ML17309A342
| ML17309A342 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/30/1984 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17309A341 | List: |
| References | |
| NUDOCS 8409260135 | |
| Download: ML17309A342 (18) | |
Text
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility "Ginna Station Report Period:
January 1 to June 38, 1984 Licensee Rochester Gas 6 Electric Regulatory Limits a
~b.
C ~
d I Fission and activation gases:
Particulates, half-lives 8 days:
Liquid effluents:
6.38 E+85 uCi/sec 4.55 E-82 uCi/sec 1.86 E+88 uCi/sec Identified MPC 2 ~
Maximum Permissible Concentrations Provide the MPCs used in determining allowable release rates or concentrations.
a.
Fission and activation gases:
18 CFR PART 28 b.
18 CFR PART 28 c.
Particulates, half-lives 8 days:
18 CFR PART 28 d.
Liquid effluents:
18 CFR PART 28 6 2E-84 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.
4 ~
8.189 Mevz Measurements and Approximations of Total Radioactivity 5 ~
b.
c.
Particulates:
d.
Liquid effluents:
Batch Releases Provide the methods used to measure or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
a.
Fission and activation gases:
Gamma Spectroscopy of Grab Samples and Continuous Gross ActivityMonitoring Gamma Spectroscopy of Continuous Samples Gamma Spectrocsopy of Continuous Samples Gamma Spectroscopy of Batch Grab Samples or Composited Samples.
Provide the following information relating to batch releases of radioactive materials in liquid and gaseous effluents.
a.
Liquid 1 ~
2 ~
3 ~
4 ~
5.
6.
Number of batch releases:
Total time period for batch releases:
Maximum time period for a batch release:
Average time period for batch releases:
Minimum time period for a batch release:
Average stream flow during periods of release of effluent into a flowing stream:
8409260135 840905 PDR ADOCK 05000244 R
PDR 498 46891 min.
3326 min.
94 min.
18 min.
2'8 E+85 gpm
~ 4 P
s I'
b.
Gaseous 1 ~
2 ~
3 ~
4 ~
5 ~
Number of batch releases:
Total time period for batch releases:
Maximum time period for a batch release:
Average time period for batch releases:
Minimum time period for a batch release:
ll 3573 min.
615 min.
325 min.
76 min.
Abnormal Releases a
~
Liquid 1.
Number of releases:
NONE 2.
Total activity released:
b.
Gaseous 1.
Number of releases:
NONE 2.
Total activity released:
~
~
~
IB B
TABLE lA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total I
1 I
2 I Error 8
I A.
Fission R activation gases 1;" Total 'release 2.'vera e"eel'ease rate for eriod Cz.
- 2. 39E+82 3 ~ 28E+88 1. 3 "E+
1 uCi sec 3.84E+81 4.17E-81 3;
Percent of technical s ecification limit 8
4.83E-83 6 '2E-85 B.
Iodines 1.
Total z.'odine-131 2.
Avera e release rate for era.od Ci 1
~ 38E-83 1
~ 64E-84 1
~ 5 E+81 uCi sec 1.65E-84 2.89E-85 3.
Percent of technical s ecification limit 8
3.68E-81 4.58E-82 C.
Particulates 1.
Parts'culates with half-loves 8 da s
2.
Avera e release rate for era.od C3.
1
.8 E+81 uCi sec 2.43E-87 1.11E-87 3:
Per'cent"of technical s ecification limit 2.29E-85 1.85E-85 4;
Gross al ha radioactivit Ci 8.88E-88 1
~ 46E-87 D.
- 1. '"Total release Ci 2 '1E+81 2 '3E+81 8 '
E+88
- 2. 'vera e rel'ease 'rate for eriod uCi sec 2.94E+88 2.56E+88
- 3. " Percent of technica'1 s ecification limit 8
3.44E-84 2.99E-84
~
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TABLE 1B EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
GASEOUS EFFLUENTS ELEVATED RELEASE Nuclides Released CONTINUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter 1.
Fission gases kr ton-85 Ci 6.58E-81 1 ~ 64E+88 2 '2E+88 kr ton-85m kr ton-87 kr ton-88 xenon-133 xenon-135 xenon-135m xenon-138 Others s ecif xenon-133m xenon-131m unidentified Total for eriod 2.
Iodines moderne-131 iodine-133 iodine-135 Total for eriod 3.
Particulates Cz.
