ML17262A594
| ML17262A594 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/30/1991 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17250B254 | List: |
| References | |
| NUDOCS 9109200169 | |
| Download: ML17262A594 (30) | |
Text
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244
'ANUARY JUNE, 1991 9109200169 910829 PDR ADOCK 05000244 R PDR
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 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
1 LIST OF TABLES Table lA Gaseous Effluents Summation of all Releases Table 1B Gaseous Effluents - Continuous and Batch Releases Table 2A Liquid Effluents Summation of all Releases Table 2B Liquid Effluents Continuous and Batch Releases Table Solid Waste and Irradiated Fuel Shipments Table 4 Release Permits Not Meeting LLD Requirements Table 5A Liquid Effluents Summation of all Releases (corrected table for July - December 1990)
Table 5B Liquid Effluents - Continuous and Batch Releases (corrected table for July - December 1990)
Table 6 Effluent and Waste Disposal Semi-Annual Report (corrected table for July December 1990)
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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 require-ments of Technical Specification Section 6.9.1.4. The report covers the period from January 1, 1991 through June 30, 1991.
This'eport 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.
Corrected forms for liquid effluents released during the July December 1990 period are included as Tables 5A and 5B to show data which was not available when the report was prepared. Table 3 listing isotopic data for radwaste shipments was incomplete during the July-December 1990 report and a corrected table is included as Table 6 with this report. The table as printed only accounted for 2/3 of the total activity shipped.
All gaseous and liquid effluents discharged during this reporting period were in compliance with the limits of the R.E. Ginna Technical Specifications.
During this report period, 5 of the liquid effluent monitors were replaced with new monitors. The Tech.
Spec. allows releases to be made when specific sampling programs are followed. when monitors are inoperable.
Several monitors were inoperable for more than 30 days, and either the sampling requirements were met or the releases were,not made for all situations.
2 ' SUPPLEMENTAL INFORMATION 2.1 Re ulato 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.
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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.
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. J 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-
'ated 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) Duringandanyto calendar year to < 3 mrem to the total
< 10 mrem to any organ.
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2 ' Maximum Permissible Concentrations MPC 2~2~1 For gaseous effluents, maximum permissible concentrations are not directly used in'elease rate calculations since the applicable limits are sta'ted in terms of dose rate at the unrestricted area boundary.
2 ' ' For liquid effluents, the'aximum 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 ' 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 0.217 Mev.
2 ' 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.
2 ' Batch Releases 2.5 ' ~Li uid 1~
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Number of batch releases:
Total time period for 2 '1 E+02 batch releases: 4.57 E+04 min.
- 3. Maximum time period for a batch release: 5.41 E+03 min.
- 4. Average time period for batch releases: 1.68 E+02 min.
- 5. Minimum time period for a batch release: 1.3 E+Ol min.
- 6. Average stream flow (LPM) during periods of release effluent into a flowing stream: 9.59'+05 lpm
2.5.2 Gaseous 1~ Number of batch releases: 1.0E+Ol 2~ Total time period for batch releases: 6.94E+03 min.
3 ~ Maximum time period for a batch release: 5.38E+03 min.
4 ~ Average time period for batch releases: 6.94E+02 min.
5 ~ Minimum time period for a batch release: 1.52E+02 min.
2.6 Abnormal Releases There were no abnormal releases of licpxid 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 elevated releases.
4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS The quantities of radioactive material released in licpxid effluents are summarized in tables 2A and 2B.
5.0 SOLID WASTES The quantities of radioactive material released in shipments of solid waste 'ransported 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 14 liquid releases. These are listed by release number in Table 4 ~
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7.0 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, 1991 Semi-Annual Report for the year of 1991.
8.0 METEOROLOGICAL DATA This data will be in the report issued for July-December, 1991.
9.0 LAND USE CHANGES This data will be in the report issued for July-December, 1991.
10 ' ANNUAL TABULATION OF PERSONNEL EXPOSURE This data will be in the report issued for July-December, 1991.
11.0 LEAK TEST OF SEALED SOURCES No sealed sources were found to be leaking when smeared by both wet and dry smears.
12 ' CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
There were no changes to the ODCM during the report period.
13.0 CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
There were no changes to the PCP during the reporting period.
