ML17263A160

From kanterella
Revision as of 17:27, 29 October 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept Jul-Dec 1992. W/930226 Ltr
ML17263A160
Person / Time
Site: Ginna Constellation icon.png
Issue date: 12/31/1992
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303040188
Download: ML17263A160 (30)
v • d • e


Text

ACCELERAT DOCUMENT DIST UTION SYSTEM REGULAT INFORMATION DISTRIBUTION 4/STEM (RIDS) lg ACCESSION NBR:9303040188 DOC.DATE: 92/12/31 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Semiannual Radioactive Effluent Release Rept Jul-Dec 1992.'"

W/930226 ltr.

DISTRIBUTION CODE:,IE48D TITLE; 50.36a(a)(2)

COPIES RECEIVED:LTR Semiannual Effluent Release i ENCL Reports g SIZE: D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES A

ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 3 3 PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL: NRR/DRSS/PRPB11 2 2 RE~" XL Ol 1 1 D RGN1 2 2 RGN1 FILE 02 1 1 DRSS/RPB'XTERNAL:

BNL TICHLER,J03 1 1 EGGG SIMPSON,F 2 2 NRC PDR 1 1 D

D NOTE TO ALL"RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15

0 4 j 1

g A

ip I<<<<<<<<<<<<Iggrlr@ZI t

tI'<<<<<<<<IIIIIII(lizztirsz StAtt.

ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649-0001 7 E S. E P N 0 N E AREA CODE 7SSS 546-2700 February 26, 1993 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. Me redy Vice President 040OCB

~

~

I ~~ ~ ~

q808040188 8SS)88$ 4444 PDR ADQCK 05 00 R ~

~

f PDR

~ ~ ~ ~

' ~

g

~

J

~ +'i, h J~~'I

< ~ I) 1 >

4 ~

r,

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 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 JULY DECEMBER, 1992

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 NOT MET 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 ' 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 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 Solid Waste and Irradiated Fuel Shipments Table 4 Release Permits Not Meeting LLD Requirements Table 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

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 require-ments of Technical Specification Section 6.9.1.4. The report covers the period from July 1, 1992 through December 31, 1992.

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 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.

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.

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 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 '.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 ef fluents, 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.

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 0.237 Mev.

2.4 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.

2.5 Batch Releases 2.5.1

1. Number of batch releases: 1.32 E+02
2. Total time period for batch releases: 2.07 E+04 min.
3. Maximum time period for a batch release: 6.76 E+02 min.

Average time period for batch releases: 1.57 E+02 min.

5. Minimum time period for a batch release: 1.4 E+Ol min.
6. Average stream flow (LPM) during periods of release effluent into a flowing stream: 1.28 E+06 LPM 2.5.2 Gaseous
l. Number of batch releases:

Total time period for batch 2.1E+01 2.

releases: 3.95E+04 min.

3. Maximum time period for a batch release: 1.04E+04 min.

Average time period for batch releases: 1.88E+03 min.

5. Minimum time period for a batch release: 2.25E+02 min.

2.6 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 elevated releases.

4.0

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 types'.0 and non-gamma emit ters were calculated from scaling factors determined by an independent laboratory from representative samples of that waste LOWER LIMIT OF DETECTION NOT MET There were no gamma emitting radionuclides that did not meet the required lower limit of detection for liquid releases.

7.0 RADIOLOGICAL IMPACT An assessment of doses to the maximally exposed indivi-dual 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, inhala-tion, 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 SA and SB.

8.0 METEOROLOGICAL DATA The annual summary of hourly meteorological data collected during 1992 is not included with this report, but can be made available at the RE E. Ginna Plant as allowed by Technical Specifications.

9.0 LAND USE CENSUS CHANGES There were no changes in critical receptor location for dose calculations during the reporting period.

10.0 ANNUAL TABULATION OF 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 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.