1 ~ 18E+88 2.96E-82 Ci 3.48E-81 8. 37E-82 1. 31E-81 1. 95E-81 Cx Ci 2 '1E+82 6 '8E-81 7 '6E+88 2 '7E+88 Ci 1 ~ 38E-83 1 ~ 64E-84 Ci
~ 48E-83 1 ~ 82E-84 Ci 6 '8E-82 2 '7E-83 5 '4E-83 Ci 8 '7E-83 5 '8E-83 C3.
1
2 '5E+82 3 '4E-82 6 '5E+88 3 '7E-81 Ci 4 '1E+88 3 '7E-81 Ci 9 '8E-82 6 '4E-82 Ci 8 '2E-83 1
~ 88E-82 Ci strontium-89 strontium-98 cesium-134 cesium-137 barium-lanthanum-148 Others s eci f unidentified Ci Cz.
Ci Ci Ci Ci Ci Ci Samples sent out. for analysis but results not yet received.
Data to be included with next semiannual report for July December, 1984.
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EFFLUENT AND MASTE DISPOSAL SENI293KHG REPORT (YEAR)
LIQUID EFFLUENTS SUMMATION OF ALL RELEASES
- Unit, Quarter Quarter Est.Total
- IError, 8
I A.
Fission and activation products 1.
Total release not a.ncludz.ng trzt~um, I
- ases, al ha) 2.
Average diluted concentration I
durin eriod 3.
Percent of a licable limit B.
Tritium Ci I8.75E-83I9.83E-82I8.7 E+88 I
I uCi ml I 5. 92E-11 I 7 ~ 69E-18 I 3.12E-84 4.24E-83 1.
Total release 2..
Average diluted concentration I
'durin eriod 3.
Percent of a lxcable lame.t C.
Dissolved and entrained gases
- 1. Total release 2.
Average diluted concentration I
durin eriod 3.
Percent of a lzcable lmzt D.
Gross alpha radioactivity 1.
Total release Ci 1 ~ 33E+82 8 '7E+81 8.8 E+88 luCi mll8.96E-8717.38E-87I 2 '9E-82 2 ~ 6E-82 Ci 6 '2E-84 2 '9E-85 2 '
E+81 I uCi ml I 4. 28E-1211. 86E-13'I 2.18E-6 9.28E-8 Ci 1 ~ 22E-85 2 '6E-84 2 '
E+81 I
I I
E. Volume of waste released rior to dzlutzon liters 3.52E+87 2.51E+87 5.8 E+88 F. Volume of dilution water used durban erxod liters 1.48E+ll 1.18E+ll 5.8 E+88
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TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
LIQUID EFFLUENTS Nu'clides Released CONTINUOUS MODE BATCH MODE Unit Quarter Quarter Quarter Quarter
'strontium-89 strontium-98 cesium-134 cesium-137 iodine-131 Cz.
Ci Ci Ci Ci
- 2. 88E-86 1 ~ 68E-83 2 ~ 18E-82 2.71E-83 3.48E-82 5 ~ 37E-86 cobalt,-58 cobalt-68 iron-59 zinc-65 man anese-54 chroma.um-51 zz.rconxum-nz.obz.um-95 mol bdenum-99 technetium-99m barium-lanthanum-148 cerium-141 C3.
Ci Ci Ci Ci Cz Ci-C3.
Ci Ci Ci 2 ~ 17E-84 5 ~ 88E-83 3.24E-83 2.81E-82 2.18E-84 6 '1E-84 1 ~ 76E-83 9 '5E-5
~
E-2.85E-85 5.48E-84
- 3. 35E-87 l. 86E-85 Other s ecif ruthenium-183 silver-118m cerium-144 iron-55 unidentified Ci Ci Ci Ci Ci 6
~ 86E-86 3
~ 46E-85 2 ~ 28E-84 5 '8E-83 xenon-133 Ci Total for eriod above Ci 8.75E-83 9.83E-82 6 '2E-84 2 '9E-85 xenon-135 Ci Samples sent out for analysis but results not yet received.
Data to be included with next semiannual report for July December, 1984
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REL SE PERMITS NOT MEETING LLD ALUE No.
