|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ . | | {{#Wiki_filter:}} |
| ENCLOSURE 1 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD OF JANUARY 1 TO DECEMBER 31, 1993 (S52 940407 305) 1 9405040233 94042s PDR ADOCK 05000327 R PDR
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1993
| |
| : 1. REGULATORY LIMITS A. Gaseous Effluents
| |
| : 1. Dose rates due to radioactivity released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
| |
| : a. Noble gases:- Less than or equal to 500 mrem / year to the total body.
| |
| - Less than or equal to 3000 mrem / year to the skin.
| |
| : b. Iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
| |
| - Less than or equal to 1500 mrem / year to any organ.
| |
| : 2. Air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
| |
| \
| |
| : a. Less than or equal 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any calendar quarter.
| |
| : b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.
| |
| : 3. Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the followings
| |
| : a. Less than or equal to 7.5 mrem to any organ during any calendar quarter.
| |
| : b. Less than or equal to 15 mrem to any organ during any calendar year.
| |
| B. Liquid Effluents l
| |
| : 1. The concentration of radioactivity released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulations, Part 20 l (Standards for Protection Against Radiation), Appendix B, Table !
| |
| II, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 microcuries/ milliliter (uci/ml) total activity.
| |
| PLO20201/5471/2
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1993
| |
| : 2. The dose or dose commitment to a member of the public from radioactivity in liquid effluents released to unrestricted areas shall be limited to
| |
| : a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.
| |
| : b. Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ during any calendar year.
| |
| : 2. MAXIMUM PERMISSIBLE CONCENTRATION A. Liquids al. The maximum permissible concentrations (MPC) for liquids are those listed in 10 CFR 20, Appendix B, Table II, Column 2, with the most restr'ctive MPC being used in all cases. For dissolved and entrained gases the MPC of 2.0E-04 uC1/ml is applied. This MPC is based on the Xe-135 MPC in air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP),
| |
| Publication 2.
| |
| B. Gaseous
| |
| *l. The maximum permissible dose rates for gaseous releases are defined in plant Offsite Dose Calculation Manual (ODCM).
| |
| : a. Noble gas dose rate at the site boundary:
| |
| - Less than or equal to 500 mrem / year to the total body,
| |
| - Less than or equal to 3000 mrem / year to skin.
| |
| : b. Iodine-131, iodine-133, tritium, and particulates with half-lives greater than eight days dose rate at the site boundary:
| |
| - Less than or equal to 1500 mrem / year to any organ.
| |
| : 3. AVERAGE ENERGY Sequoyah's ODCM limits the dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin. Therefore, the average beta and gamma energies it) for gaseous effluents as described in Regulatory Guide 1.21, " Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and l Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable.
| |
| *These values are used as applicable limits for liquid and gaseous effluents.
| |
| | |
| l EFFLUENT AND WASTE DISPOSAL ANEUAL REPORT SUPPLEMENTAL INFORMATIOM 1993
| |
| : 4. heasurements and Approximations of Total Radioactivity NOTE: Every effort is made to ensure that effluent releases from Sequoyah are conducted such that all Offsite Dose Calculation Panual (ODCM) Lower Limit of Detection (LLD) values are met.
| |
| Whenever an analysis does not identify a radioisotope, a "O.00E-01 Ci" is recorded for the release. This does not necessarily mean that no activity was released for that particular radionuclide, but that the concentration was below the ODCM and analysis LLD.
| |
| Refer to Tables A and B for estimates of these typical LLD valuee,
| |
| : a. Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded. Additional grab samples from the shield building, auxiliary building, service building, and condenser vacuum exhausts are taken and analyzed at least monthly to determine the quantity of noble gas activity released for the month based on the average vent flowrates recorded for the sample period. Also, noble gas samples are collected and evaluated for the shield and auxiliary buildings following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour (sampling only required if dose equivalent I-131 concentration in the primary coolant or the noble gas activity monitor shows that the containment activity has increased more than a factor of 3).
| |
| The quantity of noble gases released through the shield and auxiliary building exhausts due to purging or venting of containment and releases of waste gas decay tanks are also determined.
| |
| The total noble gas activity released for the month is then determined by summing all of the activity released from each vent for all sampling periods,
| |
| : b. Iodines and Particulates Iodine and particulate activity is continuously sampled. Charcoal and particulate samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity released from the plant based on the average vent flowrates recorded for sampling period.
| |
| Also, particulate and charcoal samples are taken from the auxiliary and shield building exhausts once per 24 hours for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour. The quantity of iodine and particulate released from each vent during each sampling period is then determined us.'ng the average vent flowrates recorded for the sampling period and activity concentration.
| |
| The total particulate and iodine activity released for the month is then determined by summing all of the activity released from the shield and auxi)iary building exhausts for all sampling periods.
| |
| | |
| l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATIosi 1993
| |
| : 4. Measurements and Approximation of Total Radioactivity (continued)
| |
| : c. Liquid Effluents i
| |
| Batch (Radwaste and during periods of primary to secondary leakage, condensate regenerants to cooling tower blowdown)
| |
| Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release. The total activity of a released batch is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during a month is then determined by summing the activity content of each batch discharged j during the month.
| |
| Continuous Releases and Periodic Continuous Releases (Condensate regenerants, turbine building sump and steam generator blowdown) i Total gamma isotopic activity concentration is determined daily on a composite sample from the condensate system and turbine building sump and weekly for steam generator blowdown. The total activity of the continuous release is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during the month is then determined by summing the activity content of each daily and weekly composite for the month.