OCHESTER GAS ELECTRIC CORPORAl N Table 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES JULY - DECEMBER 1992 Unit Quarter Quarter Est. Total A. Fission & activation ases 3RD 4th Error, %

1. Total release CI 4.03E+01 5.95E+01 6.60E+00
2. Avera e release rate for eriod uCi/sec 5.12E+00 7.57E+00
3. Percent of technical s eclfication limit 8.13E-04 1.20E-03 B. Iodines
1. Total iodine-131 CI 1.65E-05 1.45E-05 1.80E+01
2. Avera e release rate for eriod uCi/sec 2.10E-06 1.85E-06
3. Percent of technical s ecification limit 4.62E-03 4.06E-03 C. Particulates
1. Particulates with half-lives > 8da s CI 8.16E-08 8.43E-07 4.00E+01
2. Avera e release rate for eriod uCi/sec 1.04E-08 1.07E-07
3. Percent of technical s ecification limit 7.80E-07 8.06E-06
4. Gross ai ha radioactivit CI D. Tritium
1. Total release CI 7.42E+00 1.81E+01 3.20E+00
2. Avera e release rate for eriod uCi/sec 9.44E-01 2.30E+00
3. Percent of technical s ecification limit 1 11E-04

~ 2.71E-04 E. Carbon-14

1. Total release Ci 7.07E-01 6.07E-01 3.00E+01
2. Avera e release rate for eriod uCi/sec 8.99E-02 7.72E-02
3. Percent of technical s ecification limit 4.78E-06 4.1 1E-06 Note: Isotope for which no value is given were not identified in applicable releases.

OCHESTER GAS ELECTRIC CORPORA N Table 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode Batch Mode Nuclides released Unit Quarter Quarter Quarter Quarter 4th 4th 1 ~ Fission ases a on-41 Ci 1.55E-01 1.32E-01 3.47E-01 1.29E+00 k ton-85 Ci 4.18E-01 1.83E-01 k ton-85m CI 8.70E-02 7.16E-02 2.38E-02 7.81E-02 k ton-87 Ci 1.21E-01 9.63E-02 k ton-88 CI 1.62E-01 1.44E-01 1.96E-02 8.09E-02 xenon-1 31m Ci 4.56E-02 2.09E-02 2.01E-01 1.55E-01 xenon-133 Ci 1.58E+01 1.46E+01 1.65E+01 3.37E+01 xenon-1 33m CI 1.14E+00 1.97E-02 1.76E-01 4.34E-01 xenon-135 Ci 3.09E+00 5.76E+00 4.28E-01 1.41E+00 xenon-135m CI 1.13E+00 9.75E-01 xenon-138 CI 4.10E-01 3.68E-01 others s ecif CI Ci Ci CI Total for eriod CI 2.21E+01 2.22E+01 1.81E+01 3.73E+01

2. Iodines iodine-1 31 Ci 1.65E-05 1.45E-05 iodine-1 33 Ci 1.41E-05 2.33E-05 4.91E-09 iodine-1 35 Ci Total for eriod Ci 3.06E-05 3.78E-05 4.91E-09
3. Particulates strontium-89 CI strontium-90 CI cesium-134 Ci cesium-137 CI 8.16E-08 8.43E-07 other s ecif Ci cobalt-58 Ci cobalt-60 CI Total for eriod CI 8.16E-08 8.43E-07 unidentified Ci 1.18E-06 Note: Isotope for which no value is given were not identified in applicable releases.

OCHESTER GAS ELECTRIC CORPORA N Table 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUID EFFLUENTS - SUMMATIONOF ALL RELEASES JULY- DECEMBER 1992 Unit Quarter Quarter Est. Total A. Fission and activation roducts 3RD 4th Error, %

