ML17263A543
| ML17263A543 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/31/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9403110005 | |
| Download: ML17263A543 (43) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR 940CQQ.10005 DOC DATE 93 12 31 NOTARIZED NO DOCKET FACIL:50-24'4 Rob~!r:.t 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, Jul-Dec 1993." W/940301 ltr.
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~ zzzM ztzimz ROCHESTER GAS AND ELECTRIC CORPORATION ROBERT C MECREDY Vice Prerident Clnna Nuclear Production utv lAIrOhllh o
89 EAST AVENUE, ROCHESTER N. Y. '/4649-0001 TELEPHOtrE AitEncooE me 546-2700 March 01, 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, Vice President 9403ii0005 93i23i PDR ADOCKr05000244 PDR rgy<
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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
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SEMlANNUALRADtOACTlVE EFFLUENT RELEASE REPORT R. E. GINNA NUCLEAR PLANT ROCHESTER GAS AND ELECTRIC DOCKET NO. 50-244 JULY - DECEMBER, 1993
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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 RADIOACTIVEEFFLUENTS 5.0 SOLID WASTE 6.0 LOWER LIMITOF DETECTION NOT MET 7.0 RADIOLOGICAL IMPACT 8.0 METEOROLOGICAL DATA 9.0 LAND USE CENSUS CHANGES 10.0 ANNUALTABULATIONOF PERSONNEL EXPOSURE 11.0 LEAKTEST 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 2A, Liquid Effluents - Summation of all Releases Table 2B Liquid Effluents - Continuous and Batch Releases Table 3
Table 4
Solid Waste and Irradiated Fuel Shipments Release Permits Not Meeting LLD Requirements Table 5A Radiation Dose to Nearest Individual Receptor from Gaseous Releases Table 5B Radiation Dose to Nearest Individual Receptor from Liquid Releases Table 6A Number of Personnel and Man-Rem by Work and Job Function Table 6B Standard Report of Personnel Whole Body Exposure
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1.0 INTRODUCTION
This Semiannual Radioactive Effluent Release Report is for the 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 July 1, 1993 through December 31, 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. Girma Technical Specifications.
2.0 2.1 SUPPLEMENTAL INFORIVIATION 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.
2.1.2 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.
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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:
2.1.3 (i)
During any calendar quarter to < 7.5 mrem to any organ.
(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 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, 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 0.277 Mev.
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2.4 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 and Fe-55 by a contract laboratory.
Tritium and alpha analysis were done using liquid scintillation and gas flow proportional 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.
Batch Releases 2.5.1 Liciuid 1
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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:
Average stream flow (LPM) during periods of release effluent into a flowing stream:
1.71 E+02 3.86 E+04 min.
2.67 E+03 min.
2.25 E+02 min.
3.6 E+01 min.
1.29 E+06 LPM 2.5.2 Gaseous 1
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3.
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:
2.8E+ 01 1.28E+ 04 min.
2.57E+ 03 min.
6.09E+ 02 min.
6.0E+01 min.
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2.6 Abnormal Releases There were no abnormal releases of liquid or gaseous effluents during the reporting period.
3.0
SUMMARY
OF GASEOUS RADIOACTIVEEFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in tables 1A and 18.
All releases were considered to be elevated releases.
SUMMARY
OF LIQUID RADIOACTIVEEFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in tables 2A and 28.
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 LIMITOF DETECTION NOT MET There were no gamma emitting radionuclides that did not meet the required lower limit of detection for liquid releases.
7.0 RADIOLOGICALIMPACT An assessment of doses to the maximally exposed individual from gaseous and liquid effluents was performed for locations representing the maximum dose.
In all cases, doses were well below Technical Specification limits.
Doses were assessed upon actual meteorological conditions considering the noble gas exposure, inhalation, ground plane and ingestion pathways.
The ingestion pathways considered were the produce, vegetable, goat's milk, cow's milk and meat pathway.
The results of this assessment are presented in Tables 5A and 58.
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8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1993 is not included with this report, but can be made available at the R.E.
Ginna Plant as allowed by Technical Specifications.