| |
| : 5. Batch Value Units let _2nd Half Half
| |
| : a. Liquid (Radwaste only) l
| |
| : 1. Number of rele<ses 86 106 Each
| |
| : 2. Total time period of (;eleases 18,269 14,984 Minutes
| |
| : 3. Maximum time period of release 316 184 Minutes
| |
| : 4. Average time period of releases 212 141 Minutes l 5. Minimum time period for release 98 87 Minutes
| |
| [ 6. Average dilution stream flow during 40,051 26,515 CFS release periods j
| |
| cubic feet /second (CFS)
| |
| : b. Gaseous (Batches only)
| |
| : 1. Number of releitses 164 83 Each
| |
| : 2. Total time period of releases 31,525 8,156 Minutes
| |
| : 3. Maximum time period for release 9,680 1,332 Minutes
| |
| : 4. Average time period for releases 192 98 Minutes
| |
| : 5. Minimum time period for release 1 29 Minutes l
| |
| l l
| |
| l
| |
| | |
| EFFLUENT AND WASTE DISPOSAL Alf . AL REPORT SUPPLEMENTAL INFORMATION 1993
| |
| : 6. Abnormal Releases __ Value Units let 2nd Half Half
| |
| : a. Liquid Number of Releases 0 0 Total Activity Released 0.00E-01 0.00E-01 Ci
| |
| : b. Gaseous Number of Releases O O Total Activity Released 0.00E-01 0.00E-01 Ci l
| |
| l l
| |
| l l
| |
| 1
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES let 2nd 3rd 4th A. Fission and Activation Unit Otr Otr Otr Otr % Error Products
| |
| : 1. Total Released Curies 7.84E-02 5.72E-01 4.64E-01 4.06E-01 11.8E+01
| |
| : 2. Average Diluted Conc.
| |
| During Peric 1 of All Identified isotopes uCi/ml 1.14E-07 1.60E"06 1.27E-06 8.38E-07
| |
| : 3. Percent of Applicable Limit (IMPC<1) % 8.93E-01 3.66E400 3.54E+00 1.43E+00 NOTE: Percent of applicable limit is based on idcntified isotope concentration after dilution, related to their appropriate MPC concentration and sum of all the isotope fractions compared to 1.0.
| |
| B. Tritium
| |
| : 1. Total Released Curies 3.37E+02 7.58E+01 6.21E+01 8.46E+01 11.8E+01
| |
| : 2. Average Diluted uci/ml 4.92E-04 2.12E-04 1.70E-04 1.75E-04 Conc. During Period
| |
| : 3. Percent of Applicable Limit (3.0E-03 uci/ml) % 1.64E+01 7.06E+00 5.66E+00 5.82E+00 C. Dissolved and Entrained Gases
| |
| : 1. Total Released Curies 7.93E-02 2.15E-04 0.00E-01 1.20E-02 13.9E+01
| |
| : 2. Average Diluted uCi/ml 1.16E-07 6.00E-10 0.00E-01 2.48E-08 Conc. During Period
| |
| : 3. Percent of Applicable Limit (2.0E-04 uCi/ml) % 5.79E-02 3.00E-04 0.00E-01 1.24E-02 D. Gross Alpha Radioactivity
| |
| : 1. Total Released Curies 0.00E-01 0.00E-01 4.13E-05 0.00E-01 12.0E+01 E. Volume of Waste Released Liters 2.89E+06 1.95E+06 2.41E+06 3.59E+06 14.OE+00 F. Volume of Dilution Liters 6.82E+08 3.55E+08 3.63E+08 4.81E+08 11.1E+01 Water for Period
| |
| - . . _ . , - - .a -. -w..,. - a.~. . . . - - . ~ . _ ----.-.-n.. . - ~ , - . - - ~ . . . . - - . - - -
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G. Nuclide Summary (Note Refer to Table A for ODCM nuclides reported as 0.00E-01)
| |
| Required by ODCM/Others Fission and Activation Products Continuous Mode- Ratch Mode Nuclide Unit Ouarter Quarter Quarter Ouarter let 2nd let 2nd
| |
| : 1. Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 2.40E-04
| |
| : 2. Strontium-90 Ci 0.00E_-01 0.00E-01 0.00E-01 1.44E-04
| |
| : 3. Iron-55 Ci 0.00E-01 0.00E-Q1 1.51E-02 2.87E-02
| |
| : 4. Manganese-54 Ci 0.00E-01 0.00E-01 2.98E-04 5.34E-03
| |
| : 5. Cobalt-58 Ci 0.00E-01 1.40E-06 8.62E-03 2.60E-01
| |
| : 6. Iron-59 Ci 0.00E-01 0.00E-01 5.91E-04 7.06E-04
| |
| : 7. Cobalt-60 Ci 3.27E-06 0.00E-01 5.75E-03 3.27E-02
| |
| : 8. Zinc-65 Ci 0.00E-01 0.00E-01 5.63E-06 3.74E-02
| |
| : 9. Molybdenum-99 Ci 0.00E-01 0.00E 1.74E-05 0.00E-01
| |
| : 10. Iodine-131 Ci 0.00E-01 0.00E-01 8.45E-04 3.26E-05
| |
| : 11. Cesium-134 Ci 3.75E-06 0.00E-01 1.52E-02 3.27E-02
| |
| : 12. Cesium-137 Ci 2.40E-05 0.00E-01 2.37E-02 5.27E-02
| |
| : 13. Cerium-141 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ;
| |
| : 14. Cerium-144 Ci 0.00E-01 0.00E-01 2.79E-05 3.31E-04 l
| |
| l
| |
| : 15. Antimony-125 Ci 0.00E-01 1.64E-06 6.70E-03 9.93E-02
| |
| : 16. Cobalt-57 Ci 0.00E-01 0.00E-01 4.30E-05 1.06E-03 I
| |
| l 17. Chromium-51 Ci 0.00E-01 0.00E-01 9.09E-04 5.72E-03
| |
| : 18. Niobium-95 C1 0.00E-01 0.00E-01 6.63E-05 J.07E-03 I
| |
| l - - , , , - . - . - . . -.