1. Total release (not including tritium, ases, al ha Ci 1.66E-02 1.33E-02 7.00E+00
2. Average diluted concentration durin eriod uCi/ml 9.74E-11 7.90E-11
3. Percent of a licable limit 1.13E-03 2.10E-03 B. Tritium
1. Total release Ci 2.30E+01 5.15E+01 3.20E+00
2. Average diluted concentration durin eriod uCi/ml 1.35E-07 3.06E-07
3. Percent of a licable limit 4.49E-03 1.02E-02 C. Dissolved and entrained ases
1. Total release Ci 9.25E-04 5.91E-04 4.00E+01
2. Average diluted concentration durin eriod uCi/ml 5.42E-12 3.51E-12
3. Percent of a licable limit 2.71E-08 1.75E-06 D. Gross al ha radioactivit
1. Total release N/A N/A E. Vol. of waste released rior to dilution Liters 2.85E+07 2.25E+07 5.00E+00 F. Vol. of dilution water used durin eriod Liters 1.71E+11 1.68E+11 5.00E+00 Note: Isotope for which no value is given were not Identified in applicable releases.

0 f

4'

OCHESTER GAS ELECTRIC CORPORA N Table 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUALREPORT LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 4th 4th chromium-51 Ci man anese-54 Ci 1.55E-05 3.47E-05 iron-55 Ci iron-59 Ci cobalt-58 Ci 7.49E-07 2.64E-05 2.07E-05 1.75E-06 cobalt-60 Ci 5.94E-05 1.20E-06 zino-65 Ci strontium-89 Ci strontium-90 Ci zirconium/niobium-95 Ci 5.88E-06 mol bdenum-99 Ci silver-110m Ci 1.82E-05 antinon -122 Ci antinon -124 Ci 2.82E-04 9.64E-05 antinon -125 Ci 1.90E-04 1.70E-04 iodine-1 31 Ci 5.31E-05 6.60E-06 1.23E-04 6.09E-04 iodine-1 33 Ci 2.58E-05 3.39E-05 4.34E-04 iodine-135 Ci 3.1 8E-05 3.65E-05 2.97E-04 cesium-134 Ci 1.87E-06 5.05E-06 8.06E-03 5.68E-03 cesium-1 36 Ci cesium-1 37 Ci 9.61E-05 1.27E-04 7.65E-03 5.74E-03 barium/lanthanum-140 Ci cerium-141 Ci Sn-117m Ci Te-131m Ci Total for eriod above Ci 2.09E-04 2.36E-04 1.64E-02 1.31E-02 unidentified Ci xenon-133 Ci 9.10E-04 5.14E-04 xenon-1 35 Ci 1.51E-05 7.62E-05 Note: Isotope for which no value is given were not identiTied in applicable releases.

i 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 0
a. Spent resins, filter eva orator bottoms etc.

sludges, 1,76 E+01 2.0E+00 Ci 2.96 E+02 2.0E+01

b. Dry compressible waste, con- 3.35 E+01 2.0E+00 taminated e i etc. 1.33 E+00 2.0E+01
c. Irradiated components, control m rods etc. Ci
d. Other (describe)

Ci 2 ~ Estimate of major nuclide composition (by type of waste)

a. Co-60 2.83 E+01 Ni-63 2.83 E+01 Cs-137 1.61 E+01 Cs-134 1.09 E+01 Fe-55 7.4 E+00 Co-58 6.1 E+00 Mn-54 1.0 E+00 Sb-125 8.0 E+00 b.Fe-55 4.88 E+01 Cs-137 2.30 E+01 Cs-134 1.06 E+01 Co-60 8.3 E+00 Ni-63 5.2 E+00 Mn-54 2.0 E+00
  • Volume and activity buried by waste processor duxing this period.
3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination
    • Sole use truck Barnwell, SC Sole use truck Oak Ridge, TN
    • Transported directly to Barnwell
      • Transported 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

