ML17250A954

Semiannual Radioactive Effluent Release Rept for Jan-June 1989. W/890828 Ltr

ML17250A954
Person / Time
Site:	Ginna
Issue date:	06/30/1989
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8909060292
Download: ML17250A954 (34)

Text

,ACCZEZMTZO 31 BUTION DEMONSTR TION SYrrEX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8909060292 DOC.DATE: 89/06/30 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

SUBJECT:

"Semiannual Radioactive Effluent Release Rept." W/890828 ltr.DISTRIBUTION CODE: IE48D COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.36a(a)(2)

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

R I S 05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DSP/TPAB EXTERNAL BNL T I CHLER g J0 3 LPDR COPIES LTTR ENCL 3 3 1 1 1 1 2 2 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD IRM TECH ADV NUDOCS-ABSTRACT RGN1 DRSS/RPB EGGG SIMPSONi F NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 2 2 2 2 1 1 h TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19 a

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/LID Oa (~1 Ill III IIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649-0001 STATIC ZCLCpHONE AeL*cooa7ie 546-2700 August 28, 1989 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.ec y 85'09060292 890630 Foe eDOCK oa0002~Z g~~l Copies to: Mr.William T.Russell Regional Administrator U.S.Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA l9406 Resident NRC Inspector Ginna Station Ms.Donna Ross New York State Energy Office Empire State Plaza Albany, NY l2223 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 I I TABLE OF CONTENTS

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 7.0 RADIOLOGICAL IMPACT 8.0 METEOROLOGICAL DATA 9'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 lA Gaseous Effluents-Gaseous Summation of all Releases Table Table Table Table Table 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'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, 1989 through June 30,'1989.This report includes a summary o f the quantities o f 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<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 ODCMg 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.

t I il 2The 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'oble gases shall not exceed 2 E-04 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: 2.2 (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 2For 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.

n,k 4 2'Release Rate Limits 2.4 The release rate limits for fission and activation gases from the R.G.&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 0.448 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 were deter-mined from the measured concentration of each radio-nuclide present in grab or composite samples and the total volume of effluents released.2.5 Batch Releases 2.5.1~Li uid 1~2~3~4~5~6~Number of batch release: 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 release effluent into a flowing stream: 5'3 E+02 5.78 E+04 4.96 E+03 1.15 E+02 1.1 E+Ol of 9.05 E+05 2.5.2 Gaseous 1~2~3~4~5~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: l.1E+01 5.18E+03 min 7.26E+02 min 4.71E+02min 2.31E+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.The effluent release heights of the majority of releases were considered to be elevated.Gaseous effluent totals now include C-14 release quantities.

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.5.0 6'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.LOWER LIMIT OF DETECTION NOT MET There were 26 liquid releases for which 1 or more gamma emitting radionuclide did not meet the required lower limit for detection.

These are listed by release number in Table 4.7.0 8~0 9.0 10.0 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, 1989 Semi-Annual Report for the year of 1989.METEOROLOGICAL DATA Not applicable for this report.LAND USE CHANGES Not applicable for this report.ANNUAL TABULATION OF PERSONNEL EXPOSURE This data will be in the report issued for July-December, 1989.

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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)Minor typographical and wording changes as a result of a periodic review were made to the procedural documen-tation of the ODCM.Some of the tables were also replaced to improve legibility.

These changes were made to improve readability and legibility.

The changes do not affect the accuracy or reliability of the dose calculations or setpoint determinations.

The procedure change was reviewed by PORC and approved on 3/8/89.CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)The procedure documenting the Process Control Program was changed to include the Technical Specification reporting requirements to the procedure.

This change does not affect any of the waste processing methods.The procedure was review by PORC and approved on 6/28/89.MAJOR CHANGES TO RADNASTE TREATMENT SYSTEMS There were no major changes to the Radwaste Treatment Systems during the reporting period.

Table 1A EFFZVENT AND WASTE DISPOSAL SZ2KEANNVAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES January-June, 1989 Unit)Quarter)Quarter)Est.Total)Error 0 A.Fission&activation gases 1.Total release 2.Avera e release rate for eriod Ci 1.51E+Ol 5.21E+00 7.0 E+00 uCi sec 1.94E+00 6.55E-Ol 3.Percent of technical s ecification limit%3.08E-04 6.18E-05 B.Iodines 1.Total iodine-131 2.Avera e release rate for eriod Ci 2.29E-04 2.25E-05 4.3 E+01 uCi sec 2.95E-05 2.83E-06 3.Percent of technical s ecification limit 4 6.47E-02 6.22E-03 C.Particulates 1.Particulates with half-lives

