ML18038B651
| ML18038B651 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18038B649 | List: |
| References | |
| NUDOCS 9604010031 | |
| Download: ML18038B651 (30) | |
Text
ENCLOSURE 2 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEARPLANT(BFN)
UNITS 1, 2, AND3 EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT 1995 96040i003i
'760321 PDR ADQCK 05000259 R
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 Re ulato Limits A.
Fission and Activation Gases in Gaseous Effluent:
The release offission and activation gases is regulated by the dose limits of10 CFR 50 Appendix I. The air dose to areas at and beyond the site boundary due to noble gases released in gaseous effluents per unit, shall be limited during any calendar quarter to < 5 millirad (mrad) for gamma radiation and < 10 mrad for beta radiation; and during any calendar year to < 10 mrad for gamma radiation and < 20 mrad for beta radiation.
B.
Iodines and Particulates with Half-Lives Greater than Eight Days in
'aseous Effluents.
The release ofiodines and particulates in gaseous effluent is regulated by the dose limits of 10 CFR 50 Appendix I. The dose to a member ofthe public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases withhalf-lives greater than eight days in gaseous effluent released per unit to areas at and beyond the site boundary shall be limited to any organ during any calendar quarter to < 7.5 millirem (mrem), and during any calendar year to < 15 mrem.
C.
LiquidEffluents The release ofradioactive liquid effluents is regulated by the dose limits of 10 CFR 50 Appendix I. The doses or dose commitment to a member ofthe public from radioactive materials in liquid effluents released from each unit to unrestricted areas shall be limited during any calendar quarter to < 1.5 mrem to the total body and <5 mrem to any organ and during any calendar year to < 3 mrem to the total body and < 10 mrem to any organ.
H.
Limitation on Dose Rate A.
Fission and Activation Gases in Gaseous Effluent:
1.
The instantaneous release rate offission and activation gases is based on dose rate limit. The dose rate at any time to areas at and beyond the site boundary due to noble gases released in gaseous effluents from the site shall be limited to < 500 mrem per year to the total body and
< 3000 mrem per year to the skin.
2.
The BFN Offsite Dose Calculation Manual (ODCM) Section 7.2 determines the maximum noble gas release rate.
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EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 II.
Limitations on Dose Rate Continued B.
Iodines and Particulates with Half-Lives Greater than Eight Days in gaseous effluents.
1.
The instantaneous release rate ofparticulates and iodines is regulated by the dose rate limits. The dose rate at any time to areas at and beyond the site boundary, due to I-131, I-133, H-3 and particulates with greater than eight days half-lives released in gaseous eflluents from the site, shall be limited to < 1500 mrem per year to any organ.
2.
The BFN ODCM Section 7.2 determines the maximum particulate and iodine release rate limit.
C.
LiquidEQluents 1.
The concentration ofradionuclides in liquid e81uents released at any time &omthe site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.
2.
For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi per milliliter(ml) total activity.
Measurements and A roximations ofTotal Radioactivi A.
Fission and Activation Gases:
Noble gases in the building vent and stack gaseous e61uent are continuously monitored.
The flowrate ofthe stack is continuously monitored and the building vent eBluent flow rates are calculated once a shift based on the configuration ofoperating exhaust fans. The vent flowis calculated for each release.
Gas grab samples ofinput streams to the stack are taken and analyzed weekly. Gas grab samples ofin-service vents are taken and analyzed monthly. The specific noble gas activity concentrations and total volume of the gases are used to calculate the total curies and noble gases released.
2.
The tritium concentration is determined by the analysis ofa monthly grab sample for each release point.
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EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 III.
Measurements andA roximationsofTotalRadioactivi continued B.
Iodines and Particulates 1.
Iodines and particulates are continuously sampled on impregnated charcoal filters and particulate filters, respectively.
The charcoal and particulate samples are replaced at least weekly and analyzed to determine specific activity concentrations.
The specific activity concentrations and vent flowrate data are used weekly to verifythat release rate limits were not exceeded.