14.0 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 AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATION OF ALLRELEASES JANUARY - JUNE 1991 Unit Quarter Quarter Est. Total A. Fission & activation ases 1st 2nd Error
- 1. Total release Ci 1.03E+02 2.53E+01 6.60E+00
- 2. Avera e release rate for eriod uCi/sec 1.33E+01 3.21E+00
- 3. Percent of technical s ecification limit 2.11E-03 5.10E-04 B. Iodines
- 1. Total iodine-131 Ci 7.04E-04 5.45E-04 3.20E+01
- 2. Avera e release rate for eriod uCi/sec 9.05E-05 6.93E-05
- 3. Percent of technical s ecification limit 1.99E-01 1.52E-01 C. Particulates
- 1. Particulates with half-lives ) 8da s Ci 4.45E-06 6.60E-06 3.50E+01
- 2. Avera e release rate for eriod uCi/sec 5.72E-07 8.39E-07
- 3. Percent of technical s ecification limit 4.30E-05 6.31E-05
- 4. Gross al ha radioactivit Ci 6.10E-08 D. Tritium
- 1. Total release Ci 2.01E+01 2.30E+01 3.20E+00
- 2. Avera e release rate for eriod uCi/sec 2.58E+00 2.92E+00
- 3. Percent of technical s ecification limit 3.04E-04 3.44E-04 E. Carbon-14
- 1. Total release Ci 9.14E-01 8.56E-01 3.00E+01
- 2. Avera e release rate for eriod uCi/sec 1.18E-01 1.09E-01
- 3. Percent of technical s ecification limit 6.25E-06 5.79E-06 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 AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode Batch Mode Nuclides releas'ed Unit Quarter uarter uarter Quarter 1st 2lld 1st 2lld
- 1. Fission ases ar on-41 Ci '.76E-01 1.93E-01 3.13E-01 3.41E-02 kr ton-85 Ci 1.65E+00 5.18E-01 kr ton-85m Ci 1.23E+00 7.37E-02 7.06E-03 1.78E-03 kr ton-87 Ci 2.61E-02 6.80E-02 kr ton-88 Ci 4.36E-02 1.20E-01 8.38E-03 1.34E-03 xenon-131m Ci 6.03E-02 1.16E-01 2.82E-01 6.33E-02 xenon-133 Ci 6.92E+01 1.62E+01 1.37E+01 3.73E+00 xenon-133m Ci 2.02E-01 2.53E-02 7.23E-02 3.17E-02 xenon-135 Ci 1.22E+01 3.50E+00 9.17E-02 3.48E42 xenon-135m Ci 3.61E+00 4.62E-01 xenon-138 Ci 6.74E-02 1.55E-01 others s ecif Ci Ci Ci Ci Total for eriod Ci 8.73E+01 2.09E+01 1.61E+01 4.41E+00
- 2. Io dines iodine-131 Ci 6.89E-04 5.44E-04 1.51E-05 1.41E-06 iodine-133 Ci 3.29E-04 3.54E-05 1.16E-07 iodine-135 Ci Total for eriod Ci 1.02E-03 5.79E-04 1.52E-05 1.41E-06
- 3. Particulates strontium-89 Ci strontium-90 Ci cesium-134 Ci cesium-137 Ci 4.45E-06 6.30E-06 other s eci Ci cobalt-58 Ci 9.40E-08 cobalt-60 Ci 2.01E-07 Total for eriod Ci 4.45E-06 6.60E-06 unidentified Ci 3.39E-06 1.21E-05 Note: Isotope for which no value is given were not identified in applicable releases.
Sample sent out for analysis but result not yet received. Data for identified isotopes will be included with next semi-annual report for July - December, 1991.
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Table 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUID EFFLUENTS - SUMMATIONOF ALLRELEASES JANUARY - JUNE 1991 Unit Quarter Quarter Est. Total A. Fission and activation roducts 1st 2nd Error, %
- 1. Total release (not including tritium, ases, al ha Ci 4.26E42 2.28E-02 5.60E+00
- 2. Average diluted concentration durin eriod uCi/ml 3.22E-10 1.93E-10
- 3. Percent of a licable limit 2.41E-02 3.79E-03 B. Tritium
- 1. Total release Ci 1.75E+02 7.47E+01 3.20E+00
- 2. Average diluted concentration durin eriod uCi/ml 1.33E-06 6.33E-07
- 3. Percent of a licable limit 4.42E-02 2.11E-02 C. Dissolved and entrained ases
- 1. Total release Ci 8.53E-02 2.14E-02 6.00E+00
- 2. Average diluted concentration durin eriod uCi/ml 6.46E-10 1.81E-10
- 3. Percent of a licable limit 3.23E-04 9.07E-05 D. Gross al ha radioactivit
- 1. Total release Ci E. Vol. of waste released ( rior to dilution Liters 3.10E+07 1.34E+07 F. Vol. of dilution water used durin eriod Liters 1.32E+11 1.18E+11 Note: Isotope for which no value is given were not identified in applicable releases.