RELEASE PERMITS NOT MEETING LLD REQUIREMENTS No. Date Isoto es Cause None

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem First Quarter Adult Teen Child Infant Total Skin Thyroid Total Skin Thyroid Total Skin Thyroid Total Skin Thyroid Direction Body Body N 9.7E48 1.3E47 9.8E48 9.8E48 1.3E47 9.9E48 9.5E48 1.3E47 9.5E48 7.8E48 1.3E47 7.9E48 7.9E48 1.1 E47 7.9E48 8.0E48 1.1E47 8.0E48 7.7E48 1.1E47 7.7E48 6.5E48 1.1E47 6.5E48 NE 7.1E48 9.7E48 7.2E48 7.3E48 9.7E48 7.3E48 7.1 E48 9.7E48 7.1 E48 5.9E48 9.7E48 5.9E48 ENE 5.7E48 7.5E48 5.7E48 5.9E48 7.5E48 5.9E48 5.9E48 7.5E48 5.9E48 4.9E48 7.5E48 4.9E48 E 6.6E47 7.9E47 6.7E47 7.3E47 8.4E47 7.4E47 9.5E47 1.0E46 9.7E47 5.6E47 7.9E47 5.7E47 ESE 1.2E48 1.3E46 1.2E46 1.6E48 1.7E46 1.6E46 3.2E46 3.2E46 3.2E46 5.8E47 7.7E47 6.1E47 9.7E47 1.2E46 9.8E47 1.2E46 1.4E46 1.2E46 2.1E46 2.3E48 2.1E46 6.5E47 9.4E47 6.7E47 SSE 4.2E47 5.3E47 4.3E47 4.8E47 5.7E47 4.8E47 6.6E47 7.2E47 6.7E47 4.3E47 5.8E47 4.5E47 S 1.3E46 1.5E48 1.3E46 1.5E46 1.6E48 1.5E46 2.3E46 2.3E46 2.3E46 1.0E46 1.4E48 1.1E46 SSW 8.0E47 8.3E47 8.1 E47 9.3E47 9.4E47 9.5E47 1.4E46 1.3E46 1.4E46 S.0E47 7.3E4T 7.3E47 SW 1.0E46 1.2E46 1.0E46 1.1E46 1.3E46 1.2E46 1.5E46 1.7E46 1.6E46 7.7E47 1.2E46 8.1E47 WSW 4.3E47 5.2E47 4.3E47 4.9E47 5.7E47 4.9E47 7.0E47 7.5E47 7.1 E47 3.5E47 5.2E47 3.7E47 W 3.0E47 4.1E47 3.0E47 3AE47 4.4E47 3.4E47 4.5E47 5.4E47 4.5E47 3.0E47 4.4E47 3.0E47 WNW 2.1 E47 3.5E47 2.1 E47 2.2E47 3.5E47 2.2E47 2.3E47 3.5E47 2.3E47 1.9E47 3.5E47 1.9E47 NW 2.5E48 2.8E48 2.5E48 2.5E48 2.8E48 2.5E48 2.4E48 2.8E48 2.4E48 1.9E48 2.8E48 1.9E48 NNW 4.9E48 6.5E48 4.9E48 5.0E48 6.5E48 5.0E48 4.8E48 6.5E48 4.8E48 4.0E48 6.5E48 4.0E48 1.3E48 1.5E46 1.3E46 1.6E46 1.7E46 1.6E46 3.2E46 3.2E46 3.2E46 1.0E46 1.4E46 1.1E46