283 204
- 285, 206 221 223 224 225 230 234 235 238 239 248 241 243 247 255 256 257 258 259 272 274 276 278 288 289 298 355 411 424 446 447 449 478 471 472 473 483 Date Isoto es 3 /14/84 I Co-68 3/15/84 I Fe-59, Zn-65, Cs-137, Ce-141 3/16/84 I Fe-59, Zn-65, Cs-137, Ce-141 3/16/84 I Fe-59, Zn-65 3/27/84 I Fe-59, Zn-65, Cs-137, Ce-141 3/28/84 I Zn-65, Cs-137, Ce-141 3/28/84 I Fe-59, Zn-65, Cs-137, Ce-141 3/29/84 I Fe-59, Zn-65, Cs-137, Ce-141 4/81/84 I Fe-59, Zn-65, Cs-137, Ce-141 4/03/84 l Co-68 4/83/84 I Zn-65, Cs-137, Ce-141 4/05/84 j Fe-59, Zn-65, Ce-141 4/05/84 I Fe-59, Zn-65, Cs-137, Ce-141 4/05/84 I Zn-65, Ce-141 4/86/84 I Zn-65, Cs-137, Ce-141 4/87/84 I Fe-59, Zn-65, Ce-141 4/88/84 I Fe-59, Zn-65 4/ll/84 I Zn-65, Ce-141 4/12/84 I Fe-59, Zn-65, Cs-134, Cs-137, Ce-141 4/12/84 I Ce-141 4/13/84 I Mn-54, Fe-59, Zn-65, Cs-137, Cs-134, Ce-141 I
4/13/84 I Fe-59, Zn-65, Ce-141 4/18/84 I Fe-59, Zn-65, Cs-13 7, Ce-141 4/18/84 I Zn-65, Cs-134, Cs-137, Ce-141, I-131 4/18/84 I Fe-59, Zn-65, Cs-137, Ce-141 4/19/84 I Zn-65 4/28/84 I Fe-59, Zn-65, Cs-137, Cs-134, Ce-141 4/22/84 I Fe-59, Zn-65, Cs-134, Ce-141 4/22/84 I Fe-59, Zn-65, Ce-141 5/15/84 I Co-68 5/38/84 I Fe-59, Zn-65 6/82/84JCo-68 6/12/84IFe-59,Zn-65,Cs-137,Ce-141 6/12/84jZn-65,Cs-134,Cs-137,Ce-141 6/13/84IZn-65,Cs-134,Cs-137,Ce-141 6/23/84 I Ce-141 6/23/84 I Fe-59, Zn-65, Cs-134, Cs-137, Ce-141 6/24/84 j Fe-59, Zn-65, Cs-137, Ce-141 6/24/84 I Fe-59, Zn-65 6/28/84ICo-68 I
Cause a
~b.
b.
b.
b.
b.
b.
b.
b.
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b.
b.
b.
b.b.
b.
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a ~
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b.
b.
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b.b.
a
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'k t
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a
~
Co-68 is normally found as a background activity in all samples.
When poor peak resolution is obtained from the detector and/or electronics on samples with no detectable activity, a high LLD calculation may result after the background correction in the Co-68 peak, area.
b ~
Activity from other isotopes caused an increased background resulting in the LLD calculation exceeding 5E-87 for the listed isotopes.
2/26/84 Retention tank composite of continuous release.
Sampler was disconnected from sample point for majority of sample period.
Sample obtained was small and not representative of compositing period.
Releases through this sample point normally have no identifiable isotopes.
4
~
> f f
TABLE 3 EFFIlJENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLID WASTE AND IRRADIATED FUEL SHIPMENXS A.
Solid Mste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 1.
Type of Waste
- a. Spent resins, filter slu9ges, evaporato bottans, etc.
- b. Dry canpressible
- mste, contaminated equip., etc.
- c. Irr rat amponents, contro rods, etc.
. Ot er escrow e
Unit m
Ci m
Ci N/A 6-month Period 6.14E 1
2.02E 2 4.34E 1
6.25E 0 est. mtal
- Error, 5.'0 E 0 1.4E1 2.
Estimate of major nuclide ccm~siting (by type of waste) 2.0E 1
Go-58 Co- 0.
Nz-63 Cs-134 Cs-137 b.
Go-58 Co-60 Cs-134 Cs-137 Nz-63 1.6E 0 4.0E 1
8.0E 0 8.4E 1
4.0E 1
2.9E 0 3.2E 1
1.7E 1
3.2E 1
4.8E 0 7.1E 0 3.
Solid Waste Disposition Number of Shipnents Rx3e of Transportation Highway Wansport Highway Wansport Destination
- Barnwell, SC
- Richland, WA, B.
Irradiated Fuel Shipnents (Disposition)
Number of Shipnents
%de of Trans rtation Destination None Shipped
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