The specific activity concentrations and total volume ofgaseous effluent are used on a monthly basis to determine the total curies ofeach particulate and iodine released during the month.
2.
The gross alpha concentration is determined by analysis of a monthly particulate filter composite sample and strontium -89 and -90 are determined by analysis ofa quarterly particulate filter composite sample for each release point C.
LiquidEffluents 1.
The gamma ray emitting radionuclide concentrations are determined for each batch by gamma ray spectroscopy analysis ofa grab sample.
The allowable release rate is calculated for each batch based upon the known dilution flow. The flowrate ofthe liquid effluent is continuously monitored and the total volume released in each batch is determined.
The total gamma activity released in each batch is determined by multiplying the radionuclide concentrations by the total volume discharged.
The total gamma activity released during the month is then determined by summing the gamma activity content of each batch discharged during the month.
2.
The gross alpha and tritium concentrations are measured on a monthly composite sample.
The strontium -89 and -90 and iron -55 are measured on a quarterly composite sample.
D.
The Radioactive Gaseous and LiquidWaste Monitoring Sampling and Analysis Program is specified in ODCM Sections 1/2.2.1 and 1/2.2.2.
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0
4 IV.
Batch EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT SUPPLEMENTALINFORMATION 1995
.A.
Liquid Units guarter 1
uarter Quarter 3
uarter 1.
Number ofbatches released 2.
Total time for batch released 3.
Maximum time period for a batch release 4.
Average time period for a batch release 5.
Minimumtime period for a batch release 6.
Average stream flowduring period of release into a flowing stream Each Minutes Minutes Minutes Minutes 41 10722 328 262
'60 39 10170 318 261 135 72 18624 350 259 135 85 21575 320 254 196 Cubic feet per second 72194 17405 31320 58367 B. '- Gaseous None C.
Abnormal/Unplanned Releases
'ype Number of Releases Total Activity Releases (Curies)
Liquid Gaseous None None None None
'n explanation ofany liquid or gaseous abnormal/unexplained release shall be documented in the summaty.
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A.
Fission and Activation Products (Does not include tritium, gases, Alpha)
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES YEAR 1995 Unit guarter Quarter guarter guarter
% Error 1
2 3
4 l.
Total Release Curies 6.66E-02 1.37E-01 3.45E-Ol 3.85E-Ol 9
2.
Average Diluted Concentration Released During Period 3.
Percent ofApplicable Limit B.
Tritium pCi/ml 2.74E-09 5.66E-09 5.26E-09 4.56E-09 1.
Total Releases Curies 2.08E+00 2.36E+00 5.93E+00 5.99E+00 6
2.
Average Diluted Concentration Released During Period 3.
Percent ofApplicable Limit C.
Dissolved and Entrained Noble Gases pCi/ml 8.5SE-08 9.77E-08 9.03E-OS 7.10E-08 0/
1.
Total Releases Curies 2.78E-04 6.57E-04 3.19E-03 4.95E-03 8
2.
Average Diluted Concentration Released During Period 3.
Percent ofApplicable Limit D.
Gross Alpha Radioactivity 1.
Total Releases pCi/ml 1.14E-11 2.72E-11 4.86E-11 5.87E-11 Curies ND 48 2.
Average Diluted Concentration Released During Period E.
Volume ofLiquidWaste to Discharge Canal (Prior to dilution) pCi/ml ND Liters 4.66E+06 4.33E+06 8.47E+06 1.03E+07 3
F.
Volume ofDilutionWater for Period Liters 2.43E+10 2.42E+10 6.56E+10 8.43E+10 10 G.
Total CCW gigagallons 7.96E+01 8.96E+Ol 1.41E+02 1.43E+02
- The applicable limitis expressed in terms of dose. See Tables 5-8.
t
~Iaoto e
(Required by Regulatory (REG) Guide 1.21) 1.
Ba-140 Quarter Quarter Quarter 2
3 4
ND ND ND EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT LIQUIDRELEASES FOR YEAR 1995 - BATCHMODE CURIE Quarter 1
ND Op 2.