4~

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Second Quarter Adult Teen Child Infant Total Skin Thyroid Total Skin Thyroid Total Skin Thyroid Total Sldn Direction N 2.6E48 2.3E48 3.6E48 2.7E48 2.3E48 3.9E48 2.7E48 2.3E48 4.1 E48 2.1E48 2.3E48 3.3E48 3.8E48 4.3E48 4.9E48 4.0E48 4.3E48 5.3E48 4.0E48 4.3E48 5.5E48 3.2E48 4.3E48 4.6E48 3.0E48 3.3E48 3.8E48 3.1E48 3.3E48 4.1 E48 3.1E48 3.3E48 4.1E48 2.4E48 3.3E48 3.4E48 ENE 5.8E48 1.2E47 6.7E48 5.9E48 1.2E47 7.1 E48 5.9E48 1.2E47 7.2E48 5.3E48 1.2E47 6.5E48 4.1 E46 9.5E46 4.5E46 4.4E46 9.7E46 4.8E46 5.4E46 1.1E45 5.9E46 3.9E46 9.5E46 4.5E46 ESE 4.2E46 9.8E46 4.7E46 4.5E46 1.0E45 5.0E46 5.3E46 1.1E45 6.0E46 4.1 E46 9.9E46 4.8E46 SE 1.5E46 2.7E46 1.8E46 1.6E46 2.8E46 2.0E46 2.1E46 3.2E46 2.5E46 1.5E46 2.9E46 2.0E46 SSE 5.5E47 4.7E47 7.9E47 6.4E47 5.2E47 9.3E47 9.0E47 7.3E47 1.3E46 7.5E47 7.2E47 1.1 E46 8.4E47 8.0E47 1.1E46 1.0E46 9.2E47 1.3E46 1.5E46 1.4E46 1.9E46 9.8E47 1.0E46 1.4E46 SSW 1.1E46 8.6E47 1.4E46 1.3E46 1.0E46 1.7E46 2.0E46 1.6E46 2.5E46 9.1E47 8.8E47 1.4E46 SW 3.4E46 3.3E46 3.7E46 4.8E46 4.7E46 5.2E46 9.9E46 9.7E46 1.0E45 4.5E46 4.5E46 4.1E46 WSW 2.3E46 2.2E46 2.6E46 3.1E46 3.0E46 3.5E46 6.2E46 6.0E46 6.8E46 4.6E46 4.6E46 5.3E46 W 1.3E46 1.2E46 1.5E46 1.8E46 1.7E46 2.1 E46 3.5E46 3.3E46 3.8E46 2.5E46 2.4E46 2.8E46 WNW 2.4E47 2.1E47 2.9E47 2.9E47 2.5E47 3.5E47 4.6E47 4.0E47 5.4E47 1.2E47 1.4E47 1.8E47 NW 9.5E49 8.2E49 1.1 E48 9.8E49 8.2E49 1.2E48 9.6E49 8.2E49 1.2E48 7.3E49 8.2E49 9.6E49 NNW 1.9E48 1.5E48 2.5E48 2.0E48 1.5E48 2.7E48 2.1 E48 1.5E48 2.9E48 1.6E48 1.5E48 2.3E48 4.2E46 9.8E46 4.7E46 4.8E46 1.0E45 5.2E46 9.9E46 1.1 E45 1.0E45 4.6E46 9.9E46 5.3E46

