ML20087H453
| ML20087H453 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1994 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505020344 | |
| Download: ML20087H453 (100) | |
Text
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South:rn Nuct:ar O:>erating Company Post Offic3 Box 1295 Birm;nghim. Alab ma 35201 Telephone (205) 668-5131 h k o... uor.y Vice President Southern Nudear Operating Company Farley Project the Southern eleC!flC System April 26, 1995 Docket Nos.:50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Atmual Radinactive Effluent Release Renort Ladies and Gentlenen:
In accordance with the Unit I and Unit 2 Technical Specifications, Sections 6.9.1.8 and 6.9.1.9, the FNP Annual Radioactive Efiluent Release Report for 1994 is hereby submitted.
Should you have any questions, please advise.
Respectfully submitted, f f N Let.
Dave Morey WHO/ cit:cffirept. doc '
Enclosure cc: Mr. S. D. Ebneter Mr. B. L. Siegel Mr. T. M. Ross 9505020344 941231 PDR ADOCK 05000348 R PDR y
SOUTHERN NUCLEAR OPERATING COMPANY FARLEY NUCLEAR PLANT UNIT NO. ONE LICENSE NO. NPF-2 AND FARLEY NUCLEAR PLANT UNIT NO. TWO LICENSE NO. NPF-8 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALENDAR YEAR 1994
FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SECTION TITLE PAGE
1.0 INTRODUCTION
1 2.0 LIQUID EFFLUENTS 3 2.1 ODCM Limits 3 2.2 Measurements and Approximation 3 of Total Radioactivity 2.3 Abnormal Releases 4 2.4 Batch Releases 4 2.5 Release Summaries 9 2.5.1 Liquid Effluents - Summation of 9 All Releases 2.5.2 Liquid Effluents - Continuous 16 and Batch Releases 2.6 Radiological Impact 29 3.0 GASEOUS EFFLUENTS 35 3.1 ODCM Limits 35 3.2 Measurements and Approximation 35 of Total Radioactivity 3.3 Abnormal Releases 36 3.4 Batch Releases 37 i
3.5 Rolca2a Summaries- 42 3.5.1 Gaseous Effluents - Summation of 42 All Releases 3.5.2 Gaseous Effluents - Mixed Mode 49 Releases 3.5.3 Gaseous Effluents - Ground Mode 58 Releases 3.6 Radiological Impact 65 4.0 SOLID WASTE 75 5.0 ONSITE DOSES TO MEMBERS OF 82 THE PUBLIC 6.0 MISCELLANEOUS 89 6.1 Total Dose From Uranium Fuel Cycle 89 6.2 Licensee Initiated Changes to 89 the ODCM 6.3 Program Deviatf.vns 89 6.4 Major Changes to the Radwaste 90 Treatment Systems
FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLES PAGE 1-4A Liquid Effluents - Batch Release 5 Summary, Unit 1 1-4B Liquid Effluents - Batch Release 7 Summary, Unit 2 1-1A Liquid Effluents - Summation of 10 All Releases, Unit 1 1-1B Liquid Effluents - Summation of 12 All Releases, Unit 2 1-1C Liquid Effluents - Summation of 14 All Releases, Site 1-2A Liquid Effluents - Continuous 17 and Batch Releases, Unit 1 1-2B Liquid Effluents - Continuous 21 and Batch Releases, Unit 2 1-2C Liquid Effluents - Continuous 25 and Batch Releases, Site 1-3A Doses to a MENBER OF THE PUBLIC 30 Due to Liquid Releases, Unit 1 1-3B Doses to a NEMBER OF THE PUBLIC 32 Due to Liquid Releases, Unit 2 1-5 Typical Liquid MDC's Achieved 34 on Counting System 2-6A Gaseous Effluents - Batch Release 38 Summary, Unit 1 2-6B Gaseous Effluents - Batch Release 40 Summary, Unit 2
f-FARLEY NUCLEAR PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE ' LIST OF TABLES PAGE 2-1A Gaseous Effluents - Summation of 43 All Releases, Unit 1 2-1B Gaseous Effluents - Summation of 45 All Releases, Unit 2 2-1C Gaseous Effluents - Summation of 47 All Releases, Site 2-2A Gaseous Effluents - Mixed Mode 50 Level Releases, Unit 1 2-2B Gaseous Effluents - Mixed Mode 53 Level Releases, Unit 2 2-2C Gaseous. Effluents - Mixed Mode 55 Level Releases, Site 2-3A Gaseous Effluents - Ground 59 Level Releases, Unit 1 2-3B Gaseous Effluents - Ground 61 Level Releases, Unit 2 2-3C Gaseous Effluents - Ground 63 Level Releases, Site 2-4A Air Doses Due to Gaseous 66 Releases, Unit 1 2-4B Air Doses Due to Gaseous- 68 Releases, Unit 2 2-5A Doses to a MEMBER OF THE PUBLIC 70 Due to Radiciodines, Tritium, and Particulates in Gaseous Releases, Unit 1 2-5B Doses to a MEMBER OF THE PUBLIC 72 Due to Radiciodines, Tritium, and Particulates in Gaseous Releases, Unit 2 2-7 Typical Gaseous MDC's Achieved 74 on Counting System 3 Solid Waste and Irradiated 76 Fuel Shipments
1.0 IN7RODUCTION In accordance with Technical Specification (TS) 6.9.1.8 and 6.9.1.9 and Offsite Dose Calculation Manual (ODCM) 7.2, this Annual Radioactive Effluent Release Report covers the operations of the Farley Nuclear Plant (FNP) during 1994.
Information regarding the radioactive liquid and gaseous effluents and solid wasce releases are summarized in formats similar to those provided in the Nuclear Regulatory Commission (NRC) Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants", Revision 1, June 1974. In addition the report includes required or appropriate information regarding meteorology, dose assessment and other pertinent matters.
Detailed information on liquid effluents is provided in Section 2.
The quantities of the radioactive effluents (including any unplanned releases) are summarized on a quarterly basis. A tabulation of the total body and organ doses which were calculated in accordance with ODCM 2.4 are presented to show conformance with the limits of ODCM 2.1.3.
Detailed information on gaseous effluents similar to that for liquid effluents is provided in Section 3. Tabulations are provided of the offsite air doses calculated in accordance with ODCM 3.4.2 to show conformance with the limits of ODCM 3.1.3, and the offsite organ doses to a member of the public calculated in accordance with ODCM 3.4.3 to show conformance with the limits of ODCM 3.1.4.
Detailed information as specified by ODCM 7.2.2.4 on any solid radwastes shipped offsite is provided in Section 4. The data is summarized on a semiannual basis.
Assessments of the doses to members of the public due to their activities inside the site boundary are provided in Section 5.
These assessments are performed as specified by ODCM 6.2.
A number of miscellaneous matters are addressed in Section 6.
These are matters which require reporting only under certain conditions. The alphabetized list given below includes the conditional matters addressed.
A. An assessment of the radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources to show conformance with 40CFR190, should a determination be required by ODCM 5.1.2.
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B. Any licensco initiated changes to the ODCM purcuant to TS 6.14 including changes to the sampling locations in the Radiological l Environmental Monitoring Program pursuant to ODCM 4.1.1.2.3 or 1 4.1.2.2.2, or changes in the location of the controlling dose receptor identified in ODCM 3.4.3 pursuant to ODCM 4.1.2.2.1.
C. Discussions of deviations in the Radioactive Effluent Control Program pursuant to ODCM 7.2.2.6.
D. Any major changes to the liquid or gaseous radwaste treatment systems initiated by the licensee as required by ODCM 2.1.5 and 3.1.6, respectively, or to the colid radwaste treatment system pursuant to the Process Control Program (PCP) App. B section B.4.1.
Meteorological data are retained onsit.e; these data are available to the NRC upon request. The meteorological data include annual as well as quarterly summaries of hourly measurements of wind speed, wind direction and atmospheric stability in the form of joint frequency distribution tables.
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2.0 LIQUID EFFLUENTS This section contains applicable ODCM limits for liquid effluents as well as the quantities of radioactive liquid effluents released during 1994. These quantities are summarized on a quarterly basis and include any unplanned releases. A tabulation of the total body and organ doses which were calculated in accordance with ODCM 2.4 are presented to show conformance with the limits of ODCM 2.1.3.
2.1 ODCM Limits In accordance with Technical Specifications 6.8.3.e(ii) and 6.8.3.e(iii), the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited at all times to ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1E-04 uCi/ML total activity.
In accordance with Technical Specifications 6.8.3.e(iv) and 6.8.3.e(v), the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see ODCM Figure 10-1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
2.2 Measurements and Approximation of Total Radioactivity The radionuclides listed below are considered when evaluating liquid effluents:
-IN- 5 4 CS-134
/E-59 CS-137 CO-58 CE-141 CO-60 CE-144 ZN-65 MO-99 SR-89 FE-55 SR-90 H-3 I-131 5
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Batch Releasco: Representativo pre-release grab'camplos are obtained and analyzed in accordance with ODCM Table 2-3.
-Isotopic analyses are performed using the computerized pulse height analysis system utilizing high resolution germanium !
detectors. Isotopic values thus obtained are used for release i rate calculations as specified in the ODCM. Only those nuclides that are detected are used in the calculations. Strontium l determinations are made by performing a chemical separation and i counting the isotope thus separated using a 2 pi gas flow l proportional counter. Gross beta and gross alpha determinations '!
are made using 2_pi gas flow proportional counters. Tritium and i Iron 55 determinations are made.using liquid scintillation !
techniques. Dissolved gases are deterr.ined employing grab sampling [
techniques and then counting on the pulse height analyzer. ;
i Continuous Releases: Continuous releases are analogous to batch f releases except that they are analyzed on a weekly composite i basis in accordance,with ODCM Table 2-3. }
The maximum error associated with volume and flow measurements, ;
based upon plant calibration practice is estimated to be + or - i 10%. The average error associated with counting is estimated to !
be less than + or - 15%. !
l 2.3 Abnormal Releases i :
There were no abnormal liquid releases on either Unit 1 or Unit 2 l during 1994. ;
2.4 Batch Releases !
.t Batch release information for Units 1 and 2 is. summarized in the i following tables: l
! Unit 1 1994 Liquid Batch Releases : Table 1-4A !
Unit 2 1994 Liquid Batch Releases : Table 1-4B l
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TABLE 1-4A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Batch Release Summary Unit: 1 Starting : 1-Jan-1994 Ending : 30-Jun-1994 5
LIQUID RELEASES NUMBER OF BATCH RELEASES : 330 TOTAL TIME PERIOD FOR BATCH RELEASES : 28479.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 280.00 FINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 86.30 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 62.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 8.89E+03 CFS *
- Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.
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J TABLE 1-4A Joseph M.,Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Batch Release Summary Unit: 1 Starting : 1-Jul-1994 Ending : 31-Dec-1994
....___.. ......______............................................... __........ i LIQUID RELEASES NUMBER OF BATCH RELEASES : 132 ;
TOTAL TIME PERIOD FOR BATCH RELEASES : 11103.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 120.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 84.11 MINUTES
< MINIMUM TIME PERIOD FOR A BATCH RELEASE : 14.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF ,
RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 1.27E+04 CFS
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- Average River Flow Rate, taken at Walter F. George Lock and Dam, located ;
30.7 miles above Farley Nuclear Plant.
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i TABLE 1-4B ;
Joseph M. Farley Nuclear-Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 :
Liquid Effluents -' Batch Release Summary :
Unit: 2 l Starting : 1-Jan-1994 Ending : 30-Jun-1994 l i
LIQUID RELEASES l NUMBER OF BATCH RELEASES : 144 j TOTAL' TIME PERIOD FOR BATCH RELEASES : 12723.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 141.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES : 88.35' MINUTES ,
MINIMUM TIME PERIOD FOR A BATCH RELEASE : 60.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF ;
RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 8.89E+03 CFS
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- Average River Flow Rate, taken at Walter F. George Lock and Dam, located 30.7 miles above Farley Nuclear Plant.
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TABLE 1-4B Joseph'M. Farley Nuclear Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 !
Liquid Effluents - Batch Release Summary >
Unit: 2 .j Starting : Jul-1994 Ending : 31-Dec-1994 ;
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f LIQUID RELEASES l NUMBER OF BATCH RELEASES : 127 :
TOTAL TIME PERIOD FOR BATCH RELEASES : 11688.67 MINUTES I MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 133.00 MINUTES '
AVERAGE TIME PERIOD FOR BATCH RELEASES : 92.04 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE : 72.00 MINUTES AVERAGE STREAM FLOW DURING PERIODS OF >
RELEASE OF LIQUID EFFLUENT INTO A FLOWING STREAM : 1.27E+04 CFS
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- Average River Flow Rate, taken at Walter F. George Lock and Dam, located .
30.7 miles above Farley Nuclear Plant.
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2.5 Release Summaries This section contains the summaries of all radioactive liquid
' effluents released for Units 1 and 2 during 1994. Typical liquid Minimum Detect.able Concentrations (MDC'S) for analyses are
- in Table 1-5 of this section. Regulatory Guide 1.21 Table 2A is l found in this report as Tables 1-1A, 1-1B, and 1-1C. Regulatory
- Guide 1.21 Table 2B is found in this report as Tables 1-2A, 1-2B, q and 1-2C.
i 2.5.1 Liquid Effluents - Summation of All Releases !
l The summations of all liquid effluent releases are contained i
in the following tables- ;
Unit 1 1994 Summation of All Releases : Table 1-1A f i Unit 2 1994 Summation of All Releases : Table 1-1B
] Site 1994 Summation of All Releases : Table 1-1C l
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TABLE 1-1A Joseph M. Farley Nuclear Plant J ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Summation of All Releases Unit: 1 Starting : 1-Jan-1994 Ending : 30-Jun-1994 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 3.27E-02 7.58E-02 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.02E-09 4.33E-09
- 3. PERCENT OF APPLICABLE LIMIT % *
- B. TRITIUM
- 1. TOTAL RELEASE CURIES 2.56E+02 9.34E+01 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/N1, 1.59E-05 5.34E-06
- 3. PERCENT OF APPLICABLE LIMIT % *
- C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 5.21E-02 7.89E-04 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.23E-09 4.51E-11
- 3. PERCENT OF APPLICABLE LIMIT % *
- D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 4.03E-05 4.21E-05 2.50E+01 i i I i
, E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 6.15E+07 6.97E+07 1.00E+01 ,
l F. VOLUME OF DILUTION WATER USED LITERS 1.61E+10 1.74E+10 1.00E+01 '
O Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
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i TABLE 1-1A
- Joseph M. Farley Nuclear Plant l ANNUAL RADIOACTIVE EFFLUElff RELEASE REPORT - 1994 i Liquid Effluents - Summation of All Releases i
Unit: 1 Starting : Ending : 31-Dec-19!I4 !
1-Jul-1994 <
s 4 I i i i TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT '
i ERROR %
............................... ......................___....................... l l
J A. FISSION & ACTIVATION PRODUCTS j _________...................... ...._............................................ ;
- 1. TOTAL RELEASE (NOT INCLUDING l TRITIUM, GASES, ALPHA) CURIES 3.49E-02 1.40E-02 2.50E+01
) ...__..........___.......................... __................... ____.____.... !
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML. 2.20E-09 9.01H-10 ,
i 3. PERCENT OF APPLICABLE LIMIT % *
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i 1. TOTAL RELEASE CURIES 1.37E+02 1.60E+02 2.50E+01 l l ................. __________...................... .......______................ j
- 2. AVERAGE DILUTED CONCENTRATION !
4 DURING PERIOD uCi/ML 8.63E-06 1.03E-05 :
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- 3. PERCENT OF APPLICABLE LIMIT % * * '
4 j C. DISSOLVED AND ENTRAINED GASES ;
- ___.....................__...............................__.__.................. j l 1. TOTAL RELEASE CURIES 1.12E-04 2.16E-04 2.50E+01 l 3 2. AVERAGE DILUTED CONCENTRATION j DURING PERIOD uC1/ML 7.04E-12 1.40E-11 !
1 3. PERCENT OF APPLICABLE LIMIT % *
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j D. GROSS ALPHA RADIOACTIVITY
! 1. TOTAL RELEASE CURIES 1.58E-05 2.82E-05 2.50E+01 !
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i E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 8.52E+07 8.10E+07 1.00E+01 I s
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- F. VOLUME OF DILUTION WATER USED LITERS 1.58E+10 1.54E+10 1.00E+01 t
- Applicable limits are expressed in terms of dose. See Tables j 1-3A and 1-3B of this report.