Ce-141 3.
Co-58 4.
Co-60 5.
Cr-51 6.
Cs-134 7.
. 8.
Fe-59 9.
I-131 10.,
La-140 11.
Mn-54 12.
Mo-99 13.
Nb-95 14.
Sr-89t'~
15.
Sr-90">
16.
Tc-99m 17.
Xe-133 18.
Xe-135 19.
Zn-65 20.
Zr-95 5.13E-05 4.52E-04 8.96E-04 6.25E-04 1.15E-02 1.62E-02 2.16E-02 2.69E-02 3.33E-05 2.76E-03 1.30E-02 1.36E-02 5.46E-05 8.95E-06 1.99E-04 2.15E-04 7.08E-04 8.96E-03 ND 7.71E-05 ND 9.32E-04 3.33E-05 2.70E-03 1.45E-02 1.57E-02 1.85E-04 8.11E-05 6.65E-04 9.84E-04 9.25E-05 5.76E-04 2.52E-03 3.94E-03 3.47E-03 2.32E-03 7.78E-04 1.06E-04 5.33E-04 1.80E-03 3.38E-03 5.93E-03 2.22E-02 2.87E-02 2.30E-02 2.45E-02 ND 3.65E-03 2.29E-02 2.42E-02 1.91E-03 2.68E-03 2.73E-03 1.78E-03 2.16E-02 3.14E-02 4.32E-02 3.49E-02 Predicted estimation ofreleases.
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I~toto e
Others (Not Required by REG Guide 1.21)
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT LIQUIDRELEASES FOR YEAR 1995 - BATCHMODE CURIE Quarter Quarter Quarter Quarter 1
2 3
4 l.
Ag-110m 2.
Co-57 Fe-SS"'.
I-133 5.
Na-24 6.
Nb-97 7.
Ru-103 8.
Sb-124 9.
Ce-144 5.33E-04 1.40E-04 7.24E-04 6.93E-04 ND 2.46E-05 ND 3.99E-04 3.37E-04 8.85E-03 1.69E-03 ND 8.77E-04 3.28E-03 3.44E-03 3.57E-03 4.21E-02 1.83E-01 2.20E-01 4.13E-04 1.42E-04 7.44E-04 6.62E-04 ND 6.85E-04 3.88E-05 2.79E-05 ND 1.07E-04 ND 10.
Sr-92 11.
Ar-41 12.
Kr-87 13.
Zr-97 14.
Mn-56 1.06E-04 3.23E-05 1.02E-04 1.02E-04 2.28E-05 ND 7.55E-06 ND 1.57E-05 ND ND 1.26E-04 3.35E-04 Predicted estimation ofreleases.
This section ofthe Annual Report was prepared principally by D. W. Nix.
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EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES YEAR 1995 A.
Fission and Activation Gases Unit Quarter Quarter Quarter Quarter
% Error 1
2 3
4 1.
Total Releases Ci 3.32E+00 9.91E-01 4.62E+00 1.51E+Ol 45 2.
Average Release Rate for Period pCi/sec 4.28E-01 1.26E-Ol 5.82E-Ol 1.90E+00 3.
Percent ofApplicable limit B.
Iodines 1.
Total Iodine-131.
Ci 6.32E-05 7.78E-05 1.66E-04 3.45E-04 36 2.
Average Release Rate for Period pCi/sec 8.13E-06 9.90E-06 2.08E-05 4.34E-05 3.
Percent ofApplicable Limit C.
Particulates 1., Particulates withhalf-lives eight days 2.
Average release rate for period 3.
Percent ofApplicable limit 4.
Gross alpha radioactivity D.
Tritium Ci 1.23E-04 6.70E-05 2.10E-05 2.31E-04 35 pCi/sec 1.58E-05 8.52E-06 2.64E-06 2.91E-05 Ci 1.
Total release 2.
Average release rate for period 3.
Percent ofApplicable Limit Ci 1.93E+00 2.44E+00 3.16E+00 2.84E+00 21 pCi/sec 2.48E-Ol 3.10E-01 3.98E-Ol 3.57E-01 Applicable Limits are expressed in terms ofdose. See Tables 1-4.