LAND USE CENSUS CHANGES There were no changes in critical receptor location for dose calculations during the reporting period.
10.0 ANNUALTABULATIONOF PERSONNEL EXPOSURE The annual tabulation of the number of station, utility and other personnel receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job function required by Technical Specification 6.9.2.2 and 10CFR20.407 is included as Tables 6A and 6B.
11.0 LEAK TEST OF SEALED SOURCES No sealed sources were found to be leaking when smeared by both wet and dry smears.
12.0 CHANGES TO THE OFFSITE DOSE CALCULATIONMANUAL (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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CHESTER GAS ELECTRIC CORPORATI Table 1A EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES JULY - DECEMBER 1993 A. Fission 8 activation ases Unit Quarter 3rd Quarter 4th Est. Total Error, %
- 1. Total release
- 2. Avera e release rate for eriod
- 3. Percent of technical s ecification limit Cl 1.97E+01 uCi sec 2.48E+00 3.94E44 1.35E+01 6.60E+00 1.69E+00 2.69E44 B. Iodines
- 1. Total iodine-131
- 2. Avera e release rate for erlod
- 3. Percent of technical s ecification limit CI 1.19E45 uCI sec 1.50E-06 3.30E43 3.30E45 1.80E+01 4.16E46 9.13E43 C. Particulates
- 1. Particulates with half-lives > 8da s
- 2. Avera e release rate for eriod
- 3. Percent of technical s ecification limit CI uCI sec 1.24E46 1.57E47 1.18E45 1.58E46 1.99E47 1.50E45 4.00E+01
- 4. Gross al ha radloactivit D. Tritium
- 1. Total release
- 2. Avera e release rate for eriod
- 3. Percent of technical s ecification limit CI CI uCI sec 1.15E+01 1.18E+01 1.44E+00 1.48E+00 1.70E44 1.74E44 3.20E+00 E. Carbon-14
- 1. Total release
- 2. Avera e release rate for eriod
- 3. Percent of technical s ecificatlon limit Ci uCI sec 7.95E-01 7.17E-01 1.00E41 9.02E-02 5.32E46 4.80E46 3.00E+01 Note:
Isotope forwhich no value is given were not identified in applicable releases.
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CHESTER GAS ELECTRIC CORPORATI Table 1B EFFLUENT ANDWASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - ELEVATEDRELEASE Continuous Mode Batch Mode Nuclldes released 1.
Flsslon ases Unit 3rd 4th 3rd 4th Quarter Quarter Quarter Quarter ar on41 k
ton%5 k
ton%5m k
ton7 k
ton@8 xenon-131m xenon-133 xenon-133m xenon-135 xenon-135m xenon-138 others s ec Total for erlod CI Ci CI CI CI Ci Ci Cl CI Ci Ci Ci CI CI Ci CI 6.63E42 5.54E42 7.43E42 7.35E42 1.42E+01 1.46E42 2.64E+00 7.15E41 2.58E41 1.81E+01 1.38E41 6.18E-02 7.21E42 1.02E41 5.70E+00 1.85E42 2.87E+00 7.55E-01 2.76E-01 9.99E+00 5.66E-02 2.73E41 7.53E44 1.35E-04 1.39E42 1.31E+00 1.04E42 1.90E42 1.69E+00 4.76E42 1.99E41 3.35E43 3.07E44 4.64E42 3.09E+00 1.61E42 6.39E42 1.50E44 3.47E+00 2.
Iodlnes iodine-131 iodine-133 Iodine-135 Total for eriod 3.
Particulates strontium%9 strontium-90 CI Ci Ci CI CI CI 1.19E45 1.26E-05 1.54E48 1.32E45 1.32E-05 9.02E48 2.51E45 2.58E-05 1.06E-07 2.04E45 4.16E-05 6.20E45 cesium-134 cesium-137 Nb-95 cobalt-58 cobalt%0 Total for eriod unidentified Ci Ci CI CI CI CI CI 1.24E46 1.24E46 1.58E46 1.58E46 Note:
Isotope forwhich no value is given were not Identified in applicable releases.