| |
| | |
| l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 j LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE j (CONTINUED) l Continuous Mode Batch Mode Nuclide Unit Ouarter Ouarter Quarter Ouarter let 2nd let 2nd
| |
| : 19. Iodine-133 Ci 0.00E-01 0.00E-01 1.45E-05 0.00E-01
| |
| : 20. Zirconium-95 Ci O.00E-01 0.00E-01 0.00E-01 4.90E-04
| |
| : 21. Technetium-99m Ci 0.00E-01 0.00E-01 1.74E-05 0.00E-01
| |
| : 22. Ruthenium-103 Ci 0.00E-01 0.00E-01 0.00E-01 1.49E-04
| |
| : 23. Tellurium-132 Ci 0.00E-01 0.00E-01 1.75E-05 3.36E-05
| |
| : 24. Antimony-124 Ci 0.00E-01 0.00E-01 1.96E-04 9.89E-03
| |
| : 25. Lanthanum-140 Ci 0.00E-01 0.00E-01 9.56E-05 0.00E-01
| |
| : 26. Cesium-136 Ci 0.00E-01 0.00E-01 1.16E-04 0.00E-01
| |
| : 27. Sodium-24 Ci 0.00E-01 0.00E-01 1.13E-05 1.57E-04
| |
| : 28. Cesium-138 Ci 0.00E-01 0.00E-01 0.00E-01 7.74E-05
| |
| : 29. Niobium-97 Ci 0.00E-01 0.00E-01 0.00E-01 7.21E-05
| |
| : 30. Strontium-91 Ci 0.00E-01' O.00E-01 2.34E-05 0.00E-01
| |
| : 31. Nickel-65 Ci 0.00E-01 0.00E-01 0.00E-01 1.51E-05
| |
| : 32. Silver-110m Ci 0.00E-01 0.00E-01 0.00E-01 5.22E-04
| |
| : 33. Tellurium-129m Ci 0.00E-01 0.00E-01 0.00E-01 2.03E-03
| |
| : 34. YttridM-91m Ci 0.00E-01 0.00E-01 2.07E-05 0.00E-01
| |
| : 35. Zinc-69m Ci 0.00E-01 0.00E-01 0.00E-01 3.94E-06 Total for Period Ci 3.10E-05 3.04E-06 7.84E-02 5.72E-01 l
| |
| 1 1
| |
| l l
| |
| | |
| EFFLUENT AND WASTE D8SPOSAL ANWUAL REPORT 1993 LYQUID EFFLUiNTS - TOTAL PLANT DISCHARGE (CONTINUED) t G. Nuclide Summarv (NOTE: Refer to Table A for ODCM nuclides reported as 0.00E-01)
| |
| Required by ODCM/Others Dissolved and Entrained Noble Gases Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Ouarter Ouarter let 2nd let 2nd .
| |
| : 1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 3. Xenon-133 Ci 0.00E-01 0.00E-01 7.52E-02 2.14E-04
| |
| -4. Xenon-133m Ci 0.00E-01 0.00E-01 1.16E-03 0.00E-01
| |
| : 5. Xenon-135 Ci 0.00E-01 0.00E-01 2.87E-03 0.00E-01
| |
| : 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 7. Krypton-85m Ci O.00E-01 _O.00E-01 0.00E-01 0.00E-01
| |
| : 8. Xenon-131m Ci 0.00E-01 0.00E-01 5.62E-05 0.00E-01
| |
| : 9. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 10. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 11. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 7.93E-02 2.14E-04 .
| |
| 1 f%
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUEE4TS - TOTAL PLANT DISCHARGE l
| |
| G. Nuclide Summary (Notes Refer to Table A for ODCM nuclides reported as 0.00E-01)
| |
| Required by ODCM/Others Fission and Activation Products Continuous Mode Batch Mode Nuclide Unit Quarter Ouarter Quarter Ouarter 1 3rd 4th 3rd 4th !