II 4 Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Third Quarter Adult Teen Child Infant Total Skin Thyroid Total Skin Thyroid Total Sldn Thyroid Total Skin Thyroid Direction Body N 3.7E48 5.1E48 3.7E48 3.8E48 5.1E48 3.8E48 3.8E48 5.1E48 3.8E48 3.2E48 5.1E48 3.3E48 NNE 6.0E48 1.1E47 6.0E48 6.1E48 1.1E47 6.1E48 6.0E48 1.1E47 6.1 E48 5.5E48 1.1 E47 5.5E48 3.2E48 5.4E48 3.3E48 3.3E48 5.4E48 3.3E48 3.3E48 5.4E48 3.3E48 2.9E48 5.4E48 3.0E4S ENE 2.4E48 3.7E48 2.4E48 2.4E48 3.7E48 2.4E48 2.4E48 3.7E48 2.4E48 2.1 E48 3.7E48 21E48 1.3E46 1.6E46 1.4E46 1.SE46 2.0E46 1.9E46 3.6E46 3.7E46 3.7E46 1.1 E46 1.4E46 1.2E46 ESE 1.4E46 1.7E46 1.5E46 1.SE46 2.1 E46 1.9E46 3.4E46 3.6E46 3.5E46 1.1E46 1.5E46 1.3E46 SE 9.5E47 1.3E46 9.9E47 1.2E46 1.5E46 1.2E46 2.0E46 2.2E46 20E46 8.5E47 1.3E46 9.5E47 SSE 7.2E47 9.1E47 7.5E47 9.4E47 1.1E46 9.6E47 1.7E46 1.9E46 1.8E46 7.0E47 9.4E47 7.8E47 3.1E46 3.5E46 3.2E46 4.5E48 4.9E46 4.6E46 9.8E48 1.0E45 9.9E48 3.6E46 4.1E46 3.7E48 SSW 9.2E47 1.1 E46 9.6E47 1.2E46 1.4E48 1.2E46 2.2E46 2.4E46 2.3E46 5.7E47 8.7E47 6.2E47 SW 1.3E46 1.7E46 1.4E48 1.6E46 2.0E46 1.7E46 2.8E46 3.1E46 2.9E46 1.2E46 1.7E46 1.4E46 WSW 7.9E47 9.4E47 8.1E47 1.0E46 1.2E46 1.0E46 1.8E46 1.9E46 1.9E46 9.3E47 1.2E46 1.0E46 W 1.5E-06 1.7E46 1.6E46 2.2E46 2.4E46 2.2E46 4.8E46 4.8E46 4.8E48 21E46 2.3E46 2.1 E46 WNW 4.4E47 5.4E47 4.5E47 6.3E47 7.2E47 6.3E47 1.3E46 1.4E46 1.3E46 1.4E46 2.4E47 1.4E47 NW 9.2E49 12E48 9.2E49 9.7E49 1.2E48 9.8E49 1.0E4S 1.2E4S 1.0E48 8.3E49 1.2E48 8.4E49 NNW 1.7E48 2.2E48 1.7E48 1.8E48 2.2E48 1.8E48 1.9E48 2.2E48 1.9E48 1.6E48 2.2E48 1.6E48 3.1 E46 3.5E46 3.2E46 4.5E46 4.9E46 4.6E46 9.8E46 1.0E45 9.9E46 3.6E46 4.1E46 3.7E46

'

~ ~

k lw~

II