>8 da s 2.Avera e release rate for eriod Ci 5.00E-01 7.68E-01 3.0 E+01 uCi sec 6.43E-02 9.66E-02 3.Percent of technical s ecification limit 4 3.42E-06 5.14E-06 4.Gross al ha radioactivit D.Tritium ci 2.24E-06 Ci 1.43E+01 3.16E+01 3.2 E+00 1.Total release 2.Avera e release rate for eriod uCi sec 1.84E+00 3.98E+00 3.Percent of technical s ecification limit 0 2.16E-04 4.68E-04 C 4*4 Table 1B EFEXZH2lT AND HASTE DISPOSAL SEMIANKJAL REPORT GASEOUS EFFLUENTS-EZZVATED RELEASE January-June, 1989 Nuclides Released 1.Fission gases k ton-85 k ton-85m k ton-87 k ton-88 xenon-133 xenon-135 xenon-135m xenon-138 Others s ecif xenon-131m xenon-133m ar on-41 Total for eriod 2.Iodines iodine-131 iodine-133 iodine-135 Total for eriod 3.Particulates strontium-89 strontium-90 cesium-134 cesium-137 barium-lanthanum-140 Others s ecif carbon-14 CONTINUOUS MODE BATCH MODE Unit uarter arter uarter arter Ci Ci 3.66E-02 8.69E-03 Ci 7.48E-02 1.25E-02 Ci 9.25E-02 2.00E-02 Ci 6.06E+00 2.77E+00 2.26E+00 Ci 4.74E+00 2.08E+00 5.50E-03 Ci 8.81E-01 1.15E-Ol Ci 3.05E-01 3.89E-02 Ci Ci 1.14E-01 2.19E-02 9.69E-04 Ci 6.94E-03 3.18E-03 3.25E-02 Ci 5.35E-Ol 1.40E-Ol Ci 1.28E+Ol 5.21E+00 2.30E+00 Ci 3.45E-05 1.72E-05 Ci 1.94E-04 5.31E-06 Ci Ci 2.29E-04 2.25E-05 Ci Ci Ci Ci 3.63E-06 3.24E-06 Ci Ci Ci 5.00E-Ol 7.68E-01 4.50E-Ol 5.40E-01 cobalt-58 Ci 2.18E-05 cobalt-60 unidentified Ci 3.99E-05 Ci 5.42E-06 2.10E-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, 1989.

A I Table 2A EFEIDENT AND MSTE DISH3EBL LIQUID EPPIIJ12lTS

-SUMMATION OF ALL R1K2WBES January-June, 1989 J Unit (Quarter]Quarter/Est.Total]

A.Fission and activation products)1.Total release (not including tritium, ases al ha (2.Average diluted concentration dur iod 3.Percent of a licable limit Ci 2.25E-02 4.25E-02 1.1 E+01 I I I uCi ml 1.80E-10 3.83E-10 2.38E-02 5.31E-03 B.Tritium 1.Total release Ci 1.82E+02 1.72E+02 3.2 E+00 (2.Average diluted concentration dur icd 3.Percent of a licable limit C.Dissolved and entrained gases 1.Total release]2.Average diluted concentration dur iod 3.Percent of a licable limit D.Gross alpha radioactivity 1.Total release I I I I uCi ml 1.48E-06 1.55E-06 4.93E-02 5.17E-02 Ci 1.67E-04 I I I uCi ml 1.34E-12 1.34E-06 Ci 3.0 E+01 E.Volume of waste released rior to dilution liters 3.05E+07 2.63E+07 5.0 E+00 F.Volume of dilution water used dur'od liters 1.25E+ll 1.11E+11 5.0 E+00

~I 4\s<*X y Table 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS January-June, 1989 CONTINUOUS MODE BATCH MODE Nuclides Released strontium-89 strontium-90 cesium-134 cesium-137 iodine-131 cobalt-58 cobalt-60 iron-59 Ci 2.53E-06 2.02E-04 1.33E-03 Ci 2.81E-04 1.20E-04 2.43E-03 5.03E-03 Ci 8.82E-06 5.35E-05 5.94E-03 2.38E-03 Ci 5.05E-05 6.39E-05 1.40E-04 6.50E-03 Ci Ci 5.05E-07 1.92E-04 2.34E-03 Unit uarter uarter uarter uarter 1 2 1 2 Ci 3.62E-05 ci zinc-65 man anese-54 chromium-51 zirconium-niobium-95 mol bdenum-99 technetium-99m barium-lanthanum-140 cerium-141 Other s ecif silver-110m Ci Ci Ci Ci Ci Ci Ci Ci Ci 9.29E-09 5.42E-07 2.43E-04 1.70E-06 6.25E-06 7.36E-06 1.18E-04 2.36E-05 5.80E-05 3.34E-06 1.79E-05 9.50E-06 1.44E-04 3.45E-05 4.95E-04 antimon-124 antimon-125 iodine-133 iodine-135 unidentified C1 C1 2.40E-08 2.08E-05 1.17E-02 5.35E-05 5.15E-06 5.94E-03 Ci 4.16E-05 8.89E-05 8.53E-03 4.08E-03 Ci 5.19E-05 2.20E-06 4.49E-03 1.69E-03 C1 Total for eriod above Ci 4.70E-04 3.85E-04 2.20E-02 4.21E-02 xenon-133 xenon-135 Ci Ci 1.67E-04 NOTE: Isotopes for which no value is given were not, identified in applicable releases.12