| |
| 4
| |
| : 1. Strontium-89 Ci O.00E-01 0.00E-01 1.13E-04 0.00E-01
| |
| : 2. Strontium-90 Ci 0.00E-01 0.00E-01 1.42E-04 0.00E-01
| |
| : 3. Iron-55 Ci 0.00E-01 0.00E-01 5.00E-02 7.35E-02
| |
| : 4. Manganese-54 Ci 0.00E-01 0.00E-01 3.05E-03 5.10E-03
| |
| : 5. Cobalt-58 Ci 0.00E-01 0.00E-01 1.10E-01 9 6E-02
| |
| : 6. Iron-59 Ci 0.00E-01 0.00E-01 1.28E-04 6.13E-04 i l
| |
| : 7. Cobalt-60 Ci 0.00E-01 0.00E-01 5.35E-02 8.37E-02
| |
| : 8. Zinc-65 Ci 0.00E-01 0.00E-01 2.16E-02 1.05E-03
| |
| : 9. Molybdenum-99 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l
| |
| : 10. Iodine-131 Ci 0.00E-01 0.00E-01 0.00E-01 8.99E-05 l
| |
| : 11. Cesium-134 Ci 0.00E-01 0.00E-01 3.39E-02 4.25E-03
| |
| : 12. Cesium-137 Ci O.00E-01 0.00E-01 5.98E-02 7.88E-03
| |
| : 13. Cerium-141 Ci O.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 14. Cerium-144 Ci 0.00E-01 0.00E-01 7.98E-04 4.86E-04
| |
| : 15. Antimony-125 Ci 0.00E-01 0.00E-01 9.64E-02 1.12E-01 j i
| |
| : 16. Cobalt-57 Ci 0.00E-01 0.00E-01 8.76E-04 1.75E-03
| |
| : 17. Chromium-51 Ci 0.00E-01 0.00E-01 4.64E-03 4.53E-03
| |
| : 18. Niobium-95 Ci O.00E-01 0.00E-01 2.40E-03 2.11E-03
| |
| | |
| I l
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED) l Continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Quarter Quarter
| |
| , 3rd 4th 3rd 4th
| |
| ! )
| |
| : 19. Iodine-133 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 '
| |
| : 20. Zirconium-95 Ci O.00E-01 0.00E-01 1.10E-03 5.14E-04
| |
| : 21. Technetium-99m Ci 0.00E-01 0.OOE-01 0.00E-01 0.00E-01 i
| |
| l
| |
| : 22. Ruthenium-103 Ci 0.00E-01 0.00E-01 6.31E-05 0.00E-01
| |
| : 23. Tellurium-132 Ci 0.00E-01 O t 00E-01 5.75E-05 3.76E-05
| |
| : 24. Antimony-124 Ci 0.00E-01 0.00E-01 2.28E-02 4.12E-03
| |
| : 25. Lanthanum-140 Ci 0.00E-01 0.00E-01 0.00E-01 3.65E-05 l
| |
| : 26. Barium-140 Ci 0.00E-01 0.00E-01 4.38E-05 5.22E-05
| |
| : 27. Sodium-24 Ci 0.00E-01 0.00E-01 6.92E-05 8.21E-06
| |
| : 28. Cesium-138 Ci 0.00E-01 0.00E-01 2.32E-04 1.33E-05 l 29. Strontium-92 Ci 0.00E-01 0.00E-01 3.97E-04 1.42E-04
| |
| : 30. Niobium-97 C1 0.00E-01 0.00E-01 6.97E-04 4.88E-04
| |
| : 31. Yttrium-91 Ci 0.00E-01 0.00E-01 0.00E-01 7.58E-03
| |
| : 32. Silver-110m C1 0.00E-01 0.00E-01 9.09E-04 1.80E-03 Total for Period Ci 0.00E-01 0.00E-01 4.64E-01 4.06E-01 l
| |
| l
| |
| )
| |
| 1 i
| |
| l
| |
| ; I r
| |
| I i
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 LIQUID EFFLUENTS - TOTAL PLAliT DISCHARGE (CONTINUED)
| |
| G. Nuclide Summarv (NOTE: Refer to Table A for ODCM nuclides reported as i 0.00E-01) l l
| |
| Required by ODCM/Others I
| |
| Dissolved and Entrained Noble Gases Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Ouarter Ouarter ,
| |
| 3rd 4th 3rd 4th '
| |
| : 1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 1.45E-05 l
| |
| : 3. Xenon-133 Ci 0.00E-01 0.00E-01 0.00E-01 8.26E-03 l
| |
| : 4. Xenon-133m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l l
| |
| : 5. Xenon-135 Ci 0.00E-01 0.00E-01 0.00E-01 6.89E-05
| |
| : 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 7. Krypton-85m Ci 0.00E-01 0.00E-Q1 0.00E-01 0.00E-01 I
| |
| : 8. Xenon-131m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 j
| |
| : 9. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 10. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 3.70E-03
| |
| : 11. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.OOE-01 0.00E-01 1.20E-02 I
| |
| I i
| |
| l l
| |
| | |
| i I
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 TABLE A LIQUID " TYPICAL LLD" EVALUATION II) i I
| |
| 6tI2) ,
| |
| 1 Muclide ODCM LLQ__ 15 min 30 min 1 hr 2 hr 1
| |
| Manganese-54 5.0E-07 9.12E-09 9.12E-09 9.12E-09 9.12E-09 l
| |
| Cobalt-58 5.0E-07 8.21E-09 8.21E-09 8.21E-09 8.21E-09 Iron-59 5.0E-07 1.62E-08 1.62E-08 1.62E-08 1.62E-08 I l
| |
| i Cobalt-60 5.0E-07 1.08E-08 1.08E-08 1.08E-08 1.08E-08 Einc-65 5.0E-07 2.14E-Q8 2.14E-08 2.14E-08 2.14E-08 !