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1.
Fission Gases Quarter 3
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - ELEVATEDRELEASE CURIES Quarter Quarter 1
2 Quarter 4
Kr-85m Kr-85 Kr-87 Kr-88 Xe-'133 Xe-135m Xe-135 Xe-138 Others (specify)
Ar-41 Xe-137 8.77E-Ol 2.73E-Ol 4.31E-01 7.23E-02 1.42E+00 6.46E-01 1.46E-01 5.21E-02 3.38E-01 5.94E-02 8.85E-01 2.17E+00 1.46E+00 1.02E-01 1.09E+00 1.17E+00 7.82E-01 3.06E+00 1.39E+00 2.88E+00 1.48E-01 4.75E-01 3.96E-02 2.89E+00 1.83E-01 9.95E-01 Total for Period 3.32E+00 9.91E-01 4.62E+00 1.51E+01 2.
Iodines I-131 4.72E-05 2.39E-05 6.72E-05 6.78E-05 I-132 I-133 1.86E-04 1.31E-04 1.94E-04 3.13E-04 I-134 I-135 9.36E-05 Total for Period 2.34E-04 1.55E-04 3.55E-04 3.80E-04 E2-10
3.
Particulates t
~
Sr-89' Sr-90~~
Cs-134 Cs-137 Ba-140 La-140 guarter 1
7.74E-06 EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - ELEVATEDRELEASE CURIES guarter 2
guarter 4
Others (specify)
Rb-89 Y-91m Sr-91 Cs-138 Ba-139 La-140 Ba-140 1.35E-01 1.90E-03 4.78E-02 2.06E-04 3.79E-04 ND 2.73E-02 8.08E-04 6.39E-04 2.94E-02 ND 4.87E-06 2.27E-05 TOTALFOR PERIOD 4.
Tritium 1.36E-O]
8.08E-04 4.88E-02 6.41E-02 6.39E-04 1.05E-01 9.01E-02 1.08E-01 Includes all nuclides, even those with less than an eight day half-life.
" Predicted estimation ofreleases.
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1.
Fission Gases Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 Quarter 3
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - GROUND RELEASE CURIES Quarter Quarter 1
2 uarter Xe-13'5m Xe-135 Xe-138 Total for Period 2.
Iodines I-131 6.04E-06 3.65E-06 I-132 I-133 3.01E-05 1.87E-05 I-134 I-135 Total for Period 3.61E-05 2.24E-05 E2-12
3.
Particulates
'r-89"'r-90~
Cs-134 Cs-137 Ba-140 Quarter 3
1.22E-05 ND EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - GROUND RELEASE CURIES Quarter Quarter 1
2 uarter La-140 Others (specify)
Co-60 Total for Period I
4.
Tritium 4.72F 05 1.22E-05 3.18E-01 6.43E-01 5.82E-06 5.82E-06 2.68E-01 (1) Include all nuclides even those with less than an eight day half-life.
(2) Predicted estimation ofreleases.
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0
1.
Fission Gases Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 Xe-135m Xe-135 Xe-138 Quarter 3
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - MIXEDMODERELEASE
'URIE S
Quarter Quarter 1
2 uarter 3.25E-04 Total for Period 3.25E-04 2.
Iodines I-131 1.60E-05 5.39E-05 9.22E-05 2.33E-04 I-132 4.08E-04 I-133 2.50E-04 5.09E-04 8.47E-04 2.03E-03 I-134 I-135 1.09E-03 Total for Period 2.66E-04 5.63E-04 9.39E-04 3 76E-03
'he Reactor Building and Radwaste Building are treated as split-level releases.
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Quarter 3
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - MDKDMODERELEASE
'URIES guarter guarter 1
2 uarter 3.