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Table 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT A.SOLID WASTE AND IRRADIATED SOLID WASTE SHIPPED OFFSITE FOR BURIAL fuel)FUEL SHIPMENTS OR DISPOSAL (Not irradiated l.T e of waste (a.Spent.resins, filter sludges, eva orator bottoms etc.[b.Dry compressible waste, con-taminated e ui etc.)c.Irradiated components, control rods etc.(d.Other (describe)

Unit m Ci m Ci m Ci m Ci 6-month (Est.Total Period Error 3.41E+00i 2E+00 3.22E+01 5E+00 9.15E+Oli 2E+00 1.06E+Ol 5E+00 2.Estimate of major nuclide composition (by type of waste)a.Co-60 Cs-137 Fe-55 Ni-63 Cs-134 Mn-54 Co-58 H-3 Sb-125 b.Fe-55 Ni-63 Co-60 Co-58 Sr-90 C-14 Cs-137 3.7E+01 2.5E+01 1.1E+Ol 1.0E+Ol 5.9E+00 3.0E+00 2.4E+00 1~6E+00 1.3E+00 3.9E+01 3.3E+01 1.6E+Ol 6.0E+00 2.0E+00 2.0E+00 1.0E+00 3.Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 50 Highway Vehicle Barnwell, SC B.IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi ments Mode of Trans ortation Destination NONE 13

~I Table 4 RELEASE PERMITS NOT MEETING LLD REQUIREMENTS No.Date Isoto es Cause 240 241 243 287 288 306 307 336 341 347 375 376 378 379 382 413 417 462 464 466 , 495 507 512 514 518 522 I 13/29/89 13/29/89 13/29/89 I 4/15/89 I 4/15/89 (4/23/89 (4/23/89 15/4/89 I 5/5/89 I 5/8/89 I 5/19/89 I 5/19/89 I 5/19/89 I I 5/20/89 I 5/2 0/89 I (5/29/89 (5/30/89 I 6/17/89 I 6/17/89 I 6/17/89 16/23/89 (6/26/89 16/27/89 (6/27/89 (6/28/89 16/29/89 I (Fe-59, (Fe-59, I Ce-141 (Fe-59, (Ce-141 (Fe-59, (Fe-59, (Fe-59, (Fe-59, (Cs-134 IFe-59, (Fe-59, (Mn-54, I I-131 (Cs-134 (Mn-54, Cs-13 IFe-59, (Cs-134 IFe-59, (Fe-59, (Fe-59, (Zn-65 (Fe-59, (Fe-59, (Fe-59, (Fe-59, (Fe-59, Zn-65, Ce-141 Zn-65, Ce-141 Zn-65, Ce-141 Ce-141 Ce-141 Zn-65, Zn-65, Zn-65 Zn-65, Cs-134, Ce-141 Zn-65, Ce-141 Co-60, Zn-65, Cs-134, Ce-141 Fe-59, Zn-65, Cs-134, Ce-141, Fe-59, Co-60, Zn-65, I-131, 4, Cs-137 Zn-65, Cs-134 Ce-141, Ce-144 Ce-141 Zn-65, Zn-65 Zn-65, Zn-65 Zn-65, Zn-65 Zn-65, Zn-65 Cs-134 Cs-134, Ce-141 a~a~a~a~a~a~a~a~a~a~a~'a~a 0 a~a~a~a~a~a~a~a~a~a~'a~a~a~a.Activity from other isotopes caused an increased background resulting in the LLD calculation exceeding 5E-07 uCi/ml for the listed isotopes.The higher than normal occurrences of exceeding LLD requirements were due to the following:

Due to the 10 Year ISI program, the reactor cavity was flooded for 21 days instead of the normal 7 days.This significantly increased the amount of liquid waste water which required processing.

2~The increased quantity of waste water required the use of the recycle evaporator to process waste water.This evapora-tor system is not as efficient as the waste evaporator system which resulted in an increased concentration of contaminants in the releases.14 0