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4 TABLE 1-1B !
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Summation of All Releases j Unit: 2 ;
Starting : 1-Jan-1994 Ending : 30-Jun-1994 I
. TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT >
ERROR % ;
A. FISSION & ACTIVATION PRODUCTS t i
- 1. TOTAL RELEASE (NOT INCLUDING '
TRITIUM, GASES, ALPHA) CURIES 9.92E-03 2.81E-02 2.50E+01
- 2. AVERAGE DILUTED. CONCENTRATION l DURING PERIOD uCi/ML 5.30E-10 1.49E-09 PERCENT OF APPLICABLE LIMIT % * * ;
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......__...........__...__.____..........................___.......___.......... j B. TRITIUM i
....._..... ____...........................______...................__.......... l
- 1. TOTAL RELEASE CURIES 1.17E+02 7.79E+01 2.50E+01 ;
- 2. AVERAGE DILUTED CONCENTRATION :
DURING PERIOD uCi/ML 6.25E-06 4.12E-06 l
- 3. PERCENT OF APPLICABLE LIMIT % *
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C. DISSOLVED AND ENTRAINED GASES ,
- 1. TOTAL RELEASE CURIES 3.70E-02 2.44E-04 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.98E-09 1.29E-11
- 3. PERCENT OF APPLICABLE LIMIT % *
- D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 1.76E-05 1.62E-05 2.50E+01 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 6.63E+07 7.01E+07 1.00E+01 i F. VOLUME OF DILUTION WATER USED LITERS 1.87E+10 1.88E+10 1.00E+01 O Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
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TABLE 1-1B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Summation of All Releases Unit: 2 Starting : 1-Jul-1994 Ending : 31-Dec-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 7.82E-03 9.24E-03 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.31E-10 5.48E-10
- 3. PERCENT OF APPLICABLE LIMIT % *
- B. TRITIUM
- 1. TOTAL RELEASE CURIES 2.24E+02 2.89E+02 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.24E-05 1.72E-05
- 3. PERCENT OF APPLICABLE LIMIT % *
- C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.67E-04 9.53E-04 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.20E-12 5.65E-11
- 3. PERCENT OF APPLICABLE LIMIT % *
- D. GROSS ALPHA RADI, ACTIVITY
- 1. TOTAL RELEASE CURIES 1.60E-05 3.64E-05 2.50E+01 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 1.11E+08 8.16E+07 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 1.80E+10 1.68E+10 1.00E+01 o Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
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TABLE 1-1C Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Summation of All Releases Unit: Site Starting : 1-Jan-1994 Ending : 30-Jun-1994 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %
A. FISSION &. ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.26E-02 1.04E-01 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.22E-09 2.86E-09
- 3. PERCENT OF APPLICABLE LIMIT % *
- B. TRITIUM
- 1. TOTAL RELEASE CURIES 3.73E+02 1.71E+02 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.07E-05 4.71E-06
- 3. PERCENT OF APPLICABLE LIMIT % *
- C. DISSOLVED AND ENTRAINED' GASES
- 1. TOTAL RELEASE CURIES 8.912-02 1.03E-03 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.56E-09 2.84E-11
- 3. PERCENT OF APPLICABLE LIMIT % *
- D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 5.79E-05 5.83E-05 2.50E+01 E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 1.28E+08 1.40E+08 1.00E+01 F. VOLUME OF DILUTION WATER USED LITERS 3.47E+10 3.62E+10 1.00E+01 o Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
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1 TABLE 1-1C Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents - Summation of All Releases Unit: Site Starting : 1-Jul-1994 Ending : 31-Dec-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.27E-02 2.32E-02 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.26E-09 7.17E-10
- 3. PERCENT CF APPLICABLE LIMIT % *
- B. TRITIUM
- 1. TOTAL RELEASE CURIES 3.61E+02 4.49E+02 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.06E-05 1.39E-05
- 3. PERCENT OF APPLICABLE LIMIT % *
- C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 2.79E-04 1.17E-03 2.50E+01
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.19E-12 3.61E-11
- 3. PERCENT OF APPLICABLE LIMIT % *
- D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 3.19E-05 6.46E-05 2.50E+01 I
l E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 1.96E+08 1.63E+08 1.00E+01 l F. VOLUME OF DILUTION WATER USED LITERS 3.38E+10 3.22E+10 1.00E+01
- Applicable limits are expressed in terms of dose. See Tables 1-3A and 1-3B of this report.
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2.5.2 Liquid Effluents - Continuous and Batch Relcacca The continuous and batch release summaries of all liquid l effluent releases (includes listing by nuclide) are 1 contained in the following tables:
Unit 1 1994 Continuous and Batch Releases : Table 1-2A.
Unit 2 1994 Continuous and Batch Releases : Table 1-2B Site 1994 Continuous and Batch Releases : T&ble 1-2C {
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l l
16
- TABLE.1-2A*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents l- Unit: 1 Starting : 1-Jan-1994 Ending : 30-Jun-1994 l.
l l CONTINUOUS MODE l BATCH MODE l 3 .........._____..............__..__....__.......................................
l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l H-3 l CURIES l 1.27E-01 l 2.38E-07 l 2.56E+02 l 9.34E+01 l i
FISSION & ACTIVATION PRODUCTS i ..........................__.................................................._.
2 AG-110M CURIES 0.00E+00 0.00E+00 8.08E-04 6.19E-04 i AS-76 CURIES- 0.00E+00 0.00E+00 0.00E+00 2.26E-05
) CE-141 CURIES 0.00E+00 0.00E+00 2.16E-06 1.64E-05 CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.50E-05
, CO-57 CURIES 0.00E+00 0.00E+00 5.84E-07 4.01E-05
- CO-58 CURIES 0.00E+00 0.00E+00 1.78E-03 1.91E-02
} ~CO-60 CURIES 0.00E+00. 0.00E+00 4.11E-03 3.07E-03
- CR-51 CURIES 0.00E+00 0.00E+00 5.78E-04 2.23E-03 CS-134 CURIES 5.95E-05 0.00E+00 7.88E-05 7.98E-04 1
CS-137 CURIES 1.63E-04 0.00E+00 4.79E-04 1.43E-03 FE-55 CURIES 6.98E-10 1.16E-09 2.61E-03 1.24E-03 FE-59 CURIES 0.00B+00 0.00E+00 1.34E-05 7.36E-06 2
I-131 CURIES 1.12E-04 0.00E+00 1.64E-04 2.62E-05 I-132 CURIES 0.00E+00 0.00E+00 1.13E-04 0.00E+00
. I-133 CURIES 7.23E-03 0.00E+00 6.21E-05 0.00E+00 i LA-141 CURIES 0.00E+00 0.00E+00 1.30E-04 6.30E-04 4
MN-54 CURIES 0.00E+00 0.00E+00 '3.78E-04 5.14E-04 NA-24 CURIES 0.00E+00 0.00E+00 0.00E+00 1.49E-05
- NB-95 CURIES 0.00E+00 0.00E+00- 2.96E-04 7.92E-04 NB-97 CURIES 0.00E+00 0.00E+00 2.30E-04 2.80E-04
- OTHER CURIES 1.37E-03 6.99E-04 5.64E-05 1.37E-05 PR-144 CURIES 0.00E+00 0.00E+00 1.25E-03 9.78E-04 j RU-103 CURIES 0.00E+00 0.00E+00 1.06E-05 2.99E-05 SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 4.37E-06 i SB-124 CURIES 0.00E+00 0.00E+00 1.09E-03 5.99E-03 1 SB-125 CURIES 0.00E+00 0.00E+00 9.07E-03 3.56E-02 1 SN-113 CURIES 0.00E+00 0.00E+00 2.33E-06 6.04E-06 j SN-117M CURIES 0.00E+00 0.00E+00 1.19E-06 2.10E-05 L SR-85 CURIES 0.00E+00 0.00E+00 7.57E-07 0.00E+00 SR-89 CURIES 3.18E-11 9.09E-12 2.09E-05 8.46E-06 SR-90 CURIES 1.08E-11 8.94E-05 7.37E-07 1.51E-05
^ .SR-93 CURIES 0.00E+00 0.00E+00 1.80E-05 3.15E-05 TC-99M CURIES 0.00E+00 0.00E+00 3.97E-06 0.00E+00 i,
i 17
TABLE 1-2A*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents Unit: 1 Starting : 1-Jan-1994 Ending : 30-Jun-1994 l CONTINUOUS MODE l BATCH MODE l ,
NUCLIDE l UNIT l QUARTER 1 l QUARTER.2 l QUARTER 1 l QUARTER 2 l FISSION & ACTIVATION PRODUCTS TE-125M CURIES 0.00E+00 0.00E+00 2.15E-04 1.12E-03 TE-132 CURIES 0.00E+00 0.00E+00 9.24E-05 1.18E-06 ZR-95 CURIES 0.00E+00 0.00E+00 6.78E-05 3.31E-04 TOTALS l CURIES l 8.93E-03 l 7.88E-04 l 2.37E-02 l 7.50E-02 l DISSOLVED AND ENTRAINED GASES KR-85 CURIES 0.00E+00 0.00E+00 1.73E-04 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 9.85E-04 1.79E-05
- XE-133 CURIES 6.76E-04 0.00E+00 5.02E-02 7.66E-04 XE-133M CURIES 0.00E+00 0.00E+00 9.85E-05 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 1.88E-05 3.25E-06 XE-135M CURIES 0.00E+00 0.00E+00 0.00E+00 1.72E-06 l TOTALS l CURIES l 6.76E-04 l 0.00E+00 l 5.15E-02 l 7.89E-04 l G-ALPHA l CURIES l 6.50E-11 l 1.46E-05 l 4.03E-05 l 2.75E-05 l
- Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum detectable concentrations.
18
I l
TABLE 1-2A*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents q Unit: 1 Starting : 1-Jul-1994- Ending : 31-Dec-1994 i l CONTINUOUS MODE l BATCH MODE l I
NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l H-3 -l CURIES l 6.87E-02 l 2.53E-07 l 1.37E+02 l 1.60E+02 l ,
l FISSION & ACTIVATION PRODUCTS i AG-110M CURIES 0.00E+00 0.00E+00 0.00E+00 3.91E-05 CO-57 CURIES 0.00E+00 0.00E+00 1.08E-04 4.95E-05 .
CO-58 CURIES 0.00E+00 0.00E+00 1.94E-02 5.35E-03 s CO-60 CURIES 0.00E+00 0.00E+00 3.36E-03 2.54E-03 CR-51 CURIES 0.00E+00 0.00E+00 7.93E-05 0.00E+00 CS-134 CURIES 0.00E+00 0.00E+00 9.78E-04 9.17E-04 CS-137 CURIES 0.00E+00 0.00E+00 1.22E-03 1.34E-03 FE-55 CURIES 4.42E-09 8.38E-09 1.04E-03 2.13E-03 I
I-131 CURIES 0.00E+00 0.00E+00 0.00E+00 6.21E-06 r 4
LA-141 CURIES 0.00E+00 0.00E+00 4.01E-05 0.00E+00 ,
J MN-54 CURIES 0.00E+00 0.00E+00 4.45E-04 2.54E-04 NA-24 CURIES 0.00E+00 0.00E+00 4.78E-05 0.00E+00 ;
,j NB-95 CURIES 0.00E+00 0.00E+00 3.10E-04 9.60E-05 NB-97 CURIES 0.00E+00 0.00E+00 3.08E-04 1.97E-04
) OTHER CURIES 1.03E 0.00E+00 0.00E+00 0.00E+00
- PM-149 CURIES 0.00E+00 0.00E+00 1.66E-05 0.00E+00 l SB-122 CURIES 0.00E+00 0.00E+00 4.97E-06 2.16E-06 SB-124 CURIES 0.00E+00 0.00E+00 3.98E-04 0.00E+00 SB-125 CURIES 0.00E+00 0.00E+00 6.00E-03 9.33E-04
- SN-113 CURIES 0.00E+00 0.00E+00 0.00E+00 1.08E-06 i SR-89 CURIES 5.46E-11 6.18E-11 8.99E-06 1.50E-05 d SR-90 CURIES 3.72E-06 1.68E-11 5.88E-06 5.29E-07 SR-92 CURIES 0.00E+00 0.00E+00 9.42E-05 2.89E-05
, TC-99M CURIES 0.00E+00 0.00E+00 0.00E+00 6.75E-06 TE-127M CURIES 0.00E+00 0.00E+00 0.00E+00 4.69E-05 i ZR-95 CURIES 0.00E+00 0.00E+00 3.55E-05 5.61E-06 TOTALS l CURIES l 1.03E-03 l 8.46E-09 l 3.39E-02 l 1.40E-02 l 1
i i
l a
1 19 l l I
4 TABLE 1-2A* .
I Joseph M. Farley Nuclear Plant i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1994 Liquid Effluents Unit: 1
- Starting
- 1-Jul-1994 Ending : 31-Dec-1994
.....__..____..................._............ l
- l CONTINUOUS MODE l BATCH MODE l l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l
{NUCLIDE i
!' DISSOLVED AND ENTRAINED GASES AR-41 1 CURIES 0.00E+00 0.00E+00 0.00E+00 2.46E-06 XE-133 CURIES 0.00E+00 0.00E+00 1.00E-04 2.06E-04 XE-135 CURIES 0.00E+00 0.00E+00 1.16E-05 7.99E-06 4
TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 1.12E-04 l 2.16E-04 l
........__..... .___........____.........____..___.........___.................. i l G-ALPHA l CURIES l 5.28E-11 l 6.37E-11 l 1.58E-05 l 2.82E-05 l ;
I i r
j
- Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum i detectable concentrations.
)
> l s
i A
w f
4
', 1
. 1 I
I i
i i
4 20 4
TABLE 1-2B0 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents Unit: 2 Starting : 1-Jan-1994 Ending : 30-Jun-1994 l CONTINUOUS MODE BATCH MODE l
NUCLIDE
........l l UNIT
........................l l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 H-3 CURIES l 4.98E-03 l 1.43E-06 l 1.17E+02 l 7.79E+01
................................................................-...............l l
FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 5.72E-04 6.61E-04 AS-76 CURIES 0.00E+00 0.00E+00 1.52E-06 3.69E-06 CO-57 CURIES 0.00E+00 0.00E+00 1.26E-06 1.44E-05 CO-58 CURIES 0.00E+00 0.00E+00 1.52E-03 1.15E-02 CO-60 CURIES 0.00E+00 0.00E+00 1.87E-03 CR-51 1.39E-03 CURIES 0.00E+00 0.00E+00 7.64E-05 1.34E-03 CS-134 CURIES 0.00E+00 0.00E+00 6.73E-05 1.88E-04 CS-137 CURIES 0.00E+00 0.00E+00 1.69E-04 FE-55 2.88E-04 CURIES 7.92E-09 1.01E-03 8.36E-04 6.38E-04 I-131 CURIES ,0.00E+00 0.00E+00 1.36E-05 1.94E-05 I-132 CURIES 0.00E+00 0.00E+00 I-133 8.79E-05 0.00E+00 CURIES 0.00E+00 0.00E+00 1.89E-06 0.00E+00 LA 141 CURIES 0.00E+00 0.00E+00 6.19E-05 ML-54 7.23E-05 CURIES 0.00E+00 0.00E+00 1.65E-04 1.88E-04 Ft-24 CURIES 0.00E+00 0.00E+00 2.28E-05 4.31E-06 4B-95 CURIES 0.00E+00 0.00E+00 4.51E-05 NB 97 2.31E-04 CURIES 0.00E+00 0.00E+00 4.82E-05 8.74E-05 OTHER CURIES 0.00E+00 1.40E-03 PR-144 5.35E-07 0.00E+00 CURIES 0.00E+00 0.00E+00 4.05E-04 0.00E+00 SB-124 CURIES 0.00E+00 0.00E+00 3.61E-04 SB-125 1.13E-03 CURIES 0.00E+00 0.00E+00 3.11E-03 7.10E-03 SN 117M CURIES 0.00E+00 0.00E+00 SR-89 3.28E-06 9.40E-06 CURIES 1.24E-10 9.46E-11 9.97E-06 9.84E-06 SR-90 CURIES 7.73E-12 SR-92 1.01E-04 2.85E-07 3.91E-06 CURIES 0.00E+00 0.00E+00 1.68E-06 1.32E-05 TE-125M CURIES 0.00E+00 0.00E+00 3.32E-04 TE-132 5.33E-04 CURIES 0.00E+00 0.00E+00 1.17E-04 0.00E+00 ZN-65 CURIES 0.00E+00 0.00E+00 0.00E+00 ZN-69M 2.04E-06 CURIES 0.00E+00 0.00E+00 7.60E-07 0.00E+00 ZR.95 CURIES 0.00E+00 0.00E+00 1.04E-05 1.56E-04 TOTALS CURIES l l 8.05E-09 l 2.51E-03 9.92E-03 2.56E-02
........................................................__l_..........l...........l 21
TABLE 1-2B*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 3 Liquid Effluents Unit: 2-Starting : 1-Jan-1994 Ending : 30-Jun-1994 l CONTINUOUS MODE- l- BATCH MODE l NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1'l QUARTER 2
................__...........__......__. __......__.....___.............._....__l DISSOLVED AND ENTRAINED GASES XE-131M CURIES 0.00E+00 0.00E+00 1.04E-03 0.00E+00 XE-133 CURIES 0.00E+00 0.00E+00 3.59E-02 2.44E-04 XE-133M CURIES 0.00E+00 0.00E+00 3.70E-05 0.00E+00 XE-135 CURIES 0.00E+00 0.00E+00 1.12E-05 0.00E+00 TOTALS CURIES l l.0.00E+00 l 0.00E+00 l 3.70E-02 l 2.44E-04
...............................____.___...______...___............__............l 13-ALPHA CURIES
.l l 3.55E-11 l 3.64E-11 l 1.76E-05 1.62E-05
.____...___ ..._______....___............................__..... __..l......__..l Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum detectable concentrations.