| |
| l Molybdenum-99 5.0E-07 5.24E-08 5.25E-08 5.28E-08 5.34E-08 Cesium-134 5.0E-07 9.82E-09 9.82E-09 9.82E-09 9.82E-09 Cesium-137 5.0E-07 9.31E-09 9.31E-09 9.31E-09 9.31E-09 Cerium-141 5.0E-07 1.06E-08 1.06E-08 1.07E-08 1.07E-08 Cerium-144 5.0E-06 4.03E-08 4.03E-08 4.03E-08 4.03E-08 Iodine-131 1.0E-06 7.28E-09 7.28E-09 7.30E-09 7.32E-09 l
| |
| Krypton-87 1.0E-05 1.62E-08 1.85E-08 2.43E-08 4.20E-08 l 1
| |
| Krypton-88 1.0E-05 2.13E-08 2.27E-08 2.56E-08 3.27E-08 1
| |
| Xenon-133 1.0E-05 2.03E-08 azQ?E-08 2.04E-08 2.05E-08 l l Xenon-133m 1.0E-05 5.05E-08 5.07E-08 5.10E-08 5.17E-08 Xenon-135 1.0E-05 5.60E-09 5.70E-09 5.93E-09 6.40E-09 l Xenon-138 1.0E-05 2.82E-08 5.87E-08 2_. 5 5 E-0 7 4. 7 9 g,_QQ l
| |
| ! I
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 TABLE A LIQUID " TYPICAL LLD" EVALUATION III (Continued)
| |
| Nuclide. ODCM LLD Tvolcal LLD l
| |
| Tritium 1.0E-05 1.OE-06 Gross Alpha 1.0E-07 1 0E-QB Strontium-89 5.0E-08 2.0E-08 Strontium-90 5.0E-08 1.OE-08 Iron-55 1.0E-06 3.0E-07_
| |
| NOTES: (1) LLD values are in uCi/ml. Sample analyses are performed to ensure that ODCM LLD limits are met. These are typical LLD values.
| |
| l l (2) at is the time between sample collection and counting time.
| |
| 1 l
| |
| l l
| |
| l
| |
| | |
| l l
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 .
| |
| GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) a let 2nd 3rd 4th 1 Summation of All Releases Unit Otr Otr .. Qt r _. Otr % Error 1
| |
| A. Noble Gases j 1
| |
| : 1. Total Released Ci 5.60E+01 2.04E+01 0.00E-01 7.03E-01 11.1E+01
| |
| : 2. Average Release Rate of Period uCi/sec 7.20E+00 2.60E+00 0.00E+01 8.84E-02
| |
| : 3. Percent of Applicable Limit % 4.55E-03 7.82E-04 0.00E-01 7.96E-07.
| |
| B. Iodines
| |
| : 1. Total Iodine-131 C1 1.93E-06 0.00-01. 0.00E-01 0.00E-01 11.3E+01 j
| |
| : 2. Average Release ;
| |
| Rate for Period uCi/sec 2.48E-07 0.00E-01 0.00E-01 ~ 0.00E-01
| |
| : 3. Percent of Applicable l Limit (1.60E-01 pci/sec) % 1.55E-04 ~ 0.00E-01_ 0.00E-01 0.00E.01 C. Earticulates
| |
| : 1. Particulates with Ci 3.40E-07 0.00-01 1.19E-05 0.00E-01 11.6E+01 half-lives >8 days
| |
| : 2. Average Release Rate for Period uCi/sec 4.37E-08 0.00E-01 1.50E-06 0.00E-01 ,
| |
| : 3. Percent of Applicable l Limit % 1.10E-08 0.00E-01 2.89E-05 0.00E-01
| |
| : 4. Gross Alpha Radio- Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 12.1E+01 activity D. Iritium ,
| |
| : 1. Total Release Ci 2.14E+01 9.14E+00 7.12Er00 1.92E+00 11.5E+01
| |
| : 2. Average Release
| |
| ! Rate for Period uC1/sec 2.75E+00 1.16E+00 8.96E-01 2.41E-01 1
| |
| : 3. Percent of Applicable Limit (8.47E+04 pC1/sec) 3.25E-03 1.37E-03 1.06E-03 ~2.85E-04 )
| |
| 1 I
| |
| i l
| |
| l r
| |
| l :
| |
| i
| |
| | |
| - . _ . - - . . - . - . ~ . . . . - ._. - - - - - - - . - . .
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l- 1993 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)
| |
| Continuous Mode Batch Mode
| |
| ! Unit Ouarter Quarter Ouarter Quarter
| |
| { 1st 2nd let 2nd i F. Noble Gases l Required by ODCM/Others
| |
| : 1. Krypton-87. C1 2.94E-03 0.00E-01 0.00E-01 0.00E-01 l
| |
| : 2. Krypton-88 C1 4.57E-04 0.00E-Q1 2.41E-02 0.00E-01
| |
| ] 3. Xenon-133 C1 1.25E-01 0.00E-01 5.16E+01 2.03E+01 l' 4. Xenon-133m Ci 0.00E-01 0.00E-01 2.36E-01 0.00E-01 3
| |
| ( 5. Xenon-135 C1 2.33E-02 0.00E-01 1.93E+00 0.00E-01 i
| |
| - 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l
| |
| : 7. Krypton-85 Ci 0.00E-01 0.00E-01 8.18E-02 1.20E-01 i i
| |
| : 8. Argon-41 Ci 1.82E-02 0.00E-01 1.70E+00 0.00E-00 l l
| |
| : 9. Krypton-85m Ci 1.16E-03 0.00E-01 4.03E-02 0.00E-01
| |
| : 10. Xenon-131m Ci 0.00E-01 0.00E-01 1.54E-0.1 6.91E-03
| |
| : 11. Xenon-135m C1 1.66E-02 0.00E-01 0.00E-01 0.00E-01 Total for Period C1 1.88E-01 0.00E-01. 5.58E+01 2.04E+01 G. Idoines
| |
| : 1. Iodine-131 Ci 1.93E-06 0.00E-01
| |
| : 2. Iodine-133 Ci 13 15E-06 0.00E-01
| |
| : 3. Iodine-135 Ci 0.00E-01 0.00E-01 Total for Period Ci 3.08E-06 0.00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.