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CHESTER GAS ELECTRIC CORPORATI Table 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES JULY-DECEMBER 1993 A. Fission and activation roducts Unit Quarter 3rd Quarter 4th Est.Total Error, %
- 1. Total release (not including tritium, ases,al ha
- 2. Average diluted concentration durin eriod
- 3. Percent of a Iicable limit Ci uCi ml 1.78E42 5.38E-02 1.03E-10 3.18E-10 2.18E43 1.86E42 7.00E+00 B. Tritium 1 ~ Total release
- 2. Average diluted concentration durin erlod
- 3. Percent of a licabie limit C. Dissolved and entrained ases CI uCi ml 3.34E+01 1.92E47 6.40E43 5.05E+01 3.20E+00 2.99E47 9.97E43
- 1. Total release
- 2. Average diluted concentration durin erlod
- 3. Percent of a licable limit D. Gross ai ha radloactivi
- 1. Total release Ci uCi ml Ci 5.15E44 8.53E42 2.96E-12 5.05E-10 1.48E46 2.53E-04 4.00E+01 E. Vol. of waste released riorto dilution Liters 3.84E+07 2.65E+07 5.00E+00 F. Vol. of dilution water used durin erlod Liters 1.74E+11 1.69E+11 5.00E+00 Note:
Isotope forwhich no value is given were not identified in applicable releases.
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'.30E44 3.70E44 7.74E%5 1.99E44 4.42E-06 2.02E45 3.3?E44 1.29E43 iodine-131 Iodine-133 Iodine-135 cesium-134 cesium-136 cesium-137 barium lanthanum-140 cerium-141 Ru-106 Ru-103 Ci CI Ci CI CI CI CI Ci CI CI 5.07E46 5.06E-04 1.86E44 2.92E-04 4.25E45 5.30E45 3.45E46 6.20E44 1.53E44 7.60E44 6.45E44 1.15E-04 8.13E03 7.07E-03 4.61 E43 9.23E-03 7.13Ee3 1.45E42 1.49E44 1.33E<2 9.59E45 Total for erlod above unidentified xenon-133 xenon-1 35 Ci Ci Ci Ci 3.90E44 2.27E43 1.74E42 5.15E-02 4.85E-04 5.82E42 2.97E45 2.71E-02 Note:
Isotope for which no value is given were not identified in applicable releases.
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Table 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT Solid Waste and Irradiated Fuel Shipments July - December 1993 A.
Solid waste shipped offsite for burial or disposal (NOT irradiated fuel) c>>
TYPE OF WASTE Spent resins, filtersludges, evaporator bottoms, etc.
Dry compressible
- waste, contaminated equipment, etc.
Irradiated components, control rods, etc.
UNIT m
Ci m
Ci m
Ci 6 MONTH PERIOD 8.04 E 0 1.97 E 1 1.02 E 2 1.1 E -1 EST. TOTAL ERROR 7.0 E 0 7.0 E 0 7.0 E 0 7.0 E 0 d.
Other {describe) m Ci Estimate of major nuclide composition (by type of waste)
Fo-55 Co.60 Ni-63 Cs-137 C-14 H-3 Sb-125 3.1 E
1 3.0 E 1 1.951 7EO 5EO 2EO 2EO Fe-55 Co-60 Nb-95 Cs-137 Zr-95 Co-58 Cr-51 Ce-144 Ni-63 Cs-134 Mn.54 3.8 E 1 1.0 E 1 1.0E 1
9.0 E 0 7EO 7EO 6EO 5EO 4EO 2EO 1EO 3.
Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION 2
Sole use truck 2
Sole use truck B. IRRADIATEDFUEL SHIPMENTS (Disposition)
DESTINATION Barnwell, SC Oak Ridge, TN NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None N/A N/A
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Table 4 RELEASE PERMITS NOT MEETING LLD REQUIRElVIENTS No.