Particulates
~
~
Sr-89' Sr-90~
~
Cs-134 Cs-137 2.91E-05 7.55E-06 2.20E-05 1.42E-05 2.81E-05 La-140 Ba-140 Others (specify)
Mn-54 Cr-51 Na-24 Mo-99 Tc-99m Co-60 Y-91m Ba-139 1.06E-05 6.81E-05 2.03E-05 8.23E-07 6.81E-06 3.07E-05 1.04E-03
, 3.18E-06 4.36E-05 3.18E-06 4.36E-05 2.93E-04 8.77E-03 3.20E-05 6.76E-06 1.17E-04 Total for Period 1.15E-04 5.48E-05 2,73E-05 1.04E-02 4.
Tritium 1.88E+00 2.06E+00 2.43E+00 2.46E+00
'he Reactor Building and Radwaste Building are treated as split-level releases.
"~ Includes all nuclides, even those with less than an eight day half-life.
"~ Predicted estimation ofreleases This section ofthe Annual Report was prepared principally by D. W. Nix.
DROWNS FERRY NUCLEARPLANT ANNUALEFFLUENT ANDWASTE DISPOSAL REPORT 1995 SOLID WASTE ANDIRRADIATEDFUEL Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)
T e ofWaste Units Amount Error %
a.
Spent resins, filtersludges evaporator bottoms, etc.
m Ci c.
Irradiated components, control rod drives, shroud head bolts, etc.
m3 Ci Diycompressible waste, contaminated m3 equipment, etc.
Ci 1.22E+02 2.88E+02 1.68E+02 3.07E+00 4.19E+Ol 2.54E+04
+/-25.0
+/-25.0
+/25.0 d.
Cartridge filters 1113 Ci 6.10E+00 1.04E+02
+/-25.0
- 2. Estimate ofMajor Nuclide Composition by Waste Type a.
Spent resins, filtersludges, evaporator bottoms, etc.
Nuclide
~Percents e
Activi Curies 1.
Cobalt (I) 2.
Cesium137 (I) 3.
Nickel (2) 4.
Manganese54 (I) 5.
Iron55 (2) 6.
Zinc65 (I) 7.
Silverl (1) 8.
Chromium51 (I) 9.
Cesium134 (1) 10.
Cobalt58 (I) 11.
Other 4.17E+Ol 1.59E+01 1.24E+01 9.58E+00 9.49E+00 4.55E+00 2.95E+00 1.68E+00 9.68E41 6.91E41
<1.0 1.20E+02 4.57E+Ol 3.58E+Ol 2.76E+Ol 2.73E+01 1.31E+01 8.51E+00 4.84E+00 2.79E+00 1.99E+00 3.70E41 b.
Dry compressible waste, contaminated equipment, etc.
Nuclide
~Percents e
Activi Curies 1.
Cobalt60 (2) 2.
Iron55 (2) 3.
Cesium137 (2) 4.
Manganese54 (2) 5.
Nickel (2) 6.
Other 4.61E+01 2.92E+01 1.43E+01 6.96E+00 2.82E+00
<1.0 1.42E+00 8.96E41 4.39E41 2.14E41 8.66E42 1.44E42 E2-16
DROWNS FERRY NUCLEARPLANT ANNUALEFFLUENT AND WASTE DISPOSAL REPORT 1995 SOLID WASTE ANDIRRADIATEDFUEL Solid Waste Shipped OQ'site for Burial or Disposal (Not Irradiated Fuel)
(Continued)
- 2. Estimate ofMajor Nuclide Composition by Waste Type (Continued)
- c. Irradiated components, control rod drives, shroud head bolts, etc.
Nuclide 1.
Cobalt60 2.
Iron55 3.
Nickel 4.
5.
Nickel59 6.-
Chromium51 7.
Other (2)
(2)
(2)
(2)
(2)
(2)
~Percenta e
5.90E+01 3.17E+01 5.71E+00 3.46E+00 3.60E42 3.18E42
<1.0 Activi Curies 1.50E+04 8.05E+03 1.45E+03 8.79E+02 9.14E+00 8.08E+00 2.35E+01
- d. Cartridge filters Nuclide 1.
Cobalt 60 2.