| |
| l l
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT A113 l GASEOUS EFFLUENTS-SUHMATION OF ALL RELEASES l (GROUND LEVEL RELEASES) )
| |
| I l
| |
| H. Particulates Required by ODCM/Others Continuous Mode Nuclide Unit Ouarter Quarter let 2nd 1
| |
| : 1. Strontium-89 Ci 0.00E-01 0.00E-01 l l
| |
| : 2. Strontium-90 Ci 0.00E-01 0.00E-01 l
| |
| : 3. Iron-59 Ci 0.00E-01 0.00E-01 1
| |
| : 4. Cobalt-60 Ci 2.79E-07 0.00E-01 l
| |
| S. Zinc-65 C1 0.00E-01 0.00E-01 l
| |
| : 6. Manganese-54 Ci 5.98E-08 0.00E-01 l
| |
| : 7. Cobalt-58 Ci O.00E-01 0.00E-01 l l
| |
| : 8. Molybdenum-99 Ci O.00E-01 0.00E-01 ,
| |
| l
| |
| : 9. Cesium-134 Ci O.00E-01 0.00E-01 1
| |
| : 10. Cesium-137 Ci 0.00E-01 0.00E-01 !
| |
| l
| |
| : 11. Cerium-141 Ci 0.00E-01 0.00E-01
| |
| : 12. Cerium-144 Ci 0.00E-01 0.00E-01 Others (Specify) l
| |
| : 13. Technetium-99m Ci 0.00E-01 0.00E-01 l 14. Sodium-24 Ci 0.00E-01 0.00E-01 Total for Period C1 3.39E-07 0.00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01. i l
| |
| t
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1.9.2.3 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)
| |
| Continuous Mode Batch Mode Unit Ouarter Ouarter Ouarter Quarter 3rd 4th 3rd 4th F. Noble Gases Required by ODCM/Others
| |
| : 1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-00
| |
| : 2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 3. Xenon-133 Ci 0.00E-01 0.00E-01 0.00E-01 6.10E-01
| |
| : 4. Xenon-133m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 5. Xenon-135 Ci O.00E-01 0.00E-01 0.00E-01 Rzip'-02
| |
| : 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 7. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 8. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 6.63E-02
| |
| : 9. Krypton-85m Ci 0.00E-01 0.00E-01 0.00E-01 8.35E-04
| |
| : 10. Xenon-131m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
| |
| : 11. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 0.00E-01 7.02E-01 G. Idoines
| |
| : 1. Iodine-131 Ci 0.00E-01 0.00E-01
| |
| : 2. Iodine-133 Ci 0.00E-01 0.00E-01
| |
| : 3. Iodine-135 Ci 0.00E-01 0.00E-01 1
| |
| Total for Period Ci 0.00E-01 0.00E-01 1 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.
| |
| { EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i
| |
| I 1993 GASEOUS EFFLUENTS-SUMMATZON OF ALL RELEASES l (GROUND LEVEL RELEASES) l l
| |
| l H. Particulates )
| |
| I Required by ODCM/Others )
| |
| l Continuous Mode Nuclide Unit Ouarter Quarter 3rd 4th
| |
| : 1. Strontium-89 Ci 0.00E-01 0.00E-01
| |
| : 2. Strontium-90 Ci 0.00E-01 0.00E-01
| |
| : 3. Iron-59 Ci 0.00E-01 0.00E-01
| |
| : 4. Cobalt-60 Ci 7.48E-06 0.00E-01 )
| |
| l I
| |
| : 5. Zinc-65 Ci O.00E-01 0.00E-01
| |
| ( 6. Manganese-54 Ci 0.00E-01 0.00E-01 ,
| |
| ! l
| |
| : 7. Cobalt-58 Ci 42 30E-06 0.00E-01 l 1
| |
| i'
| |
| : 8. Molybdenum-99 Ci 0.00E-01 0.00E-01 I
| |
| : 9. Cesium-134 Ci O.00E-01 0.00E-01
| |
| : 10. Cesium-137 Ci 0.00E-01 0.00E-01
| |
| : 11. Cerium-141 Ci 0.00E-01 0.00E-01
| |
| : 12. Cerium-144 Ci 0.00E-01 0.00E-01 Others (Specify)
| |
| : 13. Technetium-99m Ci 0.00E-01 0.00E-01
| |
| : 14. Sodium-24 Ci 0.00E-01 0.00E-01 Total for Period C1 1.18E-05 0.00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.