ll ROCHESTER GAS ELECTRIC CORPORATION Table 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit uarter Quarter uarter Quarter 1st 2ild 1st 211d chromium-51 Ci 2.84E-04 man anese-54 Ci 6.79E-05 7.77E-05 iron-55 Ci iron-59 Ci 2.31E-06 cobalt-58 Ci 3.89E-03 5.07E-03 cobalt-60 Ci 1.13E-07 7.06E-05 1.05E-03 1.45E-03 zinc-65 Ci strontium-89 Ci 6.31E-07 strontium-90 Ci 4.08E-05 zirconium/niobium-95 Ci 5.65E-05 6.40E-05 mol bdenum-99 Ci 1.73E-05 silver-110m Ci 2.11E-04 antinon -122 Ci 1.49E-03 2.03E-04 antinon -124 Ci 7.82E45 1.22E-03 2.78E-03 antinon -125 Ci 8.27E-05 2.39E-04 iodine-131 Ci 2.72E-04 7.40E-05 7.62E-03 9.15E-04 iodine-133 Ci 1.69E-04 3.57E-05 3.09E-03 iodine-135 Ci 2.16E-05 2.27E-05 5.79E-04 cesium-134 Ci 1.30E-04 1.61E-04 9.88E-03 5.15E-03 cesium-136 Ci 2.58E-04 cesium-137 Ci 1.80E-04 2.41E-04 1.22E-02 5.83E-03 barium/lanthanum-140 Ci cerium-141 Ci other s eci ) Ci Ci Total for eriod (above) Ci 7.73E-04 6.83E-04 4.18E-02 2.21E-02 unidentified Ci xenon-133 Ci 2.74E-05 8.17E-02 2.14E-02 xenon-135 Ci 3.61E-03 Note: Isotope 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 1991.
I Table 3 Page 1 of 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January June 1991 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month ( Est. Total
- 1. T e of waste Unit Period Error
)a. Spent resins, filter sludges, m 1 22E+Oll 2 '+00 eva orator bottoms etc. Ci 2.30E+00 2.0+01
- b. Dry compressible waste, con- m
- 9 '7E+001 2 '+00 taminated e i etc.
)
Ci
- 8.84E-01 2.0+01 (c. Irradiated components, control m rods etc. Ci (d. Other (describe) m Ci
- 2. Estimate of major nuclide composition (by type of waste)
- a. H dro en-3 9.3E+01 Antimon -125 2.6E+00 Antimon -124 2.3E+00 Iodine-131 1.2E+00 Cobalt-58 9.9E-02 Cesium-137 6.2E-02 Iron-55 5.7E-02 Nickel-63 3.9E-02 Cesium-134 1.8E-02 Silver-110m 1.7E-02
- b. Iron-55 3. 2E+Ol Cesium-137 2.0E+01 Cobalt-58 1.5E+01 Cobalt-60 1.5E+01 Antimon -125 3.6E+00 Nickel-63 6.8E+00 Cesium-134 3.9E+00 Iodine-129 1.2E+00 Strontium-90 8.1E+00 Technetium-99 5.7E-01 Carbon-14 2.4E-01
- Volume and activity buried by waste processor during this period
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Table 3 Page 2 of 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January - June 1991
- 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. Date Isoto es Cause I I 9100351 1/24/91 (Fe-59, Zn-65,Ce-141 a0 I I 910056 I 2/6/91 JZn-65 a~
I I 9 10075 I 2/16/9 1 (Fe-59, Zn-65 a~
I I 910129 I 3/23/91 /Zn-65, Ce-141 a ~
I I 910131 I 3/24/91 /Fe-59, Zn-65 a ~
I I 910132 I 3/24/9 1 /Fe-59, Zn-65, Cs-134, Ce-141 a ~
I I 91015 I 4/8/91 /Fe-59, Zn-65, Cs-134, Ce-141 a~
I I 910159(4/9/91 /Fe-59, Zn-65, Cs-137 a~
I I 910161I4/10/91 /Fe-59, Zn-65, Cs-134, Cs-137, Ce-141 a~
I I 910169 I 4/16/91 /Fe-59, Zn-65 a~
I I 910184 I 4/3 0/91 /Fe-59, Zn-65 a~
I I 910186I5/2/91 /Fe-59, Zn-65 a~
I I 910235 5/28/91 /Zn-65
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I I 910278 ( 6/26/91 IFe-59 Co-60, Zn-65, Cs-134, 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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