ML20214U976
| ML20214U976 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/30/1986 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML20214U962 | List: |
| References | |
| NUDOCS 8612090475 | |
| Download: ML20214U976 (10) | |
Text
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EFFIDENT AND MASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Report Period: January 1 - June 30, 1986 Facility Ginna Station Licensee Rochester Gas & Electric
- 1. Regulatory Limits
- a. Fission and activation gases: 6.30 E+05 uCi/sec
- b. Iodines: 4.55 E-02 uCi/sec
- c. Particulates, half-lives > 8 days: 1.06 E+00 uCi/sec
- d. Liquid effluents: Identified MPC
- 2. Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations.
- a. Fission and activation gases: 10 CFR PART 20
- b. Iodines: 10 CFR PART 20
- c. Particulates, half-lives > 8 days: 10 CFR PART 20
- d. Liquid effluents: 10 CFR PART 20 and 2 E-04 uCi/ml for Dissolved Noble Gases
- 3. Average Energy Provide the average energy (E) of the radionuclide mixture in releases of fission and activation gases, if applicable.
0.309
- 4. Measurements and Approximations of Total Radioactivity Provide the methods used to measure or approximate the total radioacti-vity in effluents and the methods used to determine radionuclide composition.
- a. Fission and activation gases: Gamma Spectroscopy of Grab Samples
- b. Iodines: Gamma Spectroscopy of Continuous Samples
- c. Particulates: Gamma Spectroscopy of Continous Samples
- d. Liquid effluents: Gamma Spectroscopy of Batch Grab samples or Composited Samples
- 5. Batch Releases i
l Provide the following infonnation relating to batch releases of radio-active materials in liquid and gaseous effluents.
- a. Liquid
- 1. Number of batch releases: 4.44 E+02
- 2. Total time period for batch releases: 3.19 E+04 min
- 3. Maximum time period for a batch release: 1.90 E+03 min
- 4. Average time period for batch releases: 7.1 E+01 min
- 5. Minimum time period for a batch release: 1.2 E+01 min
- 6. Average stream flow during periods of release of effluent into a flowing stream: 2.83 E+5 gpm 8612090475 860828 PDR ADOCK 05000249 R PDR
- b. Gas 6 mis
- 1. Number of batch releases: 9
- 2. Total time period for batch releases: 3.70 E+03 min
- 3. Maximum time period for a batch release: 7.02 E+02 min
- 4. Average time period for batch releases: 4.12 E+02 min
- 5. Minimum time period for a batch release: 2.64 E+02 min
- 6. Abnormal Releases
- a. Liquid
- 1. Number of releases: NONE
- 2. Total activity released:
- b. Gaseous
- 1. Number of releases: NONE
- 2. Total activity released:
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EFFIDERFF AND MASTE DISPOSAL S]!MIANNUAL REPORP GASEOUS EFFIDENTS - SUMMATION OF ALL RELEASES January - June, 1986 l l Unit l Quarter l Quarter lEst. Totall l I I I- I Error % i A. Fission & activation gases 1 2
- 11. Total release l Ci 11.48E+0ll4.28E+0ll 1.8E+011 12 .- Averace release rate for Deriod IuCi/secI1.90E+0015.44E+00l
- 13. Percent of technical sDecification limitI % i1.80E-04l5.14E-04I B. Iodines i1. Total iodine-131 I Ci l1.27E-04i1.04E-04! 1.5E+01I I2. Averace release rate for Deriod IuCi/sec11.63E-05l1.34E-05l I3. Percent of technical soecification 1imitI % l2.88E-0212.35E-02I C. Particulatc.s ll- Particulates with half-lives > 8 days l Ci ll.69E-0611.33E-061 4.4E+011 l2. Averace release rate for neriod IuCi/secI2.17E-07I1.69E-071
- 13. Percent of technical specification limitl % ll.63E-0511.27E-05l I4e -Gross aloha radioactivity I Ci i1.4OE-07l2.11E-08I D. Tritium 11, Total release l Ci 11.31E+0ll1.51E+011 3.0E+001 12, Averace release rate for Deriod IuCi/secI1.68E+0011.92E+00l I3. Percent of technical specification limitI % i1.98E-0412.26E-04I
EFFIDENT AND MASTE DISPOSAL SENIAIO10AL REPORT GASEOUS EFFIDENTS - ELEVATED RELEASE January - June, 1986 CONTINUOUS MODE BATCH MODE INuclides Raleased l Unit! Quarter IQuarter IQuarter iQuarter i I I i l l