| |
| | |
| . _ _ . . . - _ _ . . - ~ _ _ _ _ - . _ . _ . . _ . - . . _ _ . _ _ _ _ __ _ _ _ _ _
| |
| EFFLUENT AND WASTE D8SPOSAL ANNUAL REPORT 1993
| |
| ' TABLE B GASEOUS " TYPICAL" LLD EVALUATION III Noble Gas At(2)
| |
| Nuclide ODCM LLD 1 hr 1.5 hr Krypton-87 1.0E-04 1.19E-06 2.69E-06 l Krypton-88 1.0E-04 1.22E-06 1.76E-06 Xenon-133 1.0E-04 5.51E-07 5.56E-07 Xenon-133m 1.0E-04 1.99E-06 2.02E-06 Xenon-135 1.0E-04 2.59E-07 2.90E-07 1 J
| |
| Xenon-138 1.0E-04 5.38E-05 8.55E-05 j l
| |
| 1 Particulate Samole 2.02 da 2.79 da 5.79 da Manganese-54 1.0E-10 1.83E-12. 7.65E-14 1.10E-14 1
| |
| Cobalt-58 1.0E-10 1.60E-12 4.79E-14 9.99E-15 Iron-59 1.0E-10 3.21E-12 1.36E-13 2.03E-14 Cobalt-60 1.0E-10 1.79E-12 7.46E-14 1.07E-14 l Zinc-65 1.0E-10 4.08E-12 1.71E-13 2 46E-14 I
| |
| Molybdenum-99 '1.0E-10 2.08E-12 1.05E-13 3.18E-14 I Cesium-134 1.0E-10 2.03E-12 8.45E-14 1.21E-14 Cesium-137 1.OE-10 .85E-12 7.71E-14 1.10E-14 Cerium-141 1.0E-10 2.32E-12 9.82E-14 1.50E-14 Cerium-144 1.0E-10 1.03E-12 4.28E-13 6.16E-14 Iodine-131 1.0E-10 1.85E-12 8.22E-14 1.52E-14 Charcoal Sample 2.0 da 2.5 da 5.5 da Iodine-131 1.0E-11 2.53E-12 1.10E-13 2.00E-14 l
| |
| l r --. - - - - , -- ,. ,m ..- - .,m,, .~._._,.,...m ,,-...,~,.-,,.r._,s_..-.- . , ,, ,, . . . . . , ...,m,,,,
| |
| | |
| l l
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l
| |
| 1993 TABLE B GASEOUS " TYPICAL" LLD EVALUATION (1)
| |
| (continued)
| |
| Nuclide ODCM LLD Tvolcal LLD Tritium 1.0E-06 1.0E-11 Gross Alpha 1.0E-11 1.5E-14 Strontium-89 1.0E-11 1.0E-14 Strontium-90 1.0E-11 1.0E-15 NOTCS: (1) LLD values are in pC1/cc.
| |
| (2) 4t for noble gases is the time from sampling to analysis.
| |
| l At for charcoal and particulate samples is the midpoint of I sampling to analysis.
| |
| l l
| |
| t l
| |
| 1 i
| |
| 1 l
| |
| l l l
| |
| l
| |
| . ~ . . - . - - - . . - - . _ . . - . -- - . -
| |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993-SOLID WASTE (RADIOACTIVE SHIPMENTS)
| |
| A. Solid Waste Shipped Offsite for Burial or Disposal (not Irradiated Fuel) 12 Month Est. Tot.
| |
| : 1. ' Type of Waste Unit Period Error %
| |
| : a. Spent resins, filter sludges, m3 1.05E+01 11.00E-1 evaporator bottoms, etc. Ci 1.70E+01 11.50E+1
| |
| : b. Dry Active Waste, compressible Waste m3 3.80E+01 11.00E-1 Contaminated Equipment,'etc. Ci 6.68E+00 11.50E+1 3 None
| |
| : c. Irradiated Components, m N/A Control Rods, etc. Ci None N/A
| |
| : d. Other: Mechanical Filters m3 5.86E+00 11.00E-1 Floor Drain Media Ci- 6.26E+01 11.50E+1
| |
| : 2. Estimate of Maior Nuclide Composition (by type of waste)
| |
| : a. Spent resins, filter sludges, evaporator bottoms, etc.
| |
| (nuclides determined by measurement)
| |
| Curies Percent
| |
| : 1. Manganese-54 3.04E-01 1.79E+00
| |
| : 2. Iron-55 3.39E+00 2.00E+01
| |
| : 3. Cobalt-58 7.01E-01 4.12E+00
| |
| : 4. Cobalt-60 6.36E+00 3.74E+01
| |
| : 5. Nickel-63 4.37E+00 2.57E+01
| |
| : 6. Antimony-125 2.32E-01 1.36E+00
| |
| : 7. Cesium-134 4.79E-01 2.82E+00 8 Cesium-137 8.69E-01 5.11E+00 l l
| |
| l
| |
| : b. Dry active waste, compressible waste, contaminated equipment, etc.
| |
| (nuclides determined by estimate)
| |
| : 1. Chromium-51 6.49E-01 9.71E+00
| |
| : 2. Manganese-54 1.28E-01 1.91E+00
| |
| : 3. Iron-55 1.51E+00 2.25E+01
| |
| : 4. Cobalt-58 2.05E+00 3.06E+01
| |
| : 5. Cobalt-60 8.77E-01 1.31E+01
| |
| : 6. Nickel-63 2.48E-01 3.71E+00
| |
| : 7. Beryllium-7 1.38E-01 2.07E+00
| |
| : 8. Niobium-95 3.11E-01 4.66E+00
| |
| : 9. Zirconium-95 1.89E-01 2.83E+00
| |
| : 10. Cesium-134 1.91E-01 2.86E+00
| |
| : 11. Cesium-137 2.50E-01 3.74E+00
| |
| : 12. Barium / Lanthanum-140 9.73E-02 1.46E+00 l
| |
| : c. Irradiated Components N/A N/A i
| |
| . , -m .- _ _ _ - . _ _ _ - - - - - . . _ - - . _ _ . - . - -
| |
| | |
| EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1993 SOLID WASTE (RADIOACTIVE SHIPMENTS)
| |
| : 2. Estimate of Maior Nuclide Composition (by tvoe of waste) Continued
| |
| : d. Other: Mechanical Filters, Floor Drain Media (nuclides determined by estimate)
| |
| Curies Percent
| |
| : 1. Manganese-54 2.81E+00 4.49E+00
| |
| : 2. Iron-55 3.67E+01 5.86E+01
| |
| : 3. Cobalt-58 6.10E+00 9.74E+00
| |
| : 4. Cobalt-60 7.67E+00 1.22E+01
| |
| : 5. Nickel-63 6.76E+00 1.08E+01
| |
| : 6. Chromium-51 6.43E-01 1.03E+00
| |
| : 3. Eolid Waste Disposition i
| |
| Number of Shipments Type Ouantity Mode of Transportation Destination
| |
| )
| |
| a) Spent resins, filter sludges, evaporator bottoms, etc.