22
TABLE 1-2B*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents Unit: 2 Starting : 1-Jul-1994 Ending : 31-Dec-1994 k l CONTINUOUS MODE l BATCH MODE l NUCLIDE -
l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l H-3 CURIES l l 2.61E-01 l 2.51E-01 l 2.24E+02 l 2.89E+02
.______.......__. ________.........._______........_____..__.....__ __..______..l FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 6.41E-05 2.98E-05 l AS-76 CURIES 0.00E+00 0.00E+00 1.26E-06 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 1.41E-06 4.15E-06 CO-58 CURIES 0.00E+00 0.00E+00 1.24E-03 5.21E-04 CO-60 CURIES 0.00E+00 0.00E+00 4.91E-04 1.08E-03 CS-134 CURIES 0.00E+00 0.00E+00 2.75E-04 1.23E-03 CS-137 CURIES 0.00E+00 0.00E+00 5.04E-04 2.02E-03 FE-55 CURIES 5.87E-05 4.07E-09 7.00E-04 1.99E-03 I-130 CURIES 0.00E+00 0.00E+00 1-131 1.68E-05 0.00E+00 CURIES 0.00E+00 0.00E+00 0.00E+00 7.11E-07 MN-54 CURIES 0.00E+00 0.00E+00 5.97E-05 1.13E-04 NA-24 CURIES 0.00E+00 0.00E+00 0.00E+00 4.33E-06 NB-95 CURIES 0.00E+00 0.00E+00 5.46E-06 NB-97 0.00E400 CURIES 0.00E+00 0.00E+00 7.44E-05 1.42E-04 OTHER CURIES 9.95E-04 0.00E+00 0.00E+00 0.00E+00 SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 SB-124 5.01E-06 CURIES 0.00E+00 0.00E+00 7.75E-05 0.00E+00 SB-125 CURIES 0.00E+00 0.00E+00 3.23E-03 SR-89 2.06E-03 CURIES 1.24E-10 6.37E-11 1.11E-05 2.51E-05
'SR-90 CURIES 5.882-06 1.07E-11 3.16E-07 SR-92 7.19E-07 CURIES 0.00E+00 0.00E+00 3.99E-06 6.37E-06 TC-99M CURIES 0.00E+00 0.0GE+00 0.00E+00 ZN-65 3.99E-06 CURIES 0.00E+00 0.00E+00 0.00E+00 4.04E-06 TOTALS CURIES l l 1.06E-03 l 4.15E-09 l 6.76E-03 9.24E-03
...........__..........______......___...._____.....__...............l__. __.....l DISSOLVED AND ENTRAINED GASES AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 XE-133 3.40E-06 CURIES 0.00E+00 0.00E+00 1.51E-04 8.87E-04 XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 XE-135 5.41E-06 CURIES 0.00E+00 0.00E+00 1.55E-05 5.73E-05 23 L
TABLE 1-2B*
Joseph M. Farley Nuclear Plant.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents Unit: 2 !
Starting : '1-Jul-1994 Ending : 31-Dec-1994 l CONTINUOUS MODE l BATCH MODE- l l NUCLIDE l . UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l i
DISSOLVED AND ENTRAINED GASES !
..........__........__....__.......___.____...__.................__....__....... s
__....._________._____..____....__......................___.............__...... i TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 1.67E-04 l 9.53E-04 l G-ALPHA l CURIES l 2.55E-11 l 3.18E-12 l 1.60E-05-l 3.64E-05 l
- Zeroes in this table. indicate that no radioactivity was present at detectable levels. See Table 1-5 for typical minimum ,
detectable concentrations.
e
?
F L
L I
i r
r h
l l
i 1
t i
1 4
P f
24 !
}
L I
I y - y. , , . , . , , . - p --.w,5 -
- m. w-g a-.
i a
TABLE 1-2C0 ;
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994
) Liquid Effluents Unit: Site t Starting : 1-Jan-1994 Ending : 30-Jun-1994 '
i l CONTINUOUS MODE l BATCH MODE l j .
i i NUCLIDE l UNIT l QUARTER l'l QUARTER 2 l QUARTER 1 l QUARTER 2 l-i j H-3 l CURIES l 1.32E-01 l 1.67E-06 l 3.73E+02 l 1.71E+02 l 4
j FISSION & ACTIVATION PRODUCTS
- AG-110M CURIES 0.)0E+00 0.00E+00 1.38E-03 1.28E-03 j j AS-76 CURIES 0.00E+00 0.00E+00 1.52E-06 2.63E-05 CE-141 CURIES 0.)0E, 1 0.00E+00 2.16E-06 1.64E-05 '
- CE-144 CURIES 0.00E+00 0.00E+00 0.00E+00 1.50E-05 CO-57 CURIES 0.0CR+00 0.00E+00 1.84E-06 5.45E-05 i 0.00E+00 CO-58 CURIES 0.00Es00 3.30E-03 3.06E-02 i CO-60 CURIES 0.00E+00 0.00E+00 5.98E-03 4.46E-03 l 4 CR-51 CURIES 0.00E+00 0.00E+00 6.55E-04 3.57E-03 :
CS-134 CURIES 5.95E-05 0.00E+00 1.46E-04 9.86E-04
- CS-137 CURIES 1.63E-04 0.00E+00 6'.48E-04 1.72E-03 l 1 FE-55 CURIES 8.61E-09 1.01E-03 3.45E-03 1.88E-03 -
FE-59 CURIES 0.00E+00 0.00E+00 1.34E-05 7.36E-06 l I-131 CURIES 1.12E-04 0.00E+00 1.77E-04 4.56E-05 i I-132 CURIES 0.00E+00 0.00E+00 2.01E-04 0.00E+00 ;
,' I-133 CURIES 7.23E-03 0.00E+00 6.40E-05 0.00E+00
- LA-141 CURIES 0.00E+00 0.00E+00 1.92E-04 7.03E-04 i i MN-54 CURIES 0.00E+00 0.00E+00 5.43E-04 7.02E-04 )
j NA-24 CURIES 0.00E+00 0.00E+00 2.28E-05 1.92E-05 ;
i NB-95 CURIES 0.00E+00 0.00E+00 3.41E-04 1.02E-03 I l NB-97 CURIES 0.00E+00 0.00E+00 2.78E-04 3 . 6 7E - Us'-
j OTHER CURIES 1.37E-03 2.10E-03 5.69E-05 1.375-f3 PR-144 CURIES 0.00E+00 0.00E+00 1.66E-03 9.78E-94 RU-103 CURIES 0.00E+00 0.00E+00 1.06E-05 2.99E 05 SB-122 CURIES 0.00E+00 0.00E+00 0.00E+00 4.37E-06 j SB-124 CURIES 0.00E+00 0.00E+00 1.45E-03 7.12E-03
- SB-125 CURIES 0.00E+00 0.00E+00 1.22E-02 4.27E-02 4 SN-113 CURIES 0.00E+00 0.00E+00 2.33E-06 6.04E-06 i SN-117M CURIES 0.00E+00 0.00E+00 4.46E-06 3.04E-05 SR-85 CURIES 0.00E+00 0.00E+00 7.57E-07 0.00E+00
- SR-89 CURIES 1.56E-10 1.04E-10 3.09E-05 1.83E-05 2
SR-90 CURIES 1.85E-11 1.91E-04 1.02E-06 1.90E-05 l SR-92 CURIES 0.00E+00 0.00E+00 1.97E-05 4.47E-05 l TC-99M CURIES 0.00E+00 0.00E+00 3.97E-06 0.00E+00 i i l l 25 j
)
4 i
4
, - _ . , . ~ _. , ._m.,_..._ . . . - - -
l TABLE 1-2C# i Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 i Liquid Effluents '
Unit: Site Starting : 1-Jan-1994 Ending : 30-Jun-1994 ;
l CONTINUOUS MODE l BATCH MODE l !
NUCLIDE l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l P
J i FISSION & ACTIVATION PRODUCTS ,
i .. ___________...__________.____ ...............,,_ .............................
0.00E+00 TE-125si CURIES 0.00E+00 5.47E-04 1.66E-03 TE-132 CURIES 0.00E+00 0.00E+00 2.09E-04 1.18E-06 ZN-65 CURIES 0.00E+00 0.00E+00 0.00E+00 2.04E-06 ZN-69M CURIES 0.00E+00 0.00E+00 7.60E-07 0.00E+00 i ZR-95 CURIES 0.00E+00 0.00E+00 7.83E-05 4.87E-04 I TOTALS l CURIES l 8.93E-03 l 3.30E-03 l 3.37E-02 l 1.01E-01 l t DISSOLVED AND ENTRAINED GASES KR-85 CURIES 0.00E+00 0.00E+00 1.73E-04 -0.00E+00 j XE-131M CURIES 0.00E+00 0.00E+00 2.02E-03 1.79E-05 !
XE-133 CURIES 6.76E-04 0.00E+00 8.61E-02 1.01E-03 i
- XE-133M CURIES 0.00E+00 0.00E+00 1.36E-04 0.00E+00
+
XE-135 CURIES 0.00E+00 0.00E+00 3.00E-05 3.25E-06 ,
XE-135M CURIES 0.00E+00 0.00E+00 0.00E+00 1.72E-06
, TOTALS l CURIES l 6.76E-04 l 0.00E+00 l 8.85E-02 l 1.03E-03 l >
G-ALPHA l CURIES l 1.00E-10 l 1.46E-05 l 5.79E-05 l 4.37E-05 l j __......._..............................__...........___........__._...._..__...
- i r
!
- Zeroes in this table indicate that no radioactivity was present '
at detectable levels. See Table 1-5 for typical minimum detectable concentrations.
l I
I
=
1 1
i i 26 i
TABLE 1-2C*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents Unit: Site Starting : 1-Jul-1994 Ending : 31-Dec-1994 l CONTINUOUS MODE l BATCH MODE l MUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 lQUA'ATER 4 l H-3 CURIES l l 3.30E-01 l 2.51E-01 l 3.61E+02 l 4.49E+02 l FISSION & ACTIVATION PRODUCTS AG-110M CURIES 0.00E+00 0.00E+00 6.41E-05 6.90E-05 AS-76 CURIES 0.00E+00 0.00E+00 1.26E-06 0.00E+00 CO-57 CURIES 0.00E+00 0.00E+00 1.09E-04 5.37E-05 CO-58 CURIES 0.00E+00 0.00E+00 2.06E-02 5.87E-03 CO-60 CURIES 0.00E+00 0.00E+00 3.85E-03 3.63E-03 CR-51 CURIES 0.00E+00 0.00E+00 7.93E-05 0.00E+00 CS-134 CURIES 0.00E+00 0.00E+00 1.25E-03 2.14E-03 CS-137 CURIES 0.00E+00 0.00E+00 1.73E-03 3.36E-03 FE-55 CURIES 5.87E-05 1.25E-08 1.74E-03 4.12E-03 I-130 CURIES 0.00E+00 0.00E+00 I-131 1.68E-05 0.00E+00 CURIES 0.00E+00 0.00E+00 0.00E+00 6.92E-06 LA-141 CURIES 0.00E+00 0.00E+00 4.01E-05 0.00E+00 MN-54 CURIES 0.00E+00 0.00E+00 5.04E-04 3.67E-04 NA-24 CURIES 0.00E+00 0.00E+00 4.78E-05 4.33E-06 NB-95 CURIES 0.00E+00 0.00E+00 3.16E-04 9.60E-05 NB-97 CURIES 0.00E+00 0.00E+00 3.83E-04 3.39E-04 OTHER CURIES 2.02E-03 0.00E+00 0.00E+00 0.00E+00 PM-149 CURIES 0.00E+00 0.00E+00 1.66E-05 0.00E+00 SB-122 CURIES 0.00E+00 0.00E+00 4.97E-06 7.17E-06 SB-124 CURIES 0.00E+00 0.00E+00 4.76E-04 SB-125
^ 00E+00 CURIES 0.00E+00 0.00E+00 9.23E-03 3.00E-03 SN-113 CURIES 0.00E+00 0.00E+00 0.00E+00 1.08E-06 SR-89 CURIES 1.78E-10 1.26E-10 2.00E-05 SR-90 4.02E-05 CURIES 9.60E-06 2.75E-11 6.20E-06 1.25E-06 SR-92 CURIES 0.00E+00 0.00E+00 9.82E-05 3.53E-05 TC-99M CURIES 0.00E+00 0.00E+00 0.00E+00 1.07E-05 TE-127M CURIES 0.00E+00 0.00E+00 0.00E+00 ZN-65 4.69E-05 CURIES 0.00E+00 0.00E+00 0.00E+00 4.04E-06 ZR-95 CURIES 0.00E+00 0.00E+00 3.55E-05 5.61E-06 TOTALS l CURIES l 2.09E-03 l 1.26E-08 l 4.06E-02 2.32E-02
.....................__......................___.....__l__.........l 27
i TABLE 1-2C*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Liquid Effluents Unit: Site <
Starting : 1-Jul-1994 Ending : 31-Dec-1994 l l CONTINUOUS MODE l BATCH MODE l l NUCLIDE l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l j DISSOLVED AND ENTRAINED GASES ,
AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 5.87E-06 '
XE-133 CURIES 0.00E+00 0.00E+00 2.52E-04 1.09E-03 XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 5.41E-06 XE-135 CURIES 0.00E+00 0.00E+00 2.71E-05 6.53E-05
.......___.____........._______________............___....__..... _______....... 4 TOTALS l CURIES l 0.00E+00 l 0.00E+00 l 2.79E-04 l 1.17E-03 l G-ALPHA l CURIES l 7.82E-11 l 6.68E-11.l 3.19E-05 l 6.46E-05 l .'
t r
- Zeroes in this table indicate that no radioactivity was present .
- at detectable levels. See Table 1-5 for typical minimum (
i detectable concentrations. !
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2.6' Radiological Impact The total body and organ doses for Units 1 and 2 are provided !
in the following tables in order to show conformance with the j limits of ODCM 2.1.3 : :
Unit 1 1994 Liquid Doses : Table 1-3A i Unit 2 1994 Liquid Doses : Table 1-3B l
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._ . -_, . . _ _ _ . . ~ . . _ _ . . _ _ _ _ _ _ _ . - _ . , , . _ - , . .
i I
TABLE 1-3A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSES TO A MEMBER OF THE PUBLIC DUE TO LICUID RELEASES 7 Unit: 1 i t
Starting: 01-Jan-1994 Ending: 30-Jun-1994 i
Cumulative Doses per Quarter i
}
Organ ODCM Units Quarter % of Quarter % of ;
Limit Limit j Bone 5.0 mrem 2.27E-03 4.55E-02 6.48E-03 1.30E Liver 5.0 mrem 3.91E-03 7.81E-02 4.64E-03 9.27E-02 TBody 1.5 mrem 3.40E-03 2.27E-01 4.48E-03 2.99E-01 Thyroid 5.0 mrem 4.70E-03 9.40E-02 8.13E-04 1.63E-02 i Kidney 5.0 mrem 3.18E-03 6.35E-02 3.26E-03 6.51E-02 '
Lung 5.0 mrem 4.78E-02 9.56E-01 1.69E-01 3.38E+00 GILLI 5.0 mrem 1.08E-02 2.17E-01 2.90E-02 5.80E-01 ,
s t
I
- Cumulative Doses per Year !