- 1. Fission gases l 1 1 2 l 1 l 2. l 1 I I I l lkrvoton-85 l Ci l l I4.52E-02l 1 Ikrvoton-85m i Ci l1.21E-0214.88E-02l l I lkrvoton-87 I Ci I2.15E-02I8.72E-02I I I Ikrvoton-88 i Ci 12.85E-0211.21E-Oli i l Ixenon-133 I Ci l1.09E+01l2.62E+0113.43E+00l6.11E-03I Ixenon-135 I Ci l2.12E-02I1.54E+0111.52E-03I I lxenon-135m- I Ci 12.48E-0116.90E-Oli l l Ixenon-138 i Ci I8.04E-02l2.91E-011 I I l others (soecifv) l Ci l I I I I I xenon-131m l Ci !2.46E-2 11.19E-01I I I I xenon-133m i Ci I i1.57E-02l4.41E-02l l l l Ci l l I I I ITotal for oeriod l Ci l1.13E+01I4.28E+1 13.52E+0016.11E-03I I I I I l
- 2. Iodines l l l l l l l l l I
- liodine-131 l Ci I8.17E-0512.91E-05I I l I Ci 14.57E-0517.51E-05l liodine-133 I I liodine-135 l Ci l I I I l ITotal for oeriod I Ci i1.27E-04l1.04E-04I I I I I I I l
- 3. Particulates l l l l l
, l I- 1 I I I nu vuuium-89 I Ci l i I I I Istrontium-90 1 Ci l i I I I Icesium-134 I Ci l i I I I Icesium-137 I Ci l i I I I lbarium-lanthanum-140 l Ci l I i l I I Others (specifv) l Ci l I I I I I l Ci I I I I i l l Ci i I i l I lunidentified l Ci ll.69E-06fl.33E-061 I i l
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EFFIIH!NP AND Mim DISREAL SEMIAltiOAL RE:EGE LIQUID EFFIDENIS - SQt!ATIN OF AIL REIEASES January - June, 1986 l Unit l Quarter [ Quarter lEst.'lbtall l l l l Error. % l l l l A. Fission and activation products l 1 l 2 l I I I l1. Total release (not including tritium, l l l l l 1 cases alnha) I Ci I6.82E-03I3.26E-03l 1.2E+01 l l2. Average diluted m c ukation l l l l l durim period IuCi/mlI6.20E-lll1.93E-11I I3. Percent of acolicable limit I % 12.58E-0312.42E-04I I I I B. Tritium l l l l l l
- 11. Total release i Ci 16.55E+0117.82E+011 3.2E+00 l l2. Average diluted cusccukation l l l l t durim ceriod IuCi/mlI5.95E-07I4.63E-07I I3. Fwmd of aDolicable limit 1 % i1.98E-02l1.54E-02I I I l C. Dissolved and entrained gases l l l 1 1 I I1. Total release I Ci I3.21E-0414.61E-07I 3.6E+01 I l2. Average diluted uam.aukation l l l l I durim period IuCi/mli2.92E-1212.73F-15I I3. Percent of aoolicable limit I % i1.46E-06l1.36E-09I I I I D. Gross alpha radioactivity l l l l l I l l1. Total release I Ci I9.14E-07I I 4.0E+01 l I I I i 1 l I l
lE. Volume of waste released (crior to dilution) Iliters12.91E+07I3.97E+071 5.0E+00 l IF. Volume of dilution water used durim Deriod IlitersI1.10E+1111.69E+111 5.OE+00 I i
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O i-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS January - June, 1986 CONTINUOUS MODE BATCH MODE INuclides Released IUnitlOuarter louarter IOuarter IOuarter I 1 2 1 2 istrontium-89 I Ci l I
- II.40E-041
- I istrontium-90 l Ci l l 17.23E-041
- I Icesium-134 I Ci 13.95E-051 18.24E-0413.56E-04l Icesium-137 I Ci 11.80E-04l2.51E-04l2.36E-0311.39E-031 liodine-131 l Ci 13.55E-0711.60E-0612.88E-0517.18E-051 l
l Icobalt-58 i Ci 12.03E-071 14.56E-0418.20E-051 icobalt-60 l Ci 13.88E-0717.39E-0516.41E-0411.02E-031 liron-59 l Ci l l l I I Izinc-65 l Ci l i I I I imancanese-54 l Ci l 15.89E-0915.99E-05l2.15E-06l Ichromium-51 l Ci l I I2.30E-0416.23E-06l Izirconium-niobium-95 I Ci l i II.58E-05tl.21E-06l Imolvbdenum-99 I Ci l i l i I Itechnetium-99m l Ci l l I I 1 j lbarium-lanthanum-140 l Ci l i I I I j leerium-141 l Ci I I i l l I Other (snecifv) l Ci I I i I I J iron-55 I Ci ll.10E-031
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- 1 I iodine-133 I Ci 12.01E-0614.32E-06I I I I ruthenium-103 I Ci l I ll.93E-06l I I silver-110m l Ci l I ll.72E-0513.81E-06l l I Ci l i I I I lunidentified I Ci i l i I I ITotal for Deriod (above)I Ci l i I l 1 lxenon-133 I Ci l 1 12.62E-04l I lxenon-135 I Ci l 1 15.86E-0514.61E-071 l
NOTE: Isotopes for which no value is given were not identified in applicable releases.
- Sample sent out for analysis but results not yet received. Data for identified isotopes to be included with next semiannual report l for July-December, 1986.