Iron 3.
Nickel63 4.
Chromium51 5.
Cesium137 6.
Manganese54 7.
Other (I)
(2)
(2)
(I)
(I)
(I)
~Percenta e
9.41E+01 1.83E+00 1.66E+00 1.00E+00 6.30E41 1.83E41
<1.0 Activi Curies 9.74E+01 1.90E+00 1.71EWO 1.04E+00 6.52E41 1.89E41 6.37E41 (I) Measured (2) Calculated E2-17
BROWNS FERRY NUCLEARPLANT ANNUALEFFLUENT ANDWASTE DISPOSAL REPORT 1995 SOLID WASTE ANDIIUUJ)IATEDFUEL Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)
(Continued)
- 3. Solid Waste Disposition Number ofShi ments 28 31 16 Mode ofTran ortation Sole Use Truck Sole Use Truck Sole Use Truck Sole Use Truck Destination Chem Nuclear Systems, Inc, Disposal Site, Barnwell, SC American
- Ecology, Oak Ridge, TN Scientific Ecology Group, Oak Ridge, TN Chem Nuclear Systems, Inc.,
Processing
- Facility, Barnwell, SC Number ofShi ments None Mode ofTran ortation N/A Destination N/A E2-18
BROWNS FERRY NUCLEARPLANT ANNUALEFFLUENT ANDWASTE DISPOSAL REPORT 1995 SOLID WASTE ANDIRRADIATEDFUEL Description ofShipments Number of
~Shi ments 32 Type Type Container Quantity Strong Tight A-LSA Container (STC)
Number of Containers 120 Container Waste Volume
~e See Note DAW Liner/Cask B
1.63 Irradiated Hardware 14 A-LSA 14 5.83 Dewatered Resin 2
16 HIC/Cask
>A-LSA HIC/Cask
>A-LSA HIC/Cask A-LSA HIC/Cask
>A-LSA DOT7A A 16 3.41 5.83 3.41 3.41 9.10 Cartridge Filters Dewatered Resin Dewatered Resin Dewatered Resin Control Rod Drives Solidification Agents Used:
None Absorbents Used:
None NOTE: The 32 shipments ofwaste packaged in strong tight containers consisted ofthe following:
T~enf STC 40'Sealand" 20'Sealand" Metal Box Metal Box Metal Box Metal Box Number ofPacka es 13 19 84 1
1 2
VolumeEachPacka e m 72.5 36.3 2.66 4.08 3.12 2.89 E2-19
EFFLUENT ANDWASTE DISPOSAL ANNUALREPORT
SUMMARY
OF ABNORMAL/UNPLANNEDRELEASES 1995 The radioactive e61uents for 1995 were normal for a three unit boiling water reactor plant with two units operating and one unit in extended outage.
The release ofradioactive material to the environment from Browns Ferry has been a small fraction ofthe 10 CFR 20 Appendix B and 10 CFR 50 Appendix I limits. There were no limits exceeded as specified in 10 CFR20 Appendix B and 10 CFR 50 Appendix I.
A compensatory sample for the inoperable raw cooling water system radiation monitor (3-RM-90-132) was missed on January 7, 1995. The sampling requirements are given in OfFsite Dose Calculation Manual (ODCM) Table 1.1-1 Action D. The sample was due on January 7, 1995, at 0405. Immediately upon discovering the missed sample, a sample was taken on January 7, 1995, at 0637. No activity was found in the samples'efore or after the missed sample (BFPER950022).
On September 19, 1995 at approximately 0744, a continuous air monitor (2-RM-90-249) was inadvertently placed in standby.
The monitor was discovered in standby on September 22, 1995, and placed in service at 1023. While the monitor was in standby all data was still available although no alarms were capable of being processed.
Data was obtained shituy and recorded while the monitor was in standby. Allrecorded data was below the setpoints while the monitor was in standby.
The reason for the monitor being placed in
~~,
standby could not be determined.
A change willbe made to a plant procedure to check the status ofthe continuous air monitors each shift (BFPER951320).
E2-20