Organ ODCM Units Year to % of Limit Ending ODCM
- Date Limit Bone 10.0 mrem 8.76E-03 8.76E-02 Liver 10.0 mrem 8.54E-03 8.54E-02 l i
TBody 3.0 mrem 7.88E-03 2.63E-01 I Thyroid 10.0 mrem 5.51E-03 5.51E-02 1 Kidney 10.0 mrem 6.43E-03 6.43E-02 l Lung 10.0 mrem 2.17E-01 2.17E+00 l GILLI 10.0 mrem 3.98E-02 3.98E-01 1
- 1
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TABLE 1-3A !
Joseph M. Farley Nuclear Plant j ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 :
DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES l Unit: 1 I Starting: 01-Jul-1994 Ending: 31-Dec-1994 i
?
Cumulative Doses per Quarter ;
...............__.______.............__ ........__........__._______.__.... j Organ ODCM Units Quarter % of . Quarter % of i Limit 3 ODCM 4 ODCM. !
Limit Limit !
l Bone 5.0 mrem 2.77E-03 5.54E 02 2.71E-03 5.42E-02 Liver 5.0 mrem 4.98E-03 9.97E-02 5.31E-03 .1.06E-01 TBody 1.5 mrem 4.19E-03 2.79E-01 4.16E-03 2.77E-01 !
Thyroid 5.0 mrem ~9.78E-04. 1.96E-02 1.18E-03 2.36E-02 ,
Kidney 5.0 mrem 2.21E-03 4.42E-02 2.60E-03 5.20E-02 Lung 5.0 mrem 3.03E-02 6.06E-01 6.19E-03 1.24E-01 ;
GZLLI 5.0 mrem 7.18E-03 1.44E-01 3.13E 6.25E l Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM ,
Date Limit l Bone 10.0 mrem 1.42E-02 1.42E-01 Liver 10.0 mrem 1.88E-02 1.88E-01 TBody 3.0 mrem 1.62E-02 5.41E-01 Thyroid 10.0 mrem 7.67E-03 7.67E-02 Kidney 10.0 mrem 1.12E-02 1.12E-01 Lung 10.0 mrem 2.53E-01 2.53E+00 GILLI 10.0 mrem 5.01E-02 5.01E-01 4
I k
31
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i TABLE 1-3B ;
Joseph M. Farley Nuclear Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 i j DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES l Unit: 2 '
5 Starting: 01-Jan-1994 Ending: 30-Jun-1994 !
I
}
. Cumulative Doses per Quarter ,
1 .______... ....... ___. _....................__...........___.......... ___
Organ ODCM Units Quarter % of Quarter % of i Limit 1 ODCM 2 ODCM ,
Limit Limit -
- o -
Bone 5.0 mrem 6.90E-04 1.38E-02 2.89E-03 5.77E-02 Liver 5.0 mrem 1.38E-03 2.77E-02 1.60E-03 3.20E-02
, TBody 1.5 mrem 1.24E-03 9.29E-02 1.77E-03 1.18E-01 Thyroid 5.0 mrem 8.95E-04 1.79E-02 6.12E-04 1.22E-02
- Kidney 5.0 mrem 1.57E-03 3.15E-02 1.48E-03 2.97E 1 Lung 5.0 mrem 1.51E-02 3.01E-01 3.22E-02 6.45E-01 ,
4 GILLI 5.0 mrem 4.62E-03 9.24E-02 7.31E-03 1.46E-01
.... ___ ........____..__...__ .__.............____..________________.____ {
d l !
1 Cumulative Doses per Year ,
} ............___ .... ___...........______..___ ._.......... ____..........
a j Organ ODCM Units Year to % of !
- Limit Ending ODCM !
Date Limit
- i
- _________.. _______....._______.._...____............._____...___......... +
Bone 10.0 mrem 3.58E-03 3.58E-02 ,
! Liver 10.0 mrem 2.98E-03 2.98E-02 i i TBody 3.0 mrem 3.02E-03 1.01E-01 ;
! Thyroid 10.0 mrem 1.51E-03 1.51E-02 t i
Kidney 10.0 mrem 3.06E-03 3.06E-02 ,
i Lung 10.0 mrem 4.73E-02 4.73E i j GILLI 10.0 mrem 1.19E-02 1.19E-01 1
1 l
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TABLE 1-3B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-1994 Ending: 31-Dec-1994 i
i Cumulative Doses per Quarter Organ ODCM Units Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 1.09E-03 2.18E-02 3.53E-03 7.06E-02 '
Liver 5.0 mrem 2.85E 5.71E-02 7.42E-03 1.48E-01 1 TBody 1.5 mrem 2.52E-03 1.68E-01 5.87E-03 3.91E-01 l Thyroid 5.0 mrem 1.54E-03 3.08E-02 1.97E-03 3.95E-02 j Kidney 5.0 mrem 1.94E-03 3.89E-02 3.70E-03 7.39E-02 Lung 5.0 mrem 1.61E-02 3.22E-01 1.20E-02 2.39E-01 3 GILLI 5.0 mrem 3.21E-03 6.41E-02 3.33E-03 6.65E-02 !
Cumulative Doses per Year Organ ODCM Units Year to % of j Limit Ending ODCM '
Date Limit I
______. ___....___ ._____....................__________________ ........._ ]
Bone 10.0 mrem 8.20E-03 8.20E-02 I Liver 10.0 mrem 1.33E-02 1.33E-01 TBody 3.0 mrem 1.14E-02 3.80E-01 Thyroid 10.0 mrem 5.02E-03 5.02E-02 Kidney 10.0 mrem 8.70E-03 8.70E-02 Lung 10.0 mrem 7.54E-02 7.54E-01 GILLI 10.0 mrem 1.85E-02 1.85E-01 l
1 l
l 1
33
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^
TABLE 1-5 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT. RELEASE REPORT - 1994 TYPICAL LIQUID MDC'S ACHIEVED ON COUNTING SYSTEM 7 1 3
Nuclide MDC(uCi/ML) i f
i a MN-54 3.14E-08 l l CO-58 4.92E-08 i l
1 FE-59 7.19E-08 CO-60 4.77E-08 :
1 ZN-65 8.11E-08 l i '
l MO-99 1.29E-07 J
I-131 2.53E-08 !
! CS-134 3.51E-08 i
i CS-137 4.28E-08 i j CE-141 5.41E-08 ;
CE-144 1.95E-07 l
1 l .
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3.0 GASEOUS EFFLUENTS This section contains applicable ODCM limits for gaseous effluents as well as the quantities of radioactive gaseous effluents released during 1994. These quantities are summarized on a quarterly basis and include any unplanned releases. Tabulations are provided of the offsite air doses calculated in accordance with ODCM 3.4.2 to show conformance with the limits of ODCM 3.1.3, and the offsite organ 4
doses to a member of the public calculated in accordance with ODCM 3.4.3 to show conformance with ODCM 3.1.4.
4 4
3.1 ODCM Limits 4
In accordance with Technical Specifications 6.8.3.e (v) and 6.8.3.e(viii), the air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and
- beyond the SITE BOUNDARY (see ODCM Figure 10-1) shall be limited to the following
4
- a. During any calendar quarter
- Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
4 In accordance with Technical Specifications 6.8.3.e(v) and 6.8.3.e(ix), the dose to a MEMBER OF THE PUBLIC from I-131, I-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents
- released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see ODCM Figure 10-1) shall be limited to the following:
I a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ, and
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
3.2 Measurements and Approximation of Total Radioactivity i
The following noble gases are considered in evaluating gaseous effluents:
KR-87 XE-133 KR-88 XE-135 XE-133M XE-138 35
The following radiciodinns end radioactiva materinic in particulate form are specifically considered in evaluating gaseous effluents:
MN-54 MO-99 FE-59 I-131 CO-58 CS-134 CO-60 CS-137 ZN-65 CE-141 SR-89 CE-144 SR-90 H-3 Periodic grab samples from plant effluent streams are analyzed by a computerized pulse height analyzer system utilizing.high resolution germanium detectors. Samples are obtained and analyzed in accordance with ODCM Table 3-3. Isotopic values thus.obtained are used for release rate calculations as specified in ODCM 3.4.2 and ODCM 3.4.3. Only those nuclides which are detected are used in calculations. For radiciodines and particulates, in addition to the nuclides listed above other nuclides with half-lives greater than 8 days which are identified are also considered.
Continuous Releases: Continuous sampling'is performed on the continuous releases points (i.e. the Plant Vent Stack, Containment Purge, and the Turbine Building Vent). Particulate material is collected by filtration. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and strontium as required. Gross alpha determinations are made using a 2 pi gas flow proportional counter. SR-89 and SR-90 values are obtained by chemical separati a and subsequent analysis using 2 pi gas flow proportional counters.
l Batch Releases: The processing of batch type releases (from Containment or Waste Gas Decay Tanks) is analogous to continuous releases, except that the release is not commenced until samples j have been obtained and analyzed, i
The maximum errors associated with monitor readings, sample fl - '
vent flow, sample collection, monitor calibration and laboratory procedure are collectively estimated to be:
Fission and Activation Gases Iodine Particulates Tritium 75% 60% 50% 45%
The average error associated with counting is estimated to be:
Fission and Activation Gases Iodine Particulates Tritium j 19% 28% 20% 8% 1 3.3 Abnormal Releases There were no abnornal gaseous releases on either Unit 1 or Unit 2 '
during 1994.
36
3.4 Batch Releases t
Batch release information for Units 1 and 2 is summarized in the ,
following tables: l 1
i Unit'l 1994 Gaseous Batch Releases : Table 2-6A ;
Unit 2 1994 Gaseous Batch Releases : Table 2-6B {
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4 TABLE 2-6A Joseph M. Farley huclear Plant 2
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents - Batch Release Summary a Unit: 1 i Starting : 1-Jan.1994 Ending : 30-Jun-1994 !
l j ________ ..._____.......____.................. ____............................. ,
i GASEOUS RELEASES i
2 NUMBER OF BATCH RELEASES : 13 l TOTAL TIME PERIOD FOR BATCH RELEASES : 5649.25 MINUTES ,
d MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 937.00 MINUTES
- AVERAGE TIME PERIOD FOR BATCH RELEASES
- 434.56 MINUTES >
MINIMUM TIME FOR A BATCH RELEASE : 115.00 MINUTES
. ....-._............................................_..... .................._. I l
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I TABLE 2-6A Joseph M. Farley Nuclear Plant l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 i Gaseous Effluents - Batch Release Sunmary
, Unit: 1 ;
Starting : 1-Jul-1994 Ending : 31-Dec-1994 t
f 1 i ;
i ;
a t GASEOUS RELEASES i NUMBER OF BATCH RELEASES : 0 TOTAL TIME PERIOD FOR BATCH RELEASES : 0.00~ MINUTES j MAXIMUM TIME PERIOD FOR A BATCH RELEASE : 0.00 MINUTES -
AVERAGE TIME PERIOD FOR BATCH RELEASES : 0.00 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 0.00 MINUTES b.
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TABLE 2-6B
- Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents - Batch Release Summary ,
Unit: 2 l Starting : 1-Jan-1994 Ending : 30-Jun-1994 i l
I I
GASEOUS RELEASES
___.....__...____.______.___....______..____.________.........____________...___ j NUMBER OF BATCH RELEASES : 0 i TOTAL TIME PERIOD FOR BATCH RELEASES : 0.00 MINUTES
-MAXIMUM TIME PERIOD FOR A BAICH RELEASE : 0.00 MINUTES ;
AVERAGE TIME PERIOD FOR BATCH RELEASES : 0.00 MINUTES !
MINIMUM TIME FOR A BATCH RELEASE : 0.00 MINUTES r
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TABLE 2-6B '
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 ,
Gaseous Effluents - Batch Release Summary 5 Unit: 2 Starting : 1-Jul-1994 Ending : 31-Dec-1994 GASEOUS RELEASES NUMBER OF BATCH RELEASES : 0 TOTAL TIME PERIOD FOR BATCH RELEASES : 0.00 MINUTES ;
MAXIMUM TIME PERIOD FOR A BATCH-RELEASE : MINUTES
~
0.00 i AVERAGE TIME PERIOD FOR BATCH RELEASES : 0.00 MINUTES MINIMUM TIME FOR A BATCH RELEASE : 0.00 MINUTES m e m - m e e m m e m m e . e m e m e . e . e . . e e . e ..e m e . ...........m s e e m . . ..G . . . . . .W . .....m .e . . . . . . m .
?
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41 1
3.5 Rolenco Summarica This section contains the summaries of all radioactive gaseous effluents released for Units 1 and 2 during 1994. Typical gaseous Miniumum Detectable Concentrations (MDC'S) for analyses are in Table 2-7 of this section. Regulatory Guide 1.21 Table 1A is found in this report as Tables 2-1A, 2-1B, and 2-1C. Regulatory Guide 1.21 Table 1B is found in this report as Tables 2-2A, 2-2B, and 2-2C. Regulatory Guide 1.21 Table 1C is found in this report as Tables 2-3A, 2-3B, and 2-3C.
3.5.1 Gaseous Effluents - Summation of All Releases The summations of all gaseous effluent releases are contained in the following tables:
Unit 1 1994 Summation of All Releases : Table 2-1A Unit 2 1994 Summation of All Releases : Table 2-1B Site 1994 Summation of All Releases : Table 2-1C l
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1 TABLE-2-1A )
Joseph M. Farley Nuclear Plant ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 i
, Gaseous Effluents - Summation of All Releases l Unit: 1
- Starting
- 1-Jan-1994 Ending : 30-Jun-1994 i
TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT l ERROR %
j ................... ___.___.................___....__.....__....................
. s A.. FISSION & ACTIVATION PRODUCTS !
- 1. TOTAL RELEASE CURIES 1.47E+02 6.06E+00 9.40E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.89E+01- 7.71E-01 !
- 3. PERCENT OF APPLICABLE LIMIT % *
- j a
, 1 B. RADIOIODINES ;
- 1. TOTAL IODINE-131 CURIES 3.60E-03 6.30E-04 8.80E+01 I
. 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.63E-04 8.01E-05 j .......____.....__.... ___..............................______.____.____........ i
- 3. PERCENT OF APPLICABLE LIMIT % * *
! C. PARTICULATES i E l i 1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 2.58E-03 5.04E-04 7.00E+01 j i
1
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.32E-04 6.41E-05 i
! 3. PERCENT OF APPLICABLE LIMIT % * *
)
3 j 4. GROSS ALPHA RADIOACTIVITY CURIES 6.47E-08 3.69E-07 1_
i D. TRITIUM
.J l ,
- 1. TOTAL RELEASE CURIES 4.01E+00 4.03E+00 5.30E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.16E-01 5.13E-01 4
- 3. PERCENT OF APPLICABLE LIMIT % *
- 1 i
1 a
1
'
- Applicable limits are expressed in terms of dose. See Tables l l 2-4A, 2-4B, 2-5A, and 2-5B of this report. i
. 43 s.
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TABLE 2-1A. '
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : 1-Jul-1994 Ending : 31-Dec-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 6.82E+00 4.01E+00 9.40E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.58E-01 5.05E-01
- 3. PERCENT OF APPLICABLE LIMIT % *
- B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.20E-05 3.88E-06 8.80E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.51E-06 4.88E-07
- 3. PERCENT OF APPLICABLE LIMIT % *
- C. PARTICULATES
- 1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.02E-03 6.79E-03 7.00E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.29E-04 8.54E-04
- 3. PERCENT OF APPLICABLE LIMIT % * *
- 4. GROSS ALPHA RADIOACTIVITY CURIES 6.33E-07 3.26E-08 D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.35E+01 2.31E+01 5.30E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.06E+00 2.91E+00
- 3. PERCENT OF APPLICABLE LIMIT % *
- Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-SA, and 2-5B of this report.
44
TABLE 2-1B.
Joseph M. Farley Nuclear-Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents - Summation of All Releases l Unit: 2 Starting : 1-Jan-1994 Ending : 30-Jun-1994 i
l TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT '
ERROR % l i
l )
l A. FISSION & ACTIVATION PRODUCTS l I
- 1. TOTAL RELEASE CURIES 1.40E+01 8.97E+00 9.40E+01 :
i 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.80E+00 1.14E+00 l
_________________________... _.__________......__... ___........................ j l 3. PERCENT OF APPLICABLE LIMIT % * * !
l I' i
B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.84E-05 3.96E-06 8.80E+01 :
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.36E-06 5.04E-07 !