Date Isotopes Cause None
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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem First Quarter T.BODY ADULT T.BODY THYRD SKIN T.BODY CHILD THYRD SKIN T.BODY THYRD N
NE ESE SE SSE SSW SW WSW 7.60E-08 7.20E-08 6.10E48 9.10E48 7.10E-07 7.70E-07 8.20E47 3.20E47 1.40E46 4.50E47 5.80E-07 5.20E-07 5.20E-07 2.10E47 2.00E48 4.70E-OS 8.90E-OS 1.10E-07 7.90E-OS 1.00E-07 6.60E-08 9.50E-OS 9.90E-08 1.70E-07 7.50E-07 1.10E-06 8.30E47 1.10E-06 8.80E47 1.20E46 3.40E47 5.10E-07 1.50E-06 2.40E-06 4.90E-07 6.60E-07 6.10E-07 6.30E-07 6.00E-07 3.60E-07 6.00E-07 3.60E-07 2.20E-07 3.20E-07 2.30E-OS 2.40E-OS 5.60E-08 6.00E-OS 7.80E48 9.50E-OS 7.50E48 8.30E-OS 6.30E-08 6.90E-OS 9.20E48 1.00E-07 7.20E-07 7.70E-07 7.90E-07 8.70E-07 8.60E47 9.30E-07 3.20E47 3.50E-07 1.50E46 1.60E-06 4.60E47 5.00E-07 6.00E47 6.40E47 5.40E47 6.40E47 5.40E47 6.40E-07 2.20E47 2.30E-07 2.10E-08 2.40E4S 4.90E48 6.00E-OS 1.10E-07 7.80E-08 1.00E-07 7.50E-08 9.50E-OS 6.40E48 1.70E47 9.10E48 1.10E46 7.20E-07 1.10E46 8.00E-07 1.20E46 S.SOE-07 5.10E-07 3.20E-07 2.40E-06 1.50E46 6.60E-07 4.50E-07 6.30E-07 5.90E-07 3.60E47 5.30E-07 3.60E-07 5.30E-07 3.20E-07 2.20E47 2.40E48 2.00E-OS 6.00E48 4.80E48 9.60E-OS 1.10E-07 8.50E-OS 1.00E-07 7.10E-OS 9.50E-08 1.00E-07 1.70E-07 7.70E-07 1.10E-06 8.80E-07 1.10E-06 9.50E-07 1.20E-06 3.50E47 5.10E-07 1.60E-06 2.40E-06 5.00E-07 6.60E-07 6.30E47 6.30E-07 6.40E-07 3.60E-07 6.40E-07 3.60E-07 2.30E-07 3.20E-07 2.40E-OS 2.40E-OS 6.10E-08 6.00E-OS 6.50E-OS 8.20E-OS 6.30E-OS 7.20E-08 5.50E48 6.10E48 8.10E48 9.10E-OS 6.30E-07 6.80E-07 6.80E-07 7.60E-07 7.50E-07 8.20E-07 2.80E47 3.10E47 1.30E46 1.40E-06 3.90E-07 4.40E-07 4.80E47 5.10E47 4.00E47 5.00E-07 4.00E-07 5.00E-07 1.90E47 2.00E-07 1.60E-OS 1.90E-08 4.00E-OS 5.10E-OS 1.10E-07 1.00E-07 9.50E48 1.70E-07 1.10E-06 1.10E-06 1.20E-06 5.10E-07 2.40E-06 6.60E-07 6.30E-07 3.60E-07 3.60E47 3.20E-07 2.40E48 6.00E-OS 1.40E46 1.50E-06 2.40E-06 1.50E-06 1.60E-06 2.40E46 1.50E46 1.60E-06 2.40E46 1.30E-06 1.40E-06 2.40E-06
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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Second Quarter T.BODY ADULT THYRD T.BODY THYRD SKIN T.BODY CHILD THYRD SKIN INFANT T.BODY THYRD SKIN N