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EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) l l l 6-month l.Est. Total l I 1. Tvoe of waste l Unit i Period l Error % l la. Spent resins, filter sludges, l m3 l 3.2E+01 l l l evaporator bottoms, etc. l Ci I 4.7E+00 1 1.2 E+01 I
.lb. Dry compressible waste, con- l m3 l 7.8E+01 l l l taminated eculo, etc. I Ci I 2.2E+01 1 1.2 E+01 l lc. Irradiated components, control l m3 l l l l rods, etc. -1 Ci I I I ld. Other (describe) l m3 l l l 1 l Ci I i 1
- 2. Estimate of major nuclide composition (by type of waste)
- a. H-3 I i 8.0E+01 1 '
Cs-137 I l 8.0E+00 i Co-60 l I 2.0E+00 I
- c. I l l I I I I I I
- d. I I I I I I I I I
- 3. Solid Waste Disposition Number of Shioments Mode of Transoortation Destination 6 Highway Carrier Barnwell, SC e
l B. IRRADIATED FUEL SHIPMENTS (Disposition) i Number of Shioments Mode of Transportation Destination
, 19 Spent Fuel Cask Ginna Station
- from West Valley
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RELEASE PERMITS NOT MEETING LLD VALUE No. I Date i Ipotones I Cause l I i 100 l 2/14/861 Fe-59, Zn-65, Cs-134, Ce-141 l a.
136 l 2/25/86l Fe-59, Zn-65, Cs-137, Ce-141 l a.
165 l 3/8/86 l Fe-59, Zn-65, Ce-141 l a.
I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I
- a. Activity from other isotopes caused an increased background resulting in the LLD calculation exceeding SE-07 for the listed isotopes.
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EFFIDENT AND MASTE DISPOSAL SEMIANNUAL REPOEU 1
LIQUID EFr W S - SUMMATION OF ALL RELEASES July - December, 1985 l Unit l Quarter l Quarter lEst. Total l l l l l Error. % i i l i A. Fission and activation products l 3 l 4 l l l I
[1. Total release (not including tritium, l l l l l l cases. aloha) I Ci 12.97E-0218.35E-021 I l2. Average diluted concentration l l l l l durina ceriod IuCi/mli1.48E-1015.03E-10l l3- Percent of apolicable limit I % 15.85E-04I8.25E-03I I I I B. Tritium l l l I I I i1. Total release l Ci l1.23E+0211.26E+02l I l2. Average diluted concentration l l l l 1 durina Deriod IuCi/mlI6.12E-0717.59E-071
- 13. Percent of anolicable limit I % l2.04E-0212.53E-02I I I I C. Dissolved and entrained gases l l l l 1 1 Ile Total release I Ci i 16,73E-071 I l2. Average diluted concentration l l l l l durina coriod IuCi/mll I4.05E-15I I3. Percent of anolicable limit I % I l4.05E-081 I I I D. Gross alpha radioactivity l l l l l l
- 11. Total release i Ci I I I i l l I I I I IE. Volume of waste released (orior to dilution) Iliters12.99E+0713.49E+07I I IF. Volume of dilution water used durina Deriod Ilitersi2.01E+1111.66E+11l I i
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EFFIDENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS July - December, 1985 CONTINUOUS MODE BATCH MODE INuclides Released iUnitIQuarter IQuarter IQuarter iQuarter-1 3 4 3 4 Istrontium-89 I Ci l i I2.58E-0313.77E-02I Istrontium-90 1 Ci l I I5.99E-06I I Icesium-134 i Ci 13.73E-0619.68E-0514.77E-0411.50E-031 lcesium-137 I Ci 11.76E-03l2.59E-0411.27E-0313.31E-031 liodine-131 l Ci 15.07E-0611.25E-04l2.21E-0612.21E-05l icobalt-58 I Ci 11.88E-0813.44E-0812.17E-0513.17E-061 i
Icobalt-60 1 Ci 19.46E-0814.85E-0419.80E-0413.75E-04l liron-59 i Ci i l l I I Izinc-65 I Ci l I I I I imancanese-54 i Ci l i 14.04E-051 I Ichromium-51 l Ci l i 16.25E-061 I Izirconium-niobium-95 I Ci l 1 12.78E-06l I luolybdenum-99 I Ci i l i I I Itechnetium-99m 1 Ci I I I I I lbarium-lanthanum-140 I Ci I i l l I icerium-141- l Ci i l l I I I Other (snecifv) I Ci l i I I I I silver-110m l Ci i l 12.74E-0617.46E-071 I iodine-133 i Ci 15.25E-0612.07E-04l I I I iron-55 I Ci ll.74E-021 15.11E-0313.98E-02l l I Ci i l I l l l l Ci l i l l I lunidentified l Ci l l I I I ITotal for Deriod (aboveil Ci 11.92E-0211.17E-03fl.05E-0214.84E-031 lxenon-133 I Ci I i I 18.23E-021
-lxenon-135 l Ci i l i I I
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NOTE: Isotopes for which no value is given were not identified in applicable releases.
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