! l
- 3. PERCENT OF APPLICABLE LIMIT % * *
.___________________...______............_____..........____....____...____ ..._ i l
! C. PARTICULATES
- 1. PARTICULATES (HALF-LIVES >8 DAYS) CURIES 6.68E-04 5.66E-04 7.00E+01 !
i ..______......___________ .....__............__ __ ....__.......................
l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.59E-05 7.19E-05
- 3. PERCENT OF APPLICABLE LIMIT % * * )
I
( 4. GROSS ALPHA RADIOACTIVITY CURIES 7.73E-08 1.50E-08 D. TRITIUM
- 1. TOTAL RELEASE CURIES 1.52E+01 2.11E+01 5.30E+01
- 2. AVERAGE RELRASE RATE FOR PERIOD uCi/Sec 1.95E+00 2.68E+00
- 3. PERCENT OF APPLICABLE LIMIT % * *
- Applicable limits are expressed in-terms of dose. See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.
I 1
1 45
h i
TABLE 2-1B-Joseph M. Farley Nuclear Plant l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents - Summation of All' Releases Unit: 2 Starting : 1-Jul-1994 Ending : 31-Dec-1994 l i l TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT t i
t ERROR % ,
A. FISSION & ACTIVATION PRODUCTS * '
- 1. TOTAL RELEASE CURIES 1.01E+01 1.33E+01 9.40E+01 -
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.27E+00 1.68E+00
- 3. PERCENT OF APPLICABLE LIMIT % *
- B. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 0.00E+00 0.00E+00 8.80E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.00E+00 0.00E+00 ,
.._......_____.____..............._____..............__.....................__.. I
- 3. PERCENT OF APPLICABLE LIMIT % *
- ___.....___...._______________..._____...........___..__......______............ 4 l
l C. PARTICULATES
- 1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 9.73E-04 4.76E-04 7.00E+01 1 ..............................__...._....................___....................
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.22E-04 5.99E-05
- 3. PERCENT OF APPLICABLE LIMIT % * *
- 4. GROSS ALPHA RADIOACTIVITY CURIES 3.52E-07 8.63E-07 l
l l D. TRITIUM l 1. TOTAL RELEASE CURIES 8.49E+00 7.99E+00 5.30E+01 l l .....................________.___.__....___.....__..____. ___.. __........___...
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.07E+00 1.01E+00 l
- 3. PERCENT OF APPLICABLE LIMIT % *
- 1 O Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.
46 i
f-- T $ -Q-F e. - me
. - - - - . .- . -. . . . - - __ =
2 TABLE 2-1C
- Joseph M. Farley Nuclear Plant
. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT .1994 l Gaseous Effluents - Summation of All Releases '
Unit: Site l Starting : 1-Jan-1994 Ending : 30-Jun-1994 I
4 TYPE.0F EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT I i ERROR % !
l -
4 A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.61E+02 1.50E+01 9.40E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.07E+01 1.91E+00 !
. 3. PERCENT OF APPLICABLE LIMIT % *
- l 1
1 i B. RADIOIODINES i
1 1. TOTAL IODINE-131 CURIES 3.62E-03 6.34E-04 8.80E+01 :
- 3. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.65E-04 8.06E-05 s ......._____.__.__........_..__.....__._............... ..____........._._......
- 3. PERCENT OF APPLICABLE LIMIT % *
- i
- C. PARTICULATES i
- 1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 3.25E-03 1.07E-03 7.00E+01 ;
............______...____..____..______...__...__ ...___........________________ i
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.18E-04 1.36E-04 !
..._________......_____.__.______.__..........._______ ......................... t 4
- 3. PERCENT OF APPLICABLE LIMIT % * * !
3
- 4. GROSS ALPHA RADIOACTIVITY CURIES 1.42E-07 3.84E-07 .
I D. TRITIUM
- 1. TOTAL RELEASE CURIES 1.92E+01 2.51E+01 5.30E+01 ,
4 ........___.____________......__......______.....__.....______..................
r
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.47E+00 3.19E+00 l i
4
- 3. PERCENT OF APPLICABLE LIMIT % *
- l
- __._......___._........______.................__.........__..................... t 4
4 o Applicable limits are expressed in terms of dose. See Tables
- 2-4A, 2-4B, 2-5A, and 2-5B of this report.
4 1
4 47 i
i l
1
-- - ., u-
-, , - - . , - ,n . .- e .- , - , . - . , - - -
TABLE 2-1C Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 i Gaseous Effluents - Summation of All Releases I
Unit: Site i j Starting : 1-Jul-1994 Ending : 31-Dec-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR.% ;
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.69E+01 1.73E+01 9.40E+01 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.13E+00 2.18E+00
- 3. PERCENT OF APPLICABLE LIMIT % *
- lB. RADIOIODINES
- 1. TOTAL IODINE-131 CURIES 1.20E-05 3.88E-06 8.80E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.51E-06 4.88E-07
\
l 3. PERCENT OF APPLICABLE LIMIT % * * '
!C. PARTICULATES I
- 1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.99E-03 7.27E-03 7.00E+01
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.50E-04 9.14E-04
- 3. PERCENT OF APPLICABLE LIMIT % *
- l
- 4. GROSS ALPHA RADIOACTIVITY CURIES 9.85E-07 8.96E-07 ,
1 i
i D. TRITIUM
- 1. TOTAL RELEASE CURIES 3.20E+01 3.11E+01 5.30E+01 i
_____...._______...__........_____________......_______. __................_____ j
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.03E+00 3.91E+00 l
- 3. PERCENT OF APPLICABLE LIMIT % *
- l* Applicable limits are expressed in terms of dose. See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.
48
3.5.2 Ganeous Effluents - Mixed Mode Releases The summaries of all gaseous effluent mixed mode releases (includes listing by nuclide) are contained in the following tables :
Unit 1 1994 Mixed Mode Summary : Table 2-2A.
Unit 2 1994 Mixed Mode Summary : Table 2-2B Site 1994 Mixed Mode Summary : Table 2-2C-s
+
49 i
f
TABLE 2-2A* l Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : 1-Jan-1994 Ending : 30-Jun-1994 l CONTINUOUS MODE- l BATCH MODE
.__......____..__....._____......________......_____.__.__._____.__......._____.l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER'2 l QUARTER 1 l QUARTER 2
.....______.______.________..__. __.......... __.....____......____.......__....l FISSION GASES AR-42 CURIES 3.40E+00 5.34E+00 0.00E+00 0.00E+00 KR-85M CURIES. 0.00E+00 0.00E+00 8.55E-03 0.00E+00 XE-135 CURIES 2.66E+00 1.32E-01 2.66E-01 9.68E-05
, XE-133M CURIES 6.20E-01 0.00E+00 2.62E-01 0.00E+00 XE-133 CURIES 1.12E+02' O.00E+00 2.36E+01 5.36E-03 XE-131M CURIES 0.00E+00 0.00E+00 KR-85 3.37E-01 0.00E+00 CURIES 0.00E+00 0.00E+00 1.07E+00 8.26E-02 TOTAL FOR PERIOD CURIES l l 1.19E+02 l 5.97E+00 l 2.55E+01
.....___..._....... ___________ _______.. ______... ______.______.__.l....... __.l 8.81E-02 IODINES I-132 CURIES 1.12E-04 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES I-131 1.98E-05 4.03E-05 0.00E+00 0.00E+00 CURIES 3.57E-03 6.30E-04 2.76E-07 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.70E-03 l 6.70E-04 2.76E-07 0.00E+00
___._____________.________________......______............l__....___._l________ __l PARTICULATES I-131 CURIES 3.52E-06 2.74E-07 1.14E-08 0.00E+00 CR-51 CURIES 0.00E+00 CO-58 7.84E-07 0.00E+00 0.00E+00 CURIES 0.00E+00 9.40E-07 0.00E+00 0.00E+00 Y-88 CURIES 0.00E+00 0.00E+00 OTHER 2.65E-04 0.00E+00 CURIES 2.17E-03 4.89E-04 1.26E-04 1.84E-08 TOTAL FOR PERIOD l CURIES l 2.17E-03 l 4.91E-04 3.91E-04 1.84E-08
____..__...____..__...........__....___.____..............l...__......l...........l 50
TABLE 2-2A*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 2994 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : 1-Jan-1994 Ending : 30-Jun-1994 l CONTINUOUS MODE l BATCH MODE
___..._____......___.__..__.....___.........__......__..__.....l 3 NUCLIDES RELEASED l UNIT l QUARTER 1Ll QUARTER 2.l QUARTER 1 l QUARTER 2 l H-3 CURIES 4.01E+00 4.03E+00 0.00E+00 0.00E+00 G-ALPHA CURIES 6.47E-08 3.69E-07 0.00E+00 0.00E+00-Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.
e 51
TABLE 2-2A*
Joseph M. Farley Nuclear Plant '
ANNUAL RADIOACTivts EFFLUENT RELEASE REPORT - 1994 i Gaseous Effluents-Mixed-Mode Level Releases !
Unit: 1 _
j Starting : 1-Jul-1994 Ending : 31-Dec-1994 l t
i l CONTINUOUS MODE l ' BATCH MODE l l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l l f
r I
FISSION GASES !
AR-41 CURIES 5.84E+00 3.98E+00 0.00E+00 0.00E+00 l XE-135 CURIES 9.78E-01 0.00E+00 0.00E+00 0.00E+00 XE-133 CURIES 0.00E+00 3.20E-02 0.00E+00 0.00E+00 -
i TOTAL FOR PERIOD l CURIES l 6.82E+00 l 4.01E+00 l 0.00E+00 l 0.00E+00 l t
IODINES L I-133 CURIES 1.45E-04 8.38E-05 0.00E+00 0.00E+00 l I-131 CURIES 1.20E-05 3.88E-06 0.00E+00 0.008+00 l l 1.57E-04 l 8.76E-Os j 0.00E+00' l .0.00E+00 'l TOTAL FOR FEXIOD l CURIES [
i 4 PARTICULATES j OTHER --
l CURIES l 1.02E-03 l 6.78E-03 l 0.00E+00 l 0.00E+00 l TOTAL FOR PERIOD l CURIES l 1.02E-03 -l 6.78E-03 l 0.00E+00 l 0.00E+00 l t
- H-3 CURIES 2.35E+01 2.31E+01 0.00E+00 0.00E+00
' G-ALPHA CURIES 6.33E-07 3.42E-08 0.00E+00 0.00E+00 f.
j
- Zeroes in this table indicate that no radioactivity was present
- at detectable levels. See Table 2-7 for typical minimum s detectable concentrations.
l l
52 1
i
- - , , - - . , - , , , . ..,..,,-w, ,-,--w.,+--, -, -- ,.,-,- --- -,n, . , , , , , , .r,. -,,,-+--n n g ,,,,w..,,,,,+r c--.m-n-ww.,,...,--.,,-,-
I TABLE 2-2B*
Joseph M. Farley Nuclear Plant ,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 :
Gaseous Effluents-Mixed-Mode Level Releases !
Unit: 2 !
Starting : 1-Jan-1994 Ending : 30-Jun-1994 :
i
+
l CONTINUOUS MODE l BATCH MODE l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l f i
FISSION GASES
.....____________ ____...........__......______............__.........__________ l o
AR-41 CURIES 5.06E+00 8.91E+00 0.00E+00 0.00E+00 :
XE-133 CURIES 8.96E+00 6.47E-02 0.00E+00 0.00E+00 {
TOTAL FOR PERIOD l CURIES l 1.40E+01 l 8.97E+00 l 0.00E+00 l 0.00E+00 l ;
r IODINES !
I-133 CURIES 7.83E-06 8.44E-06 0.00E+00 0.00E+00 I-131 CURIES 1.84E-05 3.96E-06_ 0.00E+00 0.00E+00 ,
......_______ .... __.._________......................__... _______________ .__. t TOTAL FOR PERIOD l CURIES l 2.62E-05 l 1.24E-05 l 0.00E+00.l 0.00E+00 l i l
PARTICULATES !
i i
SR-90 CURIES 0.00E+00 3.21E-09 0.00E+00 0.00E+00 !
OTHER CURIES 6.60E-04 5.56E-04 0.00E+00 0.00E+00 :
TOTAL FOR PERIOD l CURIES l 6.60E-04 l 5.57E-04 l 0.00E+00 l 0.00E+00 l l j
H-3 CURIES 1.52E+01 2.11E+01 0.00E+00 0.00E+00 :'
G-ALPHA CURIES 7.73E-08 1.50E-08 0.00E+00 0.00E+00 I
h
- Zeroes in this table indicate that no radioactivity was present i at detectable levels. See Table 2-7 for typical minimum detectable concentrations.
53
l l
TABLE 2-2B0 1 Joseph M. Farley Nuclear Plant l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 !
Gaseous Effluents-Mixed-Mode Level Releases '
Unit: 2 i Starting : 1-Jul-1994 Ending : 31-Dec-1994 I i
................... ___.......__.__.......... i l CONTINUOUS MODE l BATCH MODE l l
.....____.__..................__...._______..............__.......___..._____.__ t NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l t
' FISSION GASES I AR-41 CURIES 1.01E+01 6.15E+00 1 0.00E+00 0.00E+00 i XE-135 CURIES 0.00E+00 1.93E+00 0.00E+00 0.00E+00 ;
XE-133 CURIES 0.00E+00 5.25E+00 l 0.00E+00 0.00E+00 i TOTAL FOR PERIOD l CURIES l 1.01E+01 l 1.33E+01 l 0.00E+00 l 0.00E+00 l i
............ ____________.___________.__.__......._____...........__............ l l'
PARTICULATES SR-90 CURIES 3.75E-16 0.00E+00 0.00E+00 0.00E+00 !
OTHER CURIES 9.70E-04 4.70E-04 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 9.70E-04 l 4.70E-04 l 0.00E+00 l 0.00E+00 l f H-3 CURIES 8.49E+00 7.99E+00 0.00E+00 0.00E+00 ,
G-ALPHA CURIES 3.52E-07 8.63E-07 0.00E+00 0.00E+00 !
1
- Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.
1 l.
.i 54
TABLE 2-2C* i Joseph M. Farley Nuclear Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 !
Gaseous Effluents-Mixed-Mode Level Releases Unit: Site ;
Starting : 1-Jan-1994 Ending : 30-Jun-1994 r
____................__. ...........__........ l l CONTINUOUS MODE l BATCH MODE l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l FISSION GASES ,
......................... ____ ...__._____............___........._______....... (
AR-41 CURIES 8.45E+00 1.47E+01 0.00E+00 0.00E+00 i KR-85M CURIES 0.00E+00 0.00E+00 8.55E-03 0.00E+00 l XE-135 CURIES 2.66E+00 1.32E-01 2.66E-01 9.68E-05 XE-133M CURIES 6.20E-01 0.00E+00 2.62E-01 0.00E+00 '
XE-133 CURIES 1.21E+02' 6.47E-02 2.36E+01 5.36E-03 XE-131M CURIES 0.00E+00 0.00E+00 3.37E-01 0.00E+00 !