3.90E48 3.90E-OS 4.20E48 4.00E-OS 2.50E-06 2.50E-06 5.50E47 3.70E-07 6.20E-07 5.40E47 1.20E-06 1.00E-06 5.50E47 3.00E47 1.40E48 2.60E-OS 4.00E-OS 4.00E48 4.30E-08 4.10E-OS 2.60E-06 2.60E-06 5.70E-07 3.80E-07 6.40E47 5.50E47 1.20E46 1.00E-06 5.50E-07 3.10E-07 1.50E-OS 2.60E-08 2.30E-OS 2.30E48 2.50E48 2.20E48 2.30E46 2.20E-06 5.20E-07 3.90E-07 5.70E47 5.90E47 1.40E46 7.50E47 4.50E47 2.40E47 7.40E49 1.40E-OS 4.00E-OS 4.10E-08 4.00E48 4.10E-08 4.30E48 4.40E-OS 4.30E48
- 4.30E-OS 3.60E46 3.60E-06 3.50E46 3.50E-06 6.50E47 6.90E-07 4.50E-07 4.60E47 7.10E-07 7.30E-07 6.20E47 6.30E-07 1.50E-06 1.50E-06 1.30E46 1.30E-06 6.80E-07 6.90E-07 3.20E47 3.20E-07 1.50E48 1.50E-08 2.70E48 2.70E-OS 2.30E-OS 3.80E-08 2.30E-08 3.80E-OS 2.50E48 4.10E-OS 2.20E-OS 4.20E-OS 3.20E-06 7.20E-06 3.10E-06 7.00E-06 6.10E-07 1.00E-06 4.50E-07 7.10E-07 6.40E47 1.00E-06 6.60E-07 9.20E-07 1.60E46 2.40E46 9.30E-07 2.00E-06 5.50E-07 1.10E-06 2.40E47 3.20E-07 7.40E49 1.40E48 1.40E-OS 2.60E-08 3.90E-OS 2.30E-08 3.90E-OS 2.30E-08 4.20E48 2.50E-08 4.30E48 2.20E-OS 7.30E-06 6.70E-06 7.20E46 6.50E-06
'1.10E46 9.50E47 7.30E-07 6.80E-07 1.00E-06 9.00E-07 9.40E-07 9.20E-07 2.40E46 2.40E-06 2.10E-06 1.60E-06 1.20E-06 9.50E-07 3.20E-07 2.40E47 1.50E4S 7.40E49 2.70E-OS 1.40E-OS 2.70E-OS 2.80E-08 2.70E-OS 2.80E-OS 2.90E-OS 3.00E-OS 3.00E48 3.10E-08 3.00E-06 3.10E-06 4.80E-06 5.00E46 1.00E-06 1.10E46 8.20E-07 8.40E47 1.10E-06 1.10E-06 1.20E-06 1.30E-06 3.60E46 3.60E46 2.10E46 2.10E46 8.30E-07 8.30E-07 2.50E47 2.50E-07 1.00E-OS 1.00E4S 1.90E-OS 1.90E48 2.30E-OS 2.30E-OS 2.50E-OS 2.20E-08 2.80E-06 4.60E-06 9.70E-07 8.00E47 1.00E-06 1.20E-06 3.40E46 1.80E-06 7.50E-07 2.30E-07 7.40E49 1.40E-OS 2.50E-06 2.60E-06 2.30E-06 3.60E-06 3.60E-06 3.20E46 7.20E46 7.30E-06 6.70E46 4.80E46 5.00E46 4.60E-06
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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Third Quarter ADULT T.BODY THYRD SKIN T.BODY THYRD SKIN CHILD T.BODY THYRD SKIN T.BODY N
