.15E+ll 1.66E+11 5.0E+00

Table 2B EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE Nuclides Released Unit uarter uarter uarter '

uarter 1 1 strontium-89 Ci

• 1.13E-04

• strontium-90 Ci

• 4.51E-05

• cesium-134 Ci 1.14E-04 1.19E-04 2.03E-03 6.04E-04 cesium-137 Ci 3.06E-04 3.17E-04 3.28E-03 1.52E-03 iodine-131 Ci 7.58E-07 5.67E-06 6.23E-04 3.62E-03 cobalt:-58 Ci 7.53E-07 1.35E-07 6.78E-04 1.80E-04 cobalt-60 3.00E-05 3.70E-07 3.41E-04 7.92E-04 iron-59 Ci zinc-65 Ci man anese-54'hromium-51 Ci 5.36E-05 6.61E-05 2.70E-04 zirconium-niobium-95 Ci 3.20E-05 4.57E-05 mol bdenum-99 Ci 2.25E-05 8.83E-05 technetium-99m Ci barium-lanthanum-140 Ci cerium-141 Ci Other s ecif Ci iodine-133 Ci 3.27E-06 2.00E-05 1.03E-03 5.43E-03 iodine-135 Ci 3.37E-06 1.70E-05 7.40E-04 1.62E-03 iron-55 Ci

• 2.47E-05

• silver-110m Ci 1.14E-04 Ci unidentified Ci Total for eriod above Ci 4.58E-04 4.79E-04 9.40E-03 1.40E-02 xenon-133 Ci 6.91E-05 1.47E-03 xenon-135 Ci 1.24E-04 8.55E-04 NOTE: Isotopes for which no value is given were not identified in applicable releases.

• Sample-sent out for analysis but results not yet received. Data for identified isotopes will be included with next Semi-Annual Report for July December, 1988.

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Table 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month ( Est. Total

1. T e of waste Unit Period Error 4

]a. Spent resins, filter sludges, m I 1 466E+Ol I 2E+00 eva orator bottoms etc. Ci 1.68 E+02 5E+00

)b. Dry compressible waste, con- m )3.12 E+01( 2E+00 taminated e i etc. Ci 1.25 E+01 5E+00

)c. Irradiated components, control m rods etc. Ci (d. Other (describe) m Ci

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

a. Cobalt-60 5.33E+01 Iron-55 4.70E+00 Cesium-137 1.01E+01 H dro en-3 2.62E+00 Nickel-63 1.88E+01 Cesium-134 1.07E+01

b. Cobalt-60 2.76E+01 Iron-55 5.36E+Ol Nickel-63 1.12E+01 Cesium-137 8.00E+00

3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination Highway Vehicle Barnwell, SC B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi ments Mode of Trans ortation Destination None

I Table 4 RELEASE PERMITS NOT MEETING LLD REQUIREMENTS No. Date Isoto es Cause 12 1 I 2/13/88 Ce-141 a ~

177 I 3/1/88 Fe-59, Zn-65, Cs-137, Ce-141 a ~

258 1 3/18/88 Fe-59, Zn-65, Ce-141 a ~

432 I 6/2/88 Ce-141 a ~

487 I 6/17/88 Co-58, Fe-59, Zn-65, Ce-141 a ~

a. Activity from other isotopes caused an increased background resulting in the LLD calculation exceeding 5E-07 uCi/ml for the listed isotopes.

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'SM(!8 SFliS i sà re zzzzizz 5TAW Satire IIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 TCLEPHONC AREA coDK TI6 546.2700 August 29, 1988 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sirs:

This Semi-Annual Radioactive Effluent Release Report is being forwarded to you in accordance with the requirements of Technical Specification Section 6.9.1.4.

Very truly yours, Robert C. Me redy xco Mr. William T. Russell Regional Administrator U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406

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