KR-85 CURIES 0.00E+00 0.00E+00 1.07E+00 8.26E-02 TOTAL FOR PERIOD l CURIES l 1.33E+02 l 1.49E+01 l 2.55E+01 l 8.81E-02 l IODINES I-132 l CURIES 1.12E-04 0.00E+00 0.00E+00 0.00E+00 ,
0.00E+00 I-133 CURIES 2.76E-05 4.88E-05 0.00E+00 l I-131 CURIES 3.59E-03 6.33E-04 2.76E-07 0.00E+00 TOTAL FOR PERIOD l CURIES l 3.73E-03 l 6.82E-04 l 2.76E-07 l 0.00E+00 l r
PARTICULATES ;
I-131 CURIES 3.52E-06 2.74E-07 1.14E-08 0.00E+00 CR-51 CURIES 0.00E+00 7.84E-07 0.00E+00 0.00E+00 i CO-58 CURIES 0.00E+00 9.40E-07 0.00E+00 0.00E+00 ,
Y-88 CURIES 0.00E+00 0.00E+00 2.65E-04 0.00E+00 l SR-90 CURIES 0.00E+00 3.21E-09 0.00E+00 0.00E+00 OTHER CURIES 2.83E-03 1.05E-03 1.26E-04 1.84E-08
]
$..* '. . I 55
TABLE 2-2C* <
i Joseph M. Farley Nuclear Plant i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 i Gaseous Effluents-Mixed-Mode Level Releases i Unit: Site Starting : 1-Jan-1994 Ending : 30-Jun-1994 6
i l CONTINUOUS MODE l BATCH MODE l NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l
{
H-3 CURIES 1.92E+01 2.51E+01 0.00E+00 0.00E+00 l G-ALPHA CURIES 1.42E-07 3.84E-07 0.00E+00 0.00E+00 i i
i
~
- Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.
l l
+
l t
v b
b l
1 F
1 i
t 4
I i
l 1
l l
1 e
i l
56
\
)
I
TABLE 2-2C0 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting : 1-Jul-1994 Ending : 31-Dec-1994 l CONTINUOUS MODE l BATCH MODE l NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l FISSION GASES AR-41 CURIES 1.59E+01 1.01E+01 0.00E+00 0.00E+00 XE-135 CURIES 9.78E-01 1.93E+00 0.00E+00 0.00E+00 XE-133 CURIES 0.00E+00 5.28E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.69E+01 l 1.73E+01 l 0.00E+00 l 0.00E+00 l IODINES I-133 CURIES 1.45E-04 8.38E-05 0.00E+00 0.00E+00 I-131 CURIES 1.20E-05 3.88E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.57E-04 l 8.76E-05 l 0.00E+00 l 0.00E+00 l PARTICULATES SR-90 CURIES 3.75E-16 0.00E+00 ? 40 0.00E+00 OTHER CURIES 1.99E-03 7.25E-03 0. 0 m .0 0.00E+00 TOTAL FOR PERIOD l CURIES l 1.99E-03 l 7.25E-03 l 0.00E+00 l 0.00E+00 l H-3 CURIES 3.20E+01 3.10E+01 0.00E+00 0.00E+00 G-ALPHA CURIES 9.85E-07 8.98E-07 0.00E+00 0.00E+00 o Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.
57
j r
l 3.5.3 Ga cous Effluento - Ground Moda Releaces l
l
! The summaries of all gaseous effluent ground mode
- releases (includes listing by nuclide) are contained in the following tables :
Unit 1.1994 Ground Mode Summary : Table 2-3A ;
Unit 2 1994 Ground Mode' Summary : Table 2-3B l Site 1994 Ground Mode Summary : Table 2-3C-1 i
i i
l !
! l i
b i
t 3
l l
l 58
. . . .--.--..l
TABLE 2-3A*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 l Gaseous Effluents-Ground Level Releases Unit: 1 l Starting : 1-Jan-1994 Ending.: 30-Jun-1994 ;
l CONTINUOUS' MODE l BATCH MODE l ;
NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l l
l l
1 FISSION GASES .
l XE-133M CURIES 0.00E+00 0.00E+00 3.89E-02 0.00E+00 XE-133 CURIES 1.59E-01 0.00E+00 2.61E+00 0.00E+00 l
...........__.......__........... _.........__....._............................ I TOTAL FOR PERIOD l CURIES l 1.59E-01 l 0.00E+00 l 2.65E+00 l 0.00E+00 l [
IODINES l i
........__..._....________.... _____........................___...._____........ l I-133 CURIES 0.00E+00 0.00E+00 4.11E-07 0.00E+00 I i
I-131 CURIES 0.00E+00 0.00E+00 2.31E-05 0.00E+00 i TOTAL FOR PERIOD' l CURIES l 0.00E+00 l 0.00E+00 l 2.35E-05 l'O.00E+00 l l
.......____....__.__....................._____..__.....___.__........... ______. j PARTICULATES l
..................................__...__....................................... I I-131 CURIES 0.00E+00 0.00E+00 2.02E-07 0.00E+00 OTHER CURIES 1.17E-05 1.30E-45 0.00E+00 0.00E+00
'D3TAL FOR PERIOD l CURIES l 3.17E-05 l 1.30E-05 l 2.02E-07 l 0.00E+00 l H-3 CURIES l
l 6.18E-04 l 4.08E-04 l 4.37E-04 l 0.00E+00 l Zeroes in this table indicate that no radioactivity was present !
at detectable levels. See Table 2 7 for typical minimum detectable concentrations. j 4
l I
l l
59
l 5
TABLE 2-3A*
Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 :
Gaseous Effluents-Ground Level Releases Unit: 1 :
Starting : 1-Jul-1994 Ending : 31-Dec-1994 ;
l CONTINUOUS MODE l BATCH MODE l' ,
......___........_____......__.............................___............____.... i NUCLIDES RELEASED l UNIT l QUARTER 3 l QUARTER 4 l QUARTER 3 l QUARTER 4 l
...........................................__................................... L I
FISSION GASES t
TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l ;
3 L
IODINES h
T'. fAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l l PARTICULATES OTHER l CURIES l 4.85E-06 l 1.37E-05 l 0.00E+00 l 0.00E+00 l l TOTAL FOR PERIOD l CURIES l 4.85E-06 l 1.37E-05 l 0.00E+00 l 0.00E+00 l l i
H-3 l CURIES l 2.41E-04 l 3.91E-02 l 0.00E+00 l 0.00E+00 l i
l l
- Zeroes in this table indicate that no radir?-civity was present at detectable levels. See Table 2-7 for P fp dal minimum detectable concentrations.
60 i
-1 i
i i
TABLE 2-3B* ;
Joseph M. Farley Nuclear Plant ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents-Ground Level Releases l Unit: 2 ;
Starting : 1-Jan-1994 Ending : 30-Jun-1994 [,
l l CONTINUOUS MODE l BATCH MODE l i
NUCLIDES RELEASED l UNIT l QUARTER 1 l QUARTER 2 l QUARTER 1 l QUARTER 2 l !
t FISSION GASES i 1
i i
TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l .
f IODINES !
i
)
TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l l PARTICULATES OTHER l CURIES l 8.60E-06 l 8.73E-06 l 0.00E+00 l 0.00E+00 l l i
TOTAL FOR PERIOD l CURIES l 8.60E-06 l 8.73E-06 l 0.00E+00 l 0.00E+00 l H-3 l CURIES l 6.62E-04 l 3.57E-04 l 0.00E+00 l 0.00E+00 l i
l j
- Zeroes in this table indicate that no radioactivity was present at detectable levels. See Table 2-7 for typical minimum detectable concentrations.
1 i
61 1
l 1
1
-l l
i TABLE 2-3B* i Joseph M. Farley Nuclear. Plant ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 Gaseous Effluents-Ground Level Releases Unit: 2 .
Starting : 1-Jul.1994 Ending : 31-Dec-1994 !
f l CONTINUOUS' MODE l BATCH MODE l NUCLIDES RELEASED l UNIT l QUARTER 3.l QUARTER 4 l QUARTER 3 l QUARTER 4 l l t
t FISSION GASES ;
i i
TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l_0.00E+00 l 0.00E+00 l IODINES i
.........__...................______....................... ___............__... r P
TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00.l 0.00E+00 l ,
PARTICULATES !
r OTHER l CURIES l 3.85E-06 l 6.57E-06 l 0.00E+00 l 0.00E+00 l l TOTAL FOR PERIOD l CURIES l 3.85E-06 l 6.57E-Co l 0.00E+00 l 0.00E+00 l ;
4 j H-3 l CURIES l 3.09E-04 l 2.02E-04 l 0.00E+00 l 0.00E+00 l )1 8
1
- Zeroes in this table indicate that no radioactivity was present
.; at detectable levels. See Table 2-7 for typical minimum
, detectable concentrations. ;
i ;
i I
]
1 1
i f
a b
a 62
. . - . ~. . . - .-.
l l TABLE 2-3C*
j Joseph M. Farley Nuclear Plant ,
r ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 '
l Gaseous Effluents-Ground Level Releases l l Unit: Site l l
Starting : 1-Jan-1994 Ending : 30-Jun-1994 i
l CONTINUOUS MODE l. BATCH MODE l ,
NUCLIDES RELEASED l UNIT l QUARTER 1-l QUARTER 2 l QUARTER 1 l QUARTER 2 l t
f t
FISSION GASES [
XE-133M CURIES 0.00E+00 0.00E+00 3.89E-02 0.00E+00 i XE-133 CURIES 1.59E-01 0.00E+00 2.61E+00 0.00E+00 ;
TOTAL FOR PERIOD l CURIES l 1.59E-01 l'O.00E+00 l 2.65E+00 l 0.00E+00 l ,
IODINES ,
I-133 CURIES 0.00E+00 0.00E+00 4.11E-07 0.00E+00 I-131 CURIES 0.00E+00 0.00E+00 2.31E-05 0.00E+00 TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 2.35E-05 l 0.00E+00 l
...................____....................__............._____.__.____..__ .... 1 PARTICULATES L I-131 CURIES 0.00E+00 0.00E+00 2.02E-07 0.00E+00 i l OTHER CURIES 2.03E-05 2.17E-05 0.00E+00 0.00E+00 ,
TOTAL FOR PERIOD l CURIES l 2.03E-05 l 2.17E-05 l 2.02E-07 l 0.00E+00 l t f
! H-3 l CURIES l 1.28E-03 l 7.65E-04 l 4.37E-04 l 0.00E+00 l I l'
l
- Zeroes in this table indicate that no radioactivity was present ,
at detectable levels. See Table 2-7 for typical minimum ,
detectable concentrations. i l
63 l
- - ,en
TABLE 2-3C0 Joseph M. Farley Nuclear Plant i ANNUAL RADIOACTIVE EFFLUENT RELEASE. REPORT - 1994 l I
Gaseous Effluents-Ground Level Releases Unit: Site j Starting : 1-Jul-1994 Ending : 31-Dec-1994 i
l CONTINUOUS MODE l _ BATCH MODE l l NUCLIDES RELEASED l UNIT l QUARTER 3.l QUARTER 4 l QUARTER 3.l QUARTER 4 l !
-........___. __.. .........___........__...........__.......__.................. j i
FISSION GASES l TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00-l 0.00E+00 l t
t IODINES -l TOTAL FOR PERIOD l CURIES l 0.00E+00 l 0.00E+00 l 0.00E+00 l 0.00E+00 l PARTICULATES OTHER l CURIES l 8.70E-06 l 2.03E-05'l 0.00E+00 l 0.00E+00 l !
TOTAL FOR PERIOD l CURIES l 8.70E-06 l 2.03E-05 l 0.00E+00 l 0.00E+00 l i
1 H-3 l CURIES l 5.50E-04 l 3.93E-02 l 0.00E+00 l 0.00E+00 l l 4
t o Zeroes in this table indicate that no radioactivity was present l at detectable levele. See Table 2-7 for typical minimum detectable concentrations.
i j
64
)
i 3.6 Radiological Impact )
The air doses and organ doses due to gaseous effluents for l Units l'and 2 are provided in the following tables in order i to sho conformance with the limits of ODCM 3.1.3 and ODCM
, Unit 1 1994 Air Doses : Table 2-4A :
Unit 2 1994 Air Doses : Table 2-4B l Unit _1 1994 Organ Doses : Table 2-5A !
Unit 2 1994 Organ Doses : Table 2-5B "
I a
i i
I l !
f l !
I i
W i
i i
f i
d d
d d I i i i
4 1
- 65 i 1 1
TABLE 2-4A !
I Joseph M. Farley Nuclear Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 I t
AIR DOSES DUE TO GASEOUS RELEASES :
Unit: 1 l Starting: 01-Jan-1994 Ending: 30-Jun-1994 j I
1 Cumulative Doses per Quarter ,
Type ODCM Units Quarter % of Quarter % of ,
Radi- Limit Limit ation Gamma 5.0 mrad 4.46E-03 8.91E-02 1.87E-03 3.74E-02 't Beta 10.0 mrad 1.02E-02 1.02E-01 6.73E-04 6.73E-03 l f
1 i
Cumulative Doses per Year ,
Type ODCM Units Year to % of r of Limit Ending ODCM ,
Radi- Date Limit ation 1
Gamma 10.0 mrad 6.33E-03 6.33E-02 -
Beta 20.0 mrad 1.09E-02 5.45E-02 ;
l l
1 a
I i
1 66
TABLE 2-4A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994
-AIR DOSES DUE TO GASEOUS RELEASES ;
Unit: 1 Starting: 01-Jul-1994 Ending: 31-Dec-1994 j i
i i
Cumulative Doses per Quarter ;
Type ODCM Units Quarter % of Quarter % of ,
of Limit 3 ODCM 4 ODCM i Radi- Limit Limit !
ation :
Gamma 5.0 mrad 1.92E-03 3.85E-02 1.27E-03 2.54E-02 Beta 10.0 mrad 7.38E-04 7.38E-03 4.48E-04 4.48E >
i i
i Cumulative Doses per Year j Type ODCM Units Year to % of ;
of Limit Ending ODCM j Radi- Date Limit l ation l Gamma 10.0 mrad 9.52E-03 9.52E-02 !
Beta 20.0 mrad 1.21E-02 6.04E-02 l s e r
l 4
i b
i I
i f
f i
4 67 t
-. .. - - . . . . +
l 4 - p TABLE 2-4B >
Joseph M. Farley Nuclear Plant' !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 AIR DOSES DUE TO GASEOUS RELEASES i Unit: 2 .
Starting: 01-Jan-1994 Ending: 30-Jun-1994 !
l i
Cwmulative Doses per Quarter !
. .__............___............_______.............................___.... j Typa ODCM Units. Quarter % of Quarter % of [
2
~
of: Limit 1 ODCM ODCM Radi- Limit Limit i ation ,
Gamma 5.0 mrad 1.72E-03 3.44E-02 2.84E-03 5.67E-02 Beta 10.0 mrad 8.90E-04 8.90E-03 1.00E-03 1.00E-02 '
i Cumulative Doses per Year [
Type ODCM Units Year to % of of Limit Ending ODOM Radi- Date Limit ;
ation :
J . .__...___....................................__.____.............__...... ,
Gamma 10.0 mrad 4.55E-03 4.55E-02 !
Beta 20.0 mrad 1.89E-03 9.46E-03 ;
I k
i r
[
1 I
i 68 4
n i
.._~_,,,l
TABLE 2-4B Joseph M. Farley Nuclear Plant ,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 I AIR DOSES DUE TO GASEOUS RELEASES j
. Unit: 2 l Starting: 01-Jul-1994 Ending: 31-Dec-1994 j 1 1 1
i i Cumulative Doses per Quarter l 1 ......... .................._______.... ..__........__.___ __...._______.. ;
l Typ3 ODCM Units Quarter % of Quarter % of l J
i Radi- Limit Limit I
. ation l
$ Gamma 5.0 mrad 3.21E-03 6.42E-02 2.15E-03 4.30E-02 l l, Bata 10.0 mrad' 1.13E-03 1.13E-02 1.04E-03 1.04E-02 i i t
) Cumulative Doses per Year l
< ation ;
i Gamma 10.0 mrad 9.91E-03 9.91E-02 ;
Beta 20.0 mrad 4.07E-03 2.03E-02 !
t 1 .............. ____.....____ ..........................................__.
4 i
i l
l N
4 1
k i
a k
69 l
i i
b n
- ,- ,.m, -
c-- - - s
TABLE 2-5A Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, ,
AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-1994 Ending: 30-Jun-1994 t
Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 2.18E-04 2.91E-03 3.80E-05 5.07E-04 Liver 7.5 mrem 7.68E-04 1.02E-02 5.89E-04 7.86E-03 TBody 7.5 mrem 6.82E-04 9.10E-03 5.75E-04 7.66E-03 Thyroid 7.5 mrem 6.62E-02 8.82E-01 1.19E-02 1.59E-01 Kidney 7.5 mrem 8.95E-04 1.19E-02 6.11E-04 8.15E-03 Lung 7.5 mrem 5.70E-04 7.60E-03 5.55E-04 7.40E-03 ,
GILLI 7.5 mrem 5.87E-04 7.83E-03 5.58E-04 7.44E-03 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 2.56E-04 1.71E-03 Liver 15.0 mrem 1.36E-03 9.05E-03 TBody 15.0 mrem 1.26E-03 8.38E-03 Thyroid 15.0 mrem 7.81E-02 5.21E-01 i
- Kidney 15.0 mrem 1.51E-03 1.00E-02 Lung 15.0 mrem 1.12E-03 7.50E-03 mrem GILLI 15.0 1.15E-03 7.64E-03 l
)
g W
70 1 1
i i
! TABLE 2-5A l Joseph M. Farley Nuclear Plant l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jul-1994 Ending: 31-Dec-1994 i 1
l Cumulative Doses per Quarter f
.................... ........................._______.....___..__......... 1 Organ ODCM Unit Quarter % of Quarter % of l Limit 3 ODCM 4 ODCM !