NE ESE SE SSE SSW SW WSW 4.00E-08 4.00E-OS 5.60E48 5.70E-OS 5.70E-08 5.70E-OS 3.30E4S 3.30E-OS 2.40E-06 2.40E-06 1.90E-06 1.90E-06 7.90E-07 8.30E47 5.80E-07 6.00E-07 2.50E-06 2.60E46 9.00E-07 9.40E47 2.00E-06 2.00E-06 2.30E46 2.30E-06 1.10E-06 1.20E-06 6.10E47 6.10E47 1.70E-OS 1.70E48 1.90E-OS 1.90E48 4.10E-08 4.10E-OS 6.20E-OS 5.70E-OS 5.30E-OS 5.90E-OS 2.50E48 3.50E-OS 2.30E46 3.60E-06 1.70E-06 2.60E-06 7.70E47 9.80E-07 5.80E47 7.20E-07 2.60E46 3.40E-06 S.60E47 1.20E-06 2.00E-06 2.70E-06 2.20E46 3.50E46 1.10E46 1.70E-06 6.40E47 9.40E-07 1.40E4S 1.70E-OS 1.70E-08 2.00E-OS 4.10E-08 4.10E-OS 5.80E-OS 6.20E48 5.90E48 5.30E-08 3.50E-08 2.50E-08 3.60E46 3.50E-06 2.70E-06 2.40E-06 1.00E46 9.30E47 7.50E-07 7.10E-07 3.50E-06 3.50E-06 1.20E-06 1.10E-06 2.80E-06 2.70E-06 3.50E-06 3.30E-06 1.70E-06 1.60E-06 9.40E47 9.50E47 1.70E48 1.40E-OS 2.00E48 1.70E48 3.90E-OS 3.90E-OS 5.50E-OS 5.60E-OS 5.80E-08 5.80E-08 3.60E-OS 3.70E-OS 8.00E46 S.OOE-06 5.50E-06 5.60E-06 1.70E-06 1.70E-06 1.30E-06 1.30E-06 6.60E-06 6.80E-06 2.40E-06 2.40E-06 5.70E-06 5.80E-06 7.80E-06 7.90E-06 3.70E-06 3.70E-06 2.10E46 2.10E-06 1.70E-08 1.70E-OS 2.00E-OS 2.00E-OS 4.10E-OS 3.00E-OS 6.20E48 4.40E48 5.30E48 4.40E48 2.50E-OS 2.70E-OS 7.70E46 3.00E46 5.10E-06 3.20E-06 1.50E-06 7.40E-07 1.20E-06 S.OOE-07 6.50E-06 5.10E-06 2.20E46 1.90E-06 5.60E46 7.40E-06 7.60E-06 3.60E46 3.50E46 1.60E-06 2.10E46 8.20E48 1.40E48 1.30E-OS 1.70E-OS 1.50E-OS 3.00E-08 4.40E-OS 4.50E-OS 2.80E-OS 3.00E-06 3.30E-06 8.10E-07 8.40E-07 5.20E-06 2.00E46 7.50E-06 3.70E-06 1.60E-06 8.20E-08 1.30E-OS 1.50E-OS 4.10E-OS 6.20E-OS 5.30E-OS 2.50E-08 2.90E46 3.20E-06 8.30E-07 8.30E47 5.40E-06 2.00E-06 7.50E46 3.50E-06 1.50E-06 1.20E-07 1.40E-OS 1.70E-08 2.50E-06 2.60E-06 2.60E-06 3.60E-06 3.60E-06 3.50E46 8.00E-06 S.OOE-06 7.70E-06 7.40E-06 7.50E-06 7.50E-06
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Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Fourth Quarter T.BODY ADULT THYRD SKIN CHILD T.BODY THYRD SKIN T.BODY THYRD T.BODY TIN'RD SKIN N
3.60E-OS 4.30E-08 2.30E48 1.70E-OS 6.40E-07
~ 3.00E-07 3.20E-07 3.10E-07 8.70E-07 1.70E-07 2.50E-07 1.50E-07 2.40E47 1.40E-07 8.40E49 1.70E-08 3.60E48 2.60E48 4.40E-OS 3.20E-OS 2.30E48 1.50E-OS 1.80E-08 1.00E-08 6.70E-07 6.60E47 3.20E-07 3.20E-07 3.40E-07 3.50E-07 3.20E47 3.10E-07 9.00E47 1.10E-06 1.80E-07 1.50E-07 2.60E-07 2.60E-07 1.60E47 1.70E47 2.50E47 2.60E-07 1.50E-07 1.80E-07 8.50E-09 4.70E-09 