Rochester Gas and Electric Table 5A Radiation Doses to Nearest Individual Receptor From Gaseous Releases in Rem Fourth Quarter Adult Teen Child Infant Total Skin Thyroid Total Thyroid Total Skin Total SMn Thyroid Direction N 1.6E47 3.5E47 1.7E47 1.7E47 3.5E47 1.7E47 1.6E47 3.5E47 1.7E47 1.5E47 3.5E47 1.6E47 NNE 1.0E47 2.1E47 1.0E47 1.0E47 2.1E47 1.1E47 1.0E47 2.1 E47 1.1 E47 9.3E48 2.1E47 9.6E48 NE 6.7E48 1.2E47 7.1E48 6.9E48 1.2E47 7.4E48 7.0E48 1.2E47 7.5E48 6.2E48 1.2E47 6.7E48 ENE 1.3E47 2.8E47 1.3E47 1.3E47 2.8E47 1.4E47 1.3E47 2.8E47 1.4E47 1.2E47 2.8E47 1.3E47 3.2E46 7.5E46 3.3E46 3.2E46 7.5E46 3.4E46 3.2E46 7.5E46 3.4E46 3.1E46 7.5E46 3.2E46 ESE 2.3E46 4.1E46 2.6E46 24E46 4.1E46 2.7E46 2.4E46 4.1E46 2.7E46 2.2E46 4.1 E46 2.5E46 SE 3.3E46 6.3E46 3.5E46 3.3E46 6.3E46 3.6E46 3.3E46 6.3E46 3.6E46 3.1E46 6.3E46 3.4E46 SSE 1.6E46 3.3E46 1.7E46 1.6E46 3.3E46 1.7E46 1.6E46 3.3E46 1.7E46 1.5E46 3.3E46 1.6E46 2.2E46 4.7E46 2.2E46 2.2E46 4.7E46 2.2E46 2.2E46 4.7E46 2.2E46 2.1E46 4.7E46 2.1E46 SSW 1.2E46 2.7E46 1.3E46 1.3E46 2.7E46 1.3E46 1.3E46 2.7E46 1.3E46 1.2E46 2.7E46 1.2E46 SW 9.0E47 2.0E46 9.0E47 9.1E47 2.0E46 9.2E47 9.2E47 2.0E46 9.2E47 8.8E47 2.0E46 8.8E47 WSW 8.6E47 2.2E46 8.9E47 8.7E47 2.2E46 9.0E47 8.8E47 2.2E46 9.1E47 8.5E47 2.2E46 8.8E47 W 1.5E46 3.6E46 1.5E46 1.5E46 3.6E46 1.5E46 1.5E46 3.6E46 1.5E46 1.4E46 3.6E46 1.4E46 WNW 9.8E47 2.7E46 9.9E47 9.8E47 2.7E46 1.0E46 9.8E47 2.7E46 1.0E46 9.7E47 2.7E46 9.9E47 NW 4.6E48 9.5E48 4.6E48 4.7E48 9.5E48 4.7E48 4.7E48 9.5E48 4.8E48 4.3E48 9.5E48 4.3E48 NNW 1.0E47 2.0E47 1.1 E47 1.0E47 2.0E47 1.1 E47 1.0E47 2.0E47 1.1E47 9.3E48 2.0E47 9.8E48 3.3E46 7.5E46 3.5E46 3.3E46 7.5E46 3.6E46 3.3E46 7.5E46 3.6E46 3.1E46 7.5E46 3.4E46