Limit Limit l i
Bone 7.5 mrem 8.63E-08 1.15E-06 6.32E-07 8.42E-06 Liver 7.5 mrem 3.21E-03 4.28E-02 3.21E-03 4.28E-02 ,
TBody 7.5 mrem 3.21E-03 4.28E-02 3.21E-03 4.28E-02 Thyroid 7.5 mrem 3.48E-03 4.64E-02 3.31E-03 4.41E-02 Kidney 7.5 mrem 3.21E-03 4.28E-02 3.21E-03 4.28E-02 Lung 7.5 mrem 3.21E-03 4.28E-02 3.21E-03 4.28E-02 GILLI 7.5 mrem 3.21E-03 4.28E-02 3.21E-03 4.28E-02 ;
......._____.............................____............................. j l
- I Cumulative Doses per Year l Organ ODCM Units Year to % of .
l Limit Ending ODCM !
Date Limit j Bone 15.0 mrem 2.57E-04 1.71E-03 Liver 15.0 mrem 7.78E-03 5.18E-02 ,
TBody 15.0 mrem 7.67E-03 5.12E-02 Thyroid 15.0 mrem 8.49E-02 5.66E-01 ,
Kidney 15.0 mrem 7.93E-03 5.28E-02 '
Lung 15.0 mrem 7.54E-03 5.03E-02 GILLI 15.0 mrem 7.56E-03 5.04E-02 I l
1 1
t l
l 71 l
l
TABLE 2-SB >
Joseph M. Farley Nuclear Plant ,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994- l' DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES !
Unit: 2 l Starting: 01-Jan-1994 Ending: 30-Jun-1994 :
t I
Cumulative Doses per Quarter i Organ ODCM Unit Quarter t of Quarter t of Limit 1 ODCM 2 ODCM t Limit Limit Bonn. 7.5 mrem 1.12E-06 1.50E-05 2.56E-06 3.41E-05 Liver 7.5 mrem 2.07E-03 2.76E-02 2.88E-03 3.84E-02 ,
TBody 7.5 mrem 2.07E-03 2.76E-02 2.88E-03 3.84E-02 Thyroid 7.5 mrem 2.41E-03 3.21E-02 2.95E-03 3.94E-02 :
Kidney 7.5 mrem 2.07E-03 2.77E-02 2.88E-03 3.84E-02 ;
Lung 7.5 mrem 2.07E-03 2.76E-02 2.88E-03 3.84E-02 ,
GILLI 7.5 mrem 2.07E-03 2.76E-02 2.88E-03 3.84E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 3.68E-06 2.45E-05 Liver 15.0 mrem 4.95E-03 3.30E-02 ,
TBody 15.0 mrem 4.95E-03 3.30E-02 Thyroid 15.0 mrem 5.36E-03 3.57E-02 Kidney 15.0 mrem 4.95E-03 3.30E-02 Lung 15.0 mrem 4.95E-03 3.30E-02 GILLI 15.0 mrem 4.95E-03 3.30E-02 72
TABLE 2-5B Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-1994 Ending: 31-Dec-1994 Cumulative Doses per Quarter Organ ODCM Unit Quarter % of Quarter % of Limit 3 ODCM 4 ODCM Limit Limit Bone 7.5 mrem 1.75E-07 2.33E-06 7.11E-14 9.47E-13 Livar 7.5 mrem 1.16E-03 1.55E-02 1.09E-03 1.45E-02 TBody 7.5 mrem 1.16E-03 1.55E-02 1.09E-03 1.45E-02 Thyroid 7.5 mrem 1.16E-03 1.55E-02 1.09E-03 1.45E-02 Kidney 7.5 mrem 1.16E-03 1.55E-02 1.09E-03 1.45E-02 Lung 7.5 mrem 1.16E-03 1.55E-02 1.09E-03 1.45E-02 GILLI 7.5 mrem 1.16E-03 1.55E-02 1.09E-03 1.45E-02 Cumulative Doses per Year Organ ODCM Units Year to % of Limit Ending ODCM Date Limit Bone 15.0 mrem 3.85E-06 2.57E-05 Liver 15.0 mrem 7.20E-03 4.80E-02 TBody 15.0 mram 7.20E-03 4.80E-02 Thyroid 15.0 mrem 7.61E-03 5.07E-02 Kidney 15.0 mrem 7.20E-03 4.80E-02 Lung 15.0 mrem 7.20E-03 4.80E-02 GILLI 15.0 mrem 7.20E-03 4.80E-02 l
l l
i l
i l
73 l
i l
l TABLE 2-7 Joseph M. Farley Nuclear Plant ,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 TYPICAL GASEOUS MDC'S ACHIEVED ON COUNTING SYSTEM :
i l
l Nuclide MDC(uCi/ML) ,
MN-54 3.21E-15 !
CO-58 1.53E-14 '
FE-59 7.96E-15 .
CO-60 1.95E-14 '
ZN-65 2.34E-14 I l
MO-99 1.81E-13 .
CS-134 1.41E-14
~
CS-137 7.83E-15 CE-141 6.96E-15 l CE-144 .3.47E-14 i KR-87 8.18E-07 KR-88 3.94E-08 i XE-133 4.30E-08 XE-133M 4.82E-08 XE-135 1.78E-08 ,
XE-138 1.99E-07 ;
I-131 9.67E-15 I-133 1.80E-13 l
74
i 4.0 SOLID WASTE This section contains information regarding the types and quantities of solid radioactive waste shipped offsite during 1994 as required in ODCM 7.2.2.4. This infcrmation is presented- t in Table 3. '
1 The error involved in determining the contents of solid radwaste !
shipments is estimated to be less than + or - 15%. l i
i 5
h s
f 4
t l
t I
i i
l
)
75 l
, TABLE 3 l
Joseph M. Farley Nuclear Plant '
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-1994 Ending: 30-Jun-1994 :
A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL .
(not irradiated fuel) i
- 1. Type of Waste. UNITS 6-Months 3 ,
- a. Spent resins, Filter sludges, m 1.050E+01 evaporator bottoms, etc. Ci* 8.450E+01 i 3
- b. Dry compressible waste, contaminated m 2.72E+01 equipment, etc. Ci* 1.39E+01 1
3
- c. Irradiated components, control m None rods,-etc. Ci* None l
3 i
- d. Other (describe) m None Ci* None ,
l
- Measured and/or estimated by correlations in accordance >
with 10CFR61.55.
i i
w 76
TABLE 3 Joseph M.-Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-1994 Ending: 30-Jun-1994 (continued)
- 2. Estimate of major nuclide composition.
- a. NI-63 24.4%
CO-58 21.8%
CO-60 18.8%
FE-55 15.6%
CR-51 4.2%
CS-137 3.2%
CS-134 2.5%
MN-54 2.4%
NB-95 1.8%
ZR-95 1.1%
- b. FE-55 44.6%
CO-58 13.7%
CO-60 11.2%
CR-51 7.7%
H-3 4.5%
NI-63 3.9%
CS-137 3.7%
NB-95 3.0%
MN-54 2.2%
ZR-95 1.7%
CS-134 1.3%
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 49 Highway Chem-Nuclear Systems, Inc.
Barnwell, South Carolina.
77
TABLE 3 Joseph M. Parley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jan-1994 Ending: 30-Jun-1994 (continued)
- 4. Type of Container (la) Type of Container (1b)
High Integrity Containers. Strong Tight Containers.
Strong Tight Containers.
- 5. Solidification Agent (la) Solidification Agent (ib)
All items shipped dewatered None with the exception of Sludge which was shipped solidified with Hittman Cement.
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination None N/A N/A 78
TABLE 3 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Starting: 01-Jul-1994 Ending: 31-Dec-1994 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL CR DISPOSAL (not irradiated fuel)
- 1. Type of Waste. UNITS 6-Months 3
- a. Spent resins, Filter sludges, m 6.810E+00 evaporator bottoms, etc. Ci* 3.980E+02 3
- b. Dry compressible waste, contaminated m 5.750E+00 equipment, etc. Ci* 2.700E-01 3
- c. Irradiated components, control m 2.900E-01 rods, etc. Ci* 3.840E+00 3
- d. Other (describe) m None Ci* None
- Measured and/or estimated by correlations in accordance with 10CFR61.55.
79
TABLE 3' Joseph M. Farley Nuclear Plant ;
- SOLID WASTE AND IRRADIATED FUEL SHIPMENTS j Starting
- 01-Jul-1994 Ending: 31-Dec-1994 l I' l
) (continued) l 1
t
- 2. Estimate of major nuclide composition. !
1
- a. NI-63 35.2%
CO-58 22.1% !
4 CO-60 20.7% !
l CS-137. 5.9% l i FE-55 5.9% !
l CS-134 '4.5% t
! MN-54 4.1% i i b. FE-55 46.3%
. CO-58 16.0%
, NB-95 5.8%
i ZR-95 4.8%
4 CR-51 4.1% !
l CS-137 1.8% l s MN-54 1.8% i
! c. CO-60 44.8% [
4 NI-63 35.8%
FE-55 10.6%
SR-90 3.9%
j! ZN-65 3.3%
1 j 3. Solid Waste Disposition
) Number of Shipments Mode of Transportation Destination
?
12 Highway Chem-Nuclear
- Systems, Inc.
, Barnwell, South
- Carolina.
I i
i 4
80 l !
L i
y .- 7 , , _ , . . _ ., , , - - -
j TABLE 3 Joseph M. Farley Nuclear Plant !
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l
- Starting
- 01-Jul-1994 Ending: 31-Dec-1994 j (continued) l 1.
i .
- 4. Type of Container (la) Type of Container (ib) ;
1 i i High Integrity Containers. Strong Tight Containers.
Strong Tight Containers.
Type of Container (ic) l High Integrity Containers.
- 5. Solidification Agent (la) Solidification Agent (1b)
All items shipped dewatered. None Solidification Agent (1c)
None ;
B. IRRADIATED FUEL SHIPMENTS (Dispositien) F Number of Shipments Mode of Transportation Destination None N/A N/A r
i I
i f
I i
l l
l 81
-- _ . _ - . - . .- . . _- .- .. - .=
- - 5.0 ONSITE DOSES TO MEMBERS OF THE PUBLIC
~
require assessment.of the radiation doses from radioactive liquid 4 and gaseous effluents to MEMBERS OF THE PUBLIC due to their
{ activities inside the SITE BOUNDARY (ODCM Figure 10-1). However, i
~
this assessment has been performed for 1994 using the methods !
described in ODCM 6.2 and is included in this section as '
Table 4-1. !
] :
1 1 !
i i
! I i
i 1
4
.l
! l
.t 1
i i !
l- !
i 1
i t
l I i i 1 4
i I
i.
I l
) !
I i !
J 4 i i
k i 82 ;
}
d TABLE 4-1 4
Joseph M. Farley Nuclear Plant
! ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 '
- DOSE TO A MEMBER OF THE PUBLIC ,
- DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY
- Unit
- Site
] Starting: 01-Jan-1994 Ending: 30-Jun-1994 ;
i i Page: 1 Location Name VISITOR LOCATION 1 (VIS. CENTER) 3 Distance (kilometers) 3.06E-01 l Sector WSW Occupancy Factor 1.37E-03 (1.20E+01 hr/yr) ;
Age Group CHILD j Ground Level Releases: i Noble Gas X/Q (sec/m3) 1.04E-04 Particulate X/Q (sec/nG) 1.04E-04 Particulate D/Q (m-2) 4.80E-07 {
t Mixed Mode Releases: '
Noble Gas X/Q (sec/m3) 8.80E-06 Particulate X/Q (sec/m3) 8.80E-06 Particulate D/Q (m-2) 6.20E-08 i Elevated Releases:
Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 5.27E-05 5.05E-05 1.03E-04 1.03E Liver mrem 6.16E-05 6.09E-05 1.23E-04 1.23E-04 TBody mrem 6.16E-05 6.09E-05 1.22E-04 1.22E-04 Thyroid mrem 8.74E-05 6.30E-05 1.50E-04 1.50E-04 Kidney mrem 6.17E-05 6.09E-05 1.23E-04 1.2*2-04 Lung mrem 6.16E-05 6.09E-05 1.22E-04 1.22E-04 GI-LLI mrem 6.16E-05 6.09E-05 1.22E-04 1.22E-04 83 i
l i
TABLE 4-1 Joseph M. Farley Nuclear Plant ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT .1994 i DOSE TO A MEMBER OF THE PUBLIC l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY '
Unit: Site-Starting: 01-Jan-1994 Ending: 30-Jun-1994 .
Page: 2 i
I Location Name VISITOR LOCATION 2 (SW POND) :
Distance (kilometers) 9.66E-01 l Sector SSW l Occupancy Factor 7.53E-03 (6.60E+01 hr/yr) i Age Group CHILD {
Ground Level Releases: l Noble Gas X/Q (sec/m3) 4.74E-05 ,
Particulate X/Q (sec/m3). 4.74E-05 ,
Particulate D/Q (m-2) 1.31E-07 Mixed Mode Releases: 1 Noble Gas X/Q (sec/nG) 9.75E-07 !
Particulate X/Q (sec/m3) 9.75E-07 i Particulate D/Q (m-2) 2.78E-08 :
Elevated Releases: l Noble Gas X/Q (sec/m3) N/A j Particulate X/Q (sec/r N/A l Particulate D/Q (m-2) N/A .
....._______ .._______________.................._____......._______......___. i Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending )
Date
............_______.....______..__.___.... ___...____..__ _____....___....__. ]
Bone mrem 3.95E-05 3.08E-05 7.03E-05 7.03E-05 Liver mrem 4.50E-05 3.71E-05 8.21E-05 8.21E-05 TBody mrem 4.49E-05 3.71E-05 8.21E-05 8.21E-05 Thyroid mrem 6.39E-05 3.84E-05 1.02E-04 1.02E-04 Kidney mrem 4.50E-05 3.71E-05 8.21E-05 8.21E-05 Lung mrem 4.49E-05 3.71E-05 8.20E-05 8.20E-05 GI-LLI mrem 4.49E-05 3.71E-05 8.20E-05 8.20E-05 84 l
TABLE 4-1 Joseph M. Farley Nuclear Plant
- ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSE TO A MEMBER OF THE PUBLIC l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY i Unit: Site ,
Starting: 01-Jan-1994 Ending: 30-Jun-1994 l I
Page: 3 ,
t Location Name VISITOR LOCATION 3 (RW DISCH.) !
Dictance (kilometers) 1.64E+00 Sector SE Occupancy Factor 1.14E-02 (9.99E+01 hr/yr) !
Age Group CHILD ,j i
Ground Level Releases:
Noble Gas X/Q (sec/m3) 1.63E-05 Particulate X/Q (sec/m3) 1.63E-05 !
Particulate D/O (m-2) 4.55E-08 '
i Mixed Mode Releases: l Noble Gas X/Q (sec/m3) 7.05E-07 Particulate X/O (sec/m3) 7.05E-07 l Particulate D/Q (m-2) 1.39E-08 i
)
Elevated Releases:
Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Bone mrem 3.77E-05 3.37E-05 7.14E-05 7.14E-05 Liver mrem 4.37E-05 4.06E-05 8.43E-05 8.43E-05 TBody mrem 4.37E-05 4.06E-05 8.43E-05 8.43E-05 Thyroid mrem 6.20E-05 4.10E-05 1.04E-04 1.04E-04 Kidney mrem 4.37E-05 4.0fE-05 8.43E-05 8.43E-05 Lung mrem 4.36E-05 4.06E-05 8.42E-05 8.42E-05 l GI-LLI mrem 4.36E-05 4.06E-05 8.42E-05 8.42E-05 :
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1 TABLE 4-1 Joseph M. Farley Nuclear Plant ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-1994 Ending: 31-Dec-1994 Page: 1 Location Name VISITOR LOCATION 1 (VIS. CENTER)
Dictance (kilometers) 3.06E-01 Sector WSW Occupancy Factor 1.37E-03 (1.20E+01 hr/yr)
Age Group CHILD Ground Level Releases:
Noble Gas X/Q (sec/m3) 1.04E-04 Particulate X/Q (sec/m3) 1.04E-04 Particulate D/Q (m-2) 4.80E-07 Mixed Mode Releases:
Noble Gas X/Q (sec/m3) 8.80E-06 Particulate X/Q (sec/m3) 8.80E-06 Particulate D/Q (m-2) 6.20E-08 Elevated Releases:
Noble Gas X/Q (sec/m3) N/A .
Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Ycar to 3 and 4 2nding Date Bone mrem 5.37E-05 3.47E-05 8.83E-05 1.92E-04 Liver mrem 6.73E-05 4.79E-05 1.15E-04 2.38E-04 TBody mrem 6.73E-05 4.79E-05 1.15E-04 2.38E-04 Thyroid mrem 6.76E-05 4.81E-05 1.16E-04 2.66E-04 Kidney mrem 6.73E-05 4.79E-05 1.15E-04 2.38E-04 i Lung mrem 6.73E-05 4.79E-05 1.15E-04 2.38E-04 l GI-LLI mrem 6.73E-05 4.79E-05 1.15E-04 2.38E-04 I l
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TABLE 4-1 Joseph M. Farley Nuclear Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSE TO 1 MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE. BOUNDARY Unit: Site Starting: 01-Jul-1994 Ending: 31-Dec-1994 '
l Page: 2 l i
Location Name' VISITOR LOCATION 2 (SW POND)
Distance (kilometers) 9.66E-01 l Sector SSW '
Occupancy Factor 7.53E-03 (6.60E+01 hr/yr)
Age Group CHILD !
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~
Ground Level Releases:
Noble Gas X/Q (sec/m3) 4.74E-05 Particulate X/Q (sec/m3) 4.74E-05 ,
Particulate D/Q (m-2) 1.31E-07 l 1
Mixed Mode Releases
- Noble Gas:X/Q (sec/m3) 9.75E-07 i Particulate X/Q (sec/m3) 9.75E !
Particulate D/Q (m-2) 2.78E-08 l Elevated Releases: !
Noble Gas X/Q (sec/m3) N/A !
Particulate X/Q (sec/m3) N/A l Particulate D/Q (m-2) N/A !
Units Quarter 3 Quarter 4 Quarters Year to i 3 and 4 Ending i Date )
..._______....._______............__..__........___.___..__.___...___.....___ 1 Bone mrem 3.27E-05 2.11E-05 5.38E-05 1.24E-04 l Liver mrem 4.10E-05 2.96E-05 7.05E-05 1.53E-04 TBody mrem 4.10E-05 2.96E-05 7.05E-05 1.53E-04 )
Thyroid mrem 4.12E-05 2.96E-05 7.05E-05 1.73E-04 Kidney mrem 4.10E-05 2.96E-05 7.05E-05 1.53E-04 Lung mrem 4.10E-05 2.96E-05 7.05E-05 1.53E-04 GI-LLI mrem 4.10E-05 2.96E-05 7.05E-05 1.53E-04 G
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i TABLE 4-1 l Joseph M. Farley Nuclear Plant i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSE TO A MEMBER OF THE PUBLIC l DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY l Unit: Site l Starting: 01-Jul-1994 Ending: 31-Dec-1994 i
Page: 3 ,
e l
Location Name VISITOR LOCATION 3 (RW DISCH.) !
Distance (kilometers) 1.64E+00 Sector SE !
i Occupancy Factor 1.14E-02 (9.99E+01 hr/yr)
Age Group CHILD l l
Ground Level Releases: !
Noble Gas X/Q (sec/m3) 1.63E-05 Particulate X/Q (sec/m3) 1.63E-05 Particulate D/Q (m-2) 4.55E-08 -
l Mixed Mode Releases: !
Noble Gas X/Q (sec/m3) 7.05E-07 Particulate X/Q (sec/m3) 7.05E-07 -
Particulate D/Q (m-2) 1.39E-08 I Elevated Releases:
Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/nG) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending !
Date
............................................................................. j Bone mrem 3.58E-05 2.31E-05 5.89E-05 1.30E-04 i Liver mrem 4.49E-05 3.21E-05 7.69E-05 1.61E-04 ,
TBody mrem 4.48E-05 3.21E-05 7.69E-05 1.61E-04 {
Thyroid mrem 4.50E-05 3.22E-05 7.72E-05 1.81E-04 !
Kidney mrem 4.49E-05 3.21E-05 7.69E-05 1.61E-04 Lung mrem 4.48E-05 3.21E-05 7.69E-05 1.61E-04 j GI-LLI mrem 4.48E-05 3.21E-05 7.69E-05 1.61E-04 i
............................................................................. l 88
6.0 MISCELLANEOUS This section contains several items which are only required to be reported under certain conditions. These include radiation dose assessments to show conformance with 40CFR190 (if required by ODCM 5.1.2), licensee initiated changes to the ODCM within the last year, deviations in the Radioactive Effluent Control Program within the last year pursuant to ODCM 7.2.2.6, major changes to the liquid or gaseous radwaste treatment systems as required by ODCM 2.1.5 and 3.1.6, and any changes to the solid radwaste treatment sytem pursuant to the Process Control Program (PCF).
6.1 Total Dose From Uranium Fuel Cycle In accordance with Technical Specification 6.8.3.e(x), the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or to any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem (as stated in ODCM 5.1).
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of ODCM 2.1.3, 3.1.3, or 3.1.4, calculations shall be made according to ODCM 5.2 methods to determine whether the above (ODCM 5.1) limits have been exceeded (as stated in ODCM 5.1.2).
Since none of the ODCM 2.1.3, 3.1.3, or 3.1.4 limits were exceeded during 1994, no calculations were required.
6.2 Licensee Initiated Changes to the ODCM Revision 14 to the ODCM is attached. This revision was made to replace a milk sampling location which was no longer available.
6.3 Program Deviations l
This section contains any deviations from the composite sampling or MDC requirements included in ODCM Tables 2-3 and 3-3.
There were no deviations from composite sampling or MDC requirements on Unit 1 during 1994.
A deviation from composite sampling requirements occurred on Unit 2 during Quarter 4 in that a Containment Purge particulate filter for one of the weeks was inadvertently discarded prior to being used for composite analysis. Composite analysis for Unit 2 Containment Purge was completed using the remaining particulate filters for the month in question. This incident is documented in Chemistry Incident No. 0-95-001.
89 4
There wara no dsviations from MDC rcquiremtnte on Unit 2 during 1994.
6.4 Major Changes to the Radwaste Treatment Systems There.'were no major changes to the Radwaste Treatment' Systems during.1994.
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- 1. Procockare 14mber (NF- O Af- 08) procedure title Revision 14mber /3
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h ao veided . . . . . . . . . . . . . . . . . . . . . . . . .New Revision Num
[) Temporary change Effective tattil Next Permanent Rev
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[] ' temporary Giange one Time only or nog'd b Dates 'Jils temporary change is effective y From Plant Conditions.Ihrough tot
, [] This Proonshare is an infrequently performed test or evolution.
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, 2. Change susumary j 2.1 Procedure page mmber(s) Affacted by Onange(s) 9-N. + - el .
at l 2.2 Description of Qiange(s) # t H 6 F r#8L E' F 4 // V 4 s 9 -/9) /JA6
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- 3. Prepared ny hA.N N. , C&vatexacNTL TNh' sipature f. 9/- Q V Title cate l 4. noviewed my Y hh , kv. f&w / 14-l u pipsture' Tine cate l i5. Cross-cisciplinary/Mulc moview .
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- 1) Member Greg Staff
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(sipature/Date, required within 60 days of tegorary
[] Group supervisor v ,,
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! [] Vice President.dkaclear /
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NUCLEAR SUPPORT AO CFR 50.59 EVALUATION FORM SHEET 1 OF 5 A Unit Number: [ ] One [ ] Two [X) Shared Activity Title and Number Offsite Dose Calculation Revision Number 14 Manual (ODCMi FNP-0-M-Oll B 10 CFR 50.59 SCREENING Does the document to which this evaluation applies represent:
- 1. [ ] Yes [X) No A change to the facility as described in the FSAR?
Basis for answer: No physical chances to the olant are reouired. only chances to the ODCM are beine made to chance the milk samolino coint from one dairy to another.
- 2. [ ] Yes [X) No A change to procedures described in the FSAR?
Basis for answer: The location for oatherino a milk samole is described in the ODCM. No FSAR chances are recuired to support the ODCM chance.
- 3. [ ] Yes [X) No A test or experiment not described in the FSAR7 Basis for answer The chance in milk samole locations is not considered to be a test or experiment.
- 4. [ ] Yes [X) No A change to the Technical Specifications and/or Environmental Technical Specifications incorporated into the operating license?
Basis for answer: The technical specifications recuire licensee chances to the ODCM to be documented and reviewed. This chance to the ODCM does not chance technical specifications.
If ANY of the four questions in Section B are answered "Yes", then PORC review of the safety evaluation is required prior to implementation.
C Preparer k Dates /~2J- f Reviewed By: Dates Reviewer: , ,Date:/ d! h Reviewed By: Date Reviewed By: Date: [ '
f Reviewed By: Date:
Reviewed By: Date: Approved By: Date:
Reviewed By: Date: FNP Approved: h Date:2 * /
- k'f Reviewed By: Date: PORC Review: Date:2-l-if[
Reviewed By: Dates NORB Reviews Date: _
GS$k
[Ni+ Q hes th/ 4 h akumy or nbdYth f hu bdor hfw
.< @ ant & & -
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FARLEY NUCLEAR PLANT 10 CFR 50.59 EVALUATION SHEET 2 0F 5 l
l
, SAFETY EVALUATION:
l
- 1. ( ) YES ; (XX) NO May the proposed activity increase the probability of occurrence of an accident previously evaluated in the FSAR7 BASIS FOR ANSWER: See attached safety evaluation. 6
- 2. ( ) YES ; (XX) NO May the proposed activity increase the consequences of an accident previously .
evaluated in the FSAR?
BASIS FOR ANSWER: See attached safety evaluation.
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- 3. ( ) YES ; (XX) NO May the proposed activity increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the FSAR?
BASIS FOR ANSWER: See attached safety evaluation.
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- 4. ( ) YES ; (XX) N0 May the proposed activity increase the j consequences of a malfunction of equipment i important to safety previously evaluated in !
in the FSAR?
.i BASIS FOR ANSWER: See attached safety evaluation.
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2
FARLEY NUCLEAR PLANT 10 CFR 50.59 EVALUATION SHEET 3 0F 5 SAFETY EVALUATION (CONTINUED):
- 5. ( ) YES ; (XX) NO May the proposed activity create the l possibility of an accident of a different type than any previously evaluated in the FSAR?
BASIS FOR ANSWER: See attached safety evaluation.
l 6. ( ) YES ; (XX) NO May the proposed activity create the possibility of a malfunction of equipment important to safety of a different type than any previously evaluated in the FSAR?
BASIS FOR ANSWER: See attached safety evaluation.
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- 7. ( ) YES ; (XX) NO Does the proposed activity reduce the margin l
of safety as defined in the basis for any Technical Specification?
BASIS FOR ANSWER: See attached safety evaluation.
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If the answer to any of the questions in Section D is "YES", an unreviewed l safety question may be indicated. Approval from the NRC is required before I l
the document / activity may be implemented.
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Joseph M. Farley Nuclear Plant Units 1 and 2 Offsite Dose Calculation Manual Changes Revision 14 Safety Evaluation (Sheet 4 of 5)
Backaround The Farley Offsite Dose Calculation Manual (ODCM) describes the methods used to comply with the radiological release requirements of the Farley Technical Specifications,10 CFR 20, and 10 CFR 50, Appendix I. The ODCM provides a description of the physical configuration of the plant effluent release points as well as the calculation procedures for determining the effluent monitor setpoints, offsite doses and offsite dose rates, and describes the radiological environmental monitoring program. The ODCM is being revised to indicate a change in the milk sample location from one dairy to another. Technical specifications require any changes to the ODCM to be documented and reviewed.
This safety evaluation is applicable to Rt. vision 14 of the Farley ODCM. Revision 14 changes are included in Attachment 1.
References:
- 1. Joseph M. Farley Unit I and Unit 2 Technical Specifications
- 2. Joseph M. Farley Nuclear Plant Units 1 and 2 ODCM Evaluation The proposed changes to the ODCM simply relocate the milk sample location. Plant design and operation is unaffected by this change. Therefore, the level of radiological control will not be reduced by the proposed changes to the ODCM since compliance with applicable regulatory requirements governing radioactive effluents and radiological environmental monitoring ,
including 10 CFR 20.1302, 40 CFR 190,10 CFR 50.36a, and Appendix I to 10 CFR 50 will continue to be maintained.
Conclusion The requirements of 10 CFR 50.59 have been reviewed relative to the proposed changes to the ODCM and the following determination has been made:
- 1. The changes to the ODCM do not increase the probability of occurrence of an accident previously evaluated in the FSAR because they are administrative in nature and alter only the location of the environmental milk sample from one dairy to another.
Safety Evaluation Sheet 5 of 5
- 2. The changes to the ODCM do not increase the consequences of an accident previously evaluated in the FSAR because they do not alter any of the conditions or assumptions in the FSAR accident analyses. Therefore, since the accident analyses remain bounding, the radiolegical consequences previously evaluated are not adversely affected by the ODCM changes.
- 3. The changes to the ODCM do not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the FSAR because they do not affect the design or operation of any radiological emuent system equipment. Additionally, there is no adverse impact on the design or operation of any plant system or component important to safety as a result of these ODCM changes.
- 4. The changes to the ODCM do not increase the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR because they do not affect the design or operation of any plant system or component and because they do not adversely impact the radiological consequences presented in the FSAR accident analyses.
- 5. The changes to the ODCM do not create the possibility of an accident of a different type than any previously evaluated in the FSAR because they do not involve any change to the configuration or method of operation of any plant system component important to safety.
Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting single failure been identified. There will be no change in types or increase in the amounts of any emuents released offsite as a result of the ODCM changes.
- 6. The changes to the ODCM do not create the possibility of a malfunction of equipment imponant to safety of a different type than any previously evaluated in the FSAR because as stated previously, plant system or component performance will not be adversely affected since the ODCM changes only involve changes in milk sample location. No new accident initiators or single failures have been identified as a result of the ODCM changes.
- 7. The changes to the ODCM do not reduce the margin of safety as defined in the basis for any technical specification because the level of radioactive emuent control required by 10 CFR 20.1302,40 CFR 190,10 CFR 50.36a, and Appendix I to 10 CFR 50 is not affected and the changes do not adversely impact the accuracy or reliability of emuent, dose, or setpoint calculations.
Based on the preceding evaluation it can be concluded that the Revision 14 changes to the ODCM regarding the offsite milk sample location do not involve an unreviewed safety question as defined by 10 CFR 50.59.
_. . . - . . - . - . - . . - ~ . - - _ _ _ _
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FNP-0-M-011 January 26, 1994 Revision 14 l l
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I SOUTHERN NUCLEAR OPERATING COMPANY l JOSEPH M. FARLEY NUCLEAR PLANT l FNP-0-M-011 !
S A
F E
T i Y !
OFFSITE DOSE CALCULATION MANUAL j R ;
E L
A i T ;
E D
Approved: f FTuclear Plant - General Manager
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j Date Issued: M/
List of Effective Paces Page Rev. i i to 4-13,4-15 to 4-16,4-18 to 10-8 13 j 4-14,4-17 t; 34 r_
UNCONTROLLED COPY j CAUTION: ni.centanetmat*d i Current. Do not use in a Safety Relatedfetivity. ,
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FNP-0-M-011 Table 4-4 (contd). Radiological Environmental Monitoring Locations )
)
l Exposure Pathwa 3,,py,
,d 0r Sampling Locations
- Identifi-Sample cation
- 4. INGESTION Milk Indicator Station:
None (There are no milk animals within 5 miles per the current land use survey)
Control Station:
Bruce Ivey Dairy MB-1212 Webb, AL (W-12 miles)
Fish Indicator Station:
Smith Bend (River Mile - 41)
Game Fish FGI Bottom Feeding Fish FBI Control Station:
Andrews Lock & Dam Reservoir (River Mile - 47)
Game Fish FGB Bottom Feeding Fish FEB Forage or Indicator Stations:
Leafy South Southeast Perimeter (SSE-1.0 miles) FI-0701 Vegetation FI-1606 North South Perimeter Perimeter (N-0.8 (S-1.0 miles)8 miles) FI-0801 Northeast Perimeter (NE-1.0 miles)8 FI-0201 Control Station:
Dothan, AL (W-18 miles) FB-1218 Distance and direction as measured from the centerpoint between Unit I and Unit 2 plant vent stacks.
- 1. Not required by Section 4.1.1. Used as a spare station.
- 2. Not required by Section 4.1.1. Use for comparison purposes with State of GA EPD.
- 3. Alternate forage plots.
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