1.70E-08 1.20E-OS 3.70E-OS 3.80E-08 2.60E-OS 3.50E-OS 3.60E-OS 4.40E-OS 4.60E48 3.20E-OS 4.40E-OS 4.50E-OS 2.30E-OS 2.40E48 1.50E-08 2.30E-OS 2.30E-08 1.80E-OS 1.80E-OS 1.00E-OS 1.80E-08 1.80E-OS 7.90E-07 8.20E-07 8.10E-07 1.30E46 1.40E-06 3.40E-07 3.60E-07 3.70E-07 5.10E-07 5.40E-07 3.60E-07 3.80E47 3.90E47 5.00E47 5.30E-07 3.70E-07 3.80E-07 3.70E-07 5.80E47 6.00E-07 1.00E-06 1.10E-06 1.30E46 1.70E46 1.70E-06 1.90E-07 1.90E-07 1.60E-07 2.40E47 2.50E-07 2.80E-07 2.90E-07 2.80E-07 3.50E47 3.70E47 1.80E-07 1.90E47 1.80E-07 2.40E47 2.60E-07 2.70E-07 2.80E-07 2.80E-07 3.70E-07 3.80E-07 1.50E-07 1.70E-07 1.90E-07 1.90E47 2.10E-07 8.90E-09 9.10E49 4.70E-09 8.90E-09 9.10E-09 1.80E-OS 1.80E-08 1.20E-08 1.80E-OS 1.80E-OS 2.60E-08 3.20E-OS 1.50E-08 1.00E-OS 1.30E-06 5.30E-07 5.30E-07 5.90E-07 1.90E-06 2.20E-07 3.40E-07 2.40E-07 3.70E-07 2.30E-07 4.70E49 1.20E-OS 2.60E-OS 2.70E-OS 3.30E-08 3.40E-OS 1.70E48 1.70E48 1.30E-08 1.30E-08 1.10E-06 1.10E-06 2.50E-07 2.80E-07 2.40E47 2.60E-07 7.40E-07 7.60E47 9.50E47 1.00E46 1.20E-07 1.20E-07 3.00E47 3.20E-07 1.80E47 2.00E47 2.50E47 2.60E-07 1.10E-07 1.20E47 6.50E49 6.60E49 1.40E48 1.40E48 2.60E-OS 3.20E-OS 1.50E48 1.00E-OS 1.20E-06 3.20E-07 3.10E-07 7.80E47 1.30E46 1.30E-07 3.30E-07 2.00E47 2.80E-07 1.70E-07 4.70E-09 1.20E-OS 8.70E-07 9.00E47 1.10E-06 1.00E-06 1.10E-06 1.30E-06 1.70E-06 1.70E-06 1.90E-06 1.10E-06 1.10E-06 1.30E-06
Table 5B Radiation Dose To Nearest Individual From Liquid Releases In REM First Quarter T.BODY BONE THYRD ADULT 9.10E-06 6.90E-06 5.10E-07 TEEN 5.20E-06 7.20E-06 4.60E-07 CHILD 2.00E-06 9.00E-06 7.80E-07 INFANT 1.60E-08 1.20E-07 8.00E-07 Second Quarter T.BODY BONE THYRD 6.80E-06 4.90E-06 2.80E-08 3.90E-06 5.20E-06 2.50E-08 1.50E-06 6.40E-06 4.10E-08 1.10E-08 8.50E-08 4.10E-08 Third Quarter T.BODY BONE THYRD 9.90E-06 7.10E-06 1.10E-07 5.60E-06 7.40E-06 9.70E-08 2.20E-06 9.30E-06 1.60E-07 1.60E-08 1.20E-07 1.60E-07 Fourth Quarter T.BODY BONE
'IKYRD 1.40E-05 1.10E-05 6.30E-07 8.20E-06 1.10E-05 5.70E-07 3.10E-06 1.40E-05 9.70E-07 2.50E-08 1.80E-07 1.00E-06
ROCHESTER GAS 8 ELECTRIC CORPORATION GINNA STATION, NUMBER OF PERSONNEL AHD HAN-REH BY lRRK AND JOB FUNCTION FOR 93/01/01. 93/12/31 ACTUAL MHOLE BODY DOSE NO.