| |
| 2 B-LSA Motor Freight Barnwell, SC ;
| |
| 1 A-LSA Motor Freight Barnwell, SC Number of Shipments Tvoe Ouantity Mode of Transportation Destination I b) Dry active waste, compressible waste, contaminated equipment, etc.
| |
| 2 63 A-LSA Motor Freight Barnwell, SC 4
| |
| Number of Shipments Tvoe Ouantity Mode of Transportation Destination c) Irradiated components, control rods, etc.
| |
| None ;
| |
| Number of Shipments Tvoe Ouantity Mode of Transoortation Destination l 4 d) Other: Mechanical Filters, Floor Drain Media 2 B-LSA Motor Freight Barnwell, SC
| |
| : 4. Irradiated Fuel Shioments (Disposition)
| |
| Number of Shipments Tvoe Ouantity Mode of Transportation Destination None N/A N/A N/A
| |
| : 5. Solidification of Waste Was solidification performed? NO If yes, solidification media: N/A 1
| |
| 4
| |
| | |
| 1 l
| |
| Effluent and Waste Disposal Annual Report 1993 Attachment 1.0 INOPERABLE INSTRUMENTATION l
| |
| Pursuant to ODCM Section 1.1.1, the following information is provided concerning radioactive effluent monitoring instrumentation which was inoperable for greater than 30 consecutive days during the period of January 1, 1993, through December 31, 1993.
| |
| Radiation Monitor System Date/ Time Date/ Time Total Number Monitored Out of Service Returned to Service Days j 0-RM-90-134/141 ERCW-Train B 1/8/93 1320 2/13/93 1425 37 5/16/93 0705 7/23/93 1500 38 O-RM-90-212 Turbina Bldg. 5/11/93 1433 6/15/93 1638 35 Sump i
| |
| O-RM-90-133/140 ERCW-Train A 5/18/93 1140 7/23/93 1500 37 )
| |
| 0-RM-90-225 condensate 11/11/93 1035 12/23/93 1510 41 l Demin Eff. j ERCW radiation monitors (0-RM-90-133/140, 134/141) were inoperable numerous times throughout the year. The primary downtime was related to the ability to maintain radiation monitor sample flow. Both ERCW train were in an outage which essentially placed the train out-of-service thus not having adequate volume to maintain radiation monitor sample flow. l l
| |
| ERCW-Train B radiation monitors were inoperable due to flow switches being i found out-of-calibration tolerance during the required quarterly evaluation. ,
| |
| The flow switches were unable to be calibrated within tolerance and were declared inoperable. A work request was prepared for both monitors to implement the use of a new and different flow switch. Since the required modifications in the flow switch required a design change the 30-day ODCM time frame was exceeded.
| |
| The turbine building sump (0-RM-90-212) was inoperable for greater than 30 days due to a shutdown board 1A-A outage followed by flow restriction problems.
| |
| Condensate demin radiation monitor was inoperable due to air inleakage from the mechanical seals of an associated discharge pump. Air in the sample prevented the monitor from receiving an adequate sample. Since the problem was not at the monitor itself, it took longer than normal to troubleshoot.
| |
| The pump seals have since been replaced.
| |
| | |
| l-Effluent and Waste Disposal Annual Report 1993 Attachment 2.0 Missed Surveillance l
| |
| ODCM Section 1.2.2.1 requires that if samples were not collected and analyzed according to a specified frequency then report with an explanation as to why j they were missed and actions taken to prevent reoccurrence.
| |
| ODCM SR 2.2.2.1.2 requires monitoring of the applicable units shield building cxhaust once per day for tritium during refueling when the refueling canal is flooded. Unit 1 had completed all refueling operations, the head had been put in place but not fully tensioned, and was in preparation for draindown. The l
| |
| table below identifies the partial July '93 sampling frequency for the shield building exhaust. Samples for 7/13 through 7/15 were not collected and analyzed due to a communication error between Operations and Chemistry )
| |
| personnel in verifying the status of the refueling canal. ;
| |
| H-3 conc. Shield Bldg. Flow Dose j DATE-Time uCi/cc CFM mrem /vr j 7/10-11:03 8.31E-08 9430 6.55E-03 7/11-00:05 8.01E-08 12109 8.11E-03 7/12-12:08 1.11E-07 10960 1.02E-02 l 7/1o-16:08 1.70E-07 5485 7.79E-03 7/17-15:57 1.54E-07 5725 7.37E-03 7/18-15:26 1.85E-07 5750 8.89E-03 j AVERAGE 1.31E-07 8.15E-03 l The average concentration of the sample period before and after the missed samples is 1.31E-07 uC1/cc with an average dose of 8.15E-03 mrem /yr.
| |
| The sample collected on 7/16-16:08 was used in covering the time frame in question. If the average concentration was used to evaluate the release period the dose rate would decrease due to the low flowrate. The instruction used by Chemistry was revised to more clearly identify the surveillance and i the applicability with regard to the refueling canal.
| |
| | |
| l i
| |
| l
| |
| ! ENCLOSURE 2 SEQUOYAll NUCLEAR PLANT RADIOLOGICAL IMPACT ASSESSMENT REPORT (S52 940407 305) l l
| |
| l l
| |
| l l
| |
| l l
| |
| I l
| |
| l l
| |
| l l
| |
| l l
| |
| i :
| |
| l 1 i
| |
| l 1
| |
| I l
| |
| i
| |
| . .. - -- I}}
| |