Table 5B RADIATION DOSE TO NEdLREST INDIVIDUAL FROM LIQUID RELEASES IN REM Adult Teen Child Infant First Quarter Total Body 9.7E-06 5.5E-06 2 'E-06 1.6E-08 Bone 7.2E-06 7.6E-06 9.4E-06 1.3E-07 Thyroid 1.4E-07 1.3E-07 2.2E-07 2.2E-07 Second Quarter Total Body 2.1E-05 1.2E-OS 4.9E-06 2.2E-06 Bone 1.7E-05 1.8E-05 2.2E-OS 1.8E-06 Thyroid 1.6E-06 1.5E-06 2.5E-06 2.6E-06 Third Quarter Total Body 1.3E-OS 7.6E-06 2.9E-06 2.2E-08 Bone 9.8E-06 1.5E-OS 1.3E-OS 1.7E-07 Thyroid 3.9E-08 3.5E-08 5.7E-08 5.8E-08 Fourth Quarter Total Body 7.3E-OS 4.2E-05 1.6E-05 1.6E-07 Bone 5.4E-05 5.7E-OS 7.0E-05 1.0E-06 Thyroid 1.5E-05 1.3E-OS 2.2E-05 2.3E-OS

TABLE 6A ROCHESTER GAS & ELECTRIC CORPORATIOH GIHNA STATIOH NUMBER OF PERSOHHEL AND MAH-REM BY WORK AND JOB FUHCTIOH FOR 92/01/01 - 92/12/31 ACTUAL WHOLE BODY DOSE HO. OF PERSOHHEL (P 100) TOTAL MAH-REM CONTRACT STATION UTILITY CONTRACT STAT IOH UTILITY WORK PERMIT CATERGORY WORK GROUP WORKERS EMPLOYEES EHPLOYEES WORKERS EMPLOYEES EMPLOYEES REACTOR OPERATIONS & SURV MAIHTEHANCE PERSOHNEL 121 47 64 0 '98 1.874 0.182 OPERATING PERSONNEL 3 30 1 0.048 5.382 0.019 HEALTH PHY. PERSONNEL 43 15 1 8.756 3.174 0.000 SUPERVISORY PERSONNEL 17 16 18 0.704 3.521 1.577 ENGIHEERIHG PERSONNEL 9 2 6 0.118 0 ~ 015 0.169 ROUT I HE MAINTENANCE MAIHTEHAHCE PERSOHHEL 208 47 135 20.626 8.944 9.146 OPERATIHG PERSONNEL 0 26 0 0.000 0.352 0.000 HEALTH PHD PERSONNEL 35 15 2 5.552 3.585 0.238 SUPERVISORY PERSOHNEL 'l6 16 17 1.183 0.898 1.619 ENGIHEERIHG PERSOHHEL 13 2 5 2.612 0.563 2.804 INSERVICE INSPECTION MAINTEHAHCE PERSOHHEL 70 18 19.346 0 '40 0.953 OPERATING PERSONNEL 0 0 0.000 0.012 0.000 HEALTH PHY. PERSONNEL 5 0 0.155 0.020 0.000 SUPERVISORY PERSONNEL 10 6 1.112 0.451 0.471 EHGIHEERIHG PERSONNEL 0 0 0.000 0.000 0.000 SPECIAL MAINTENAHCE MAINTENANCE PERSOHHEL 196 4'I 135 53.567 4.827 45.958 OPERATING PERSONHEL 0 25 0 0.000 1.916 0.000 HEALTH PHY. PERSONHEL 19 11 0 1.122 2 ~ 110 0.000 SUPERVISORY PERSONHEL 12 15 15 2.447 1.553 0.645 EHGIHEERIHG PERSOHHEL 4 1 1.290 0.225 0.085 WASTE PROCESSING MAINTENANCE PERSONNEL 22 0.169 0.000 0.000 OPERATING PERSOHHEL 0 0.000 0.000 0.000 HEALTH PHY. PERSOHNEL 1 0.000 0.000 0.000 SUPERVISORY PERSONNEL 0 0.000 0.000 0.000 EHGINEERIHG PERSOHNEL 0 0.000 0.000 0.000 REFUELIHG MAIHTEHAHCE PERSOHHEL 56 21 22 8.893 0.883 2.408 OPERATING PERSONNEL 0 9 0 0.000 2.522 0 F 000 HEALTH PHY. PERSONNEL 2 2 0 0.009 0.164 0.000 SUPERVISORY PERSONHEL 2 3 5 0.005 0.420 0.065 ENGINEERING PERSONNEL 1 2 0 0.000 0.308 0.000 MODIFICATIONS MAINTENANCE PERSOHHEL 69 8.554 0.008 0.370 OPERATING PERSONNEL 0 0.000 0.038 0.000 HEALTH PHY. PERSOHHEL 1 0.000 0.000 0.000 SUPERVISORY PERSONNEL 7 0.349 0.095 0.995 EHGIHEERIHG PERSOHHEL 0 0.000 0.000 0.010 TOTAL MAINTENANCE PERSOHHEL 221 48 139 111.753 16.776 59.017 OPERATIHG PERSONNEL 3 30 1 0.048 10.222 0.019 HEALTH PHY. PERSOHHEL 44 15 2 15.594 9.054 0.238 SUPERVISORY PERSONHEL 18 17 18 4.799 6.938 5.372 ENGIHEERIHG PERSONNEL 14 2 6 4.020 1 '11 3.069 GRAND TOTAL 109 163 137.214 67.715 294 44.101

Table 6B STANDARD REPORT OF PERSONNEL WHOLE BODY EXPOSURE 1992 DOSE REM NUMBER OF PEOPLE 00.000 00 000 F 818 00.001 00.100 288 00.101 00.250 165 00.251 00.500 185 00.501 00.750 108 00.751 01.000 56 01.001 02.000 30 02.001 03.000 0 03.001 04.000 0 04.001 05.000 0 Total number of personnel monitored 1650 The total collective dose for 1992 is 260.947 person-rem based on the sum of all personnel TLD badge readings.

FIVE HIGHEST EXPOSURES FOR THE YEAR A 1.573 rem B 1.432 rem C 1.430 rem D 1.404 rem E 1.403 rem This report contains all personnel mon'itored during 1992.

Retrieved from "https://kanterella.com/w/index.php?title=ML17263A160&oldid=1997723"