OF PERSONNEL (>
100)
TOTAL MAN REH MORK PERMIT CATERGORY WORK GROUP COHTRACT QRKERS STATION UTILITY EMPLOYEES EMPLOYEES CONTRACT MORKERS STATION EMPLOYEES UTILITY EMPLOYEES REACTOR OPERATIONS t, SURV MAINTENANCE PERSOHHEL OPERATING PERSONNEL HEALTH PHY. PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSOHHEL 110 0
48 12 4
43 27 13 14 1
50 0
0 16 2
1.040 0.000 2.233 0.284 0.202 1.052 4.728 1.136
'1.179 0.041 0.182 0.000 0.000 0.637 0.'143 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHY.
PERSONNEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL 141 0
51 13 3
43
, 20 13 14 1
75 0
3 15 2
7.305 0.000 14.109 0.345 0 ~ 562 5.994 0.249 4.378 1.480 0.162 3.630 0.000 0.330 0.677 0.054 INSERVICE INSPECTION MAINTENANCE PERSONNEL OPERATING PERSONHEL HEALTH PHY. PERSONNEL SUPERVISORY PERSONNEL ENGINEERIMG PERSONNEL 54 0
28'0 1
27 6
8 11 0
44 0
0 14 2
4.464 0.000 1.377 1.224 0.020 1.511 0.228 0.173 0.870 0.000 2.617 0.000 0.000 3.346 0.056 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHY. PERSOHNEL SUPERVISORY PERSOHHEL ENGINEERING PERSONNEL 132 0
34 9
2 42 22 11 5
1 77 0
3 14 1
12.567 5.000 2.651 0.667 0.149 8.672 1.419 1.267 0.513 0.035 8.857 0.000 0.015 0.632 0.000 llASTE PROCESSING MAINTENANCE PERSONNEL OPERATING PERSONNEL HEALTH PHD PERSOHHEL SUPERVISORY PERSONNEL ENGINEERING PERSONNEL 24 0
18 1
0 14 5
1 0
0.452 0 ~ 000 0.634 0.018 0.000 0.291 0.093 0.261 0.021 0.000 0.106 0.000 0.131 0.111 0.000 REFUELING MAINTENANCE PERSONNEL OPERATING PERSOHNEL HEALTH PHD PERSONNEL SUPERVISORY PERSONNEL EHGIHEERIHG PERSOHHEL 33 0
13 3
1 18 8
2 2
1 27 0
0 5
0 9.426 0.000 0.754 0.100 O.128 0.609 2.143 0.339 0.285 O.448 2.160 0.000 0.000 0.120 0 ~ 000 MODIFICATIONS TOTAL HAINTENAMCE PERMNNEL OPERATING PERSONNEL HEALTH PHY.
PERSONHEL SUPERVISORY PERSONNEL ENGIHEERING PERSONNEL MAINTENANCE PERSOHHEL OPERATING PERSONNEL HEALTH PHD
-PERSOHHEL SUPERVISORY PERSOHHEL ENGINEERING PERSONHEL 87 0
21 5
1 172 0
53 14 14 0
3 4
0 43 27 13 14 1
12 0
0 4
1 77 0
3 16 2
8.142 0.000 1.769 0.331 0.000 43.397 0.000 23.527 2.968 1.061 0.447 0.000 0.079 0.083 0.000 18.576 8.859 7.634 4.431 0.686 0.216 0.000 0.000 0.012 0.015 17.768 0.000 0.476 5.535 0.268 GRAND TOTAL RRSSSRSRRkRRRSSSSNSIR 241 97 98 70.953 40.186 24.047
Table 6B STANDARD REPORT OF PERSONNEL WHOLE BODY EXPOSURE 1993 DOSE REM NUMBER OF PEOPLE 00.000 - 00.000 00.001
- 00.100 00.101
- 00.250 00.251
- 00.500 00.501
- 00.750 00.751
- 01.000 01.001
- 02.000 02.001
- 03.000 03.001
- 04.000 04.001
- 05.000 759 370 224 153 58 31 20 0
0 0
Total number of personnel monitored 1615 The total collective dose for 1993 is 193.13 person-rem based on the sum of all personnel TLD badge readings.
FIVE HIGHEST EXPOSURES FOR THE YEAR A
B C
D E
1.838 rem 1.452 rem 1.441 rem 1.436 rem 1.338 rem This report contains all personnel monitored during 1993.