ML18038B651

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Effluent & Waste Disposal Annual Rept 1995.
ML18038B651
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/31/1995
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18038B649 List:
References
NUDOCS 9604010031
Download: ML18038B651 (30)
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ENCLOSURE 2 TENNESSEE VALLEYAUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL ANNUALREPORT 1995 96040i003i '760321 PDR ADQCK 05000259 R PDR

EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 Re ulato Limits A. Fission and Activation Gases in Gaseous Effluent:

The release of fission and activation gases is regulated by the dose limits of 10 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 of iodines and particulates in gaseous effluent is regulated by the dose limits of 10 CFR 50 Appendix I. The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-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. Liquid Effluents The release of radioactive liquid effluents is regulated by the dose limits of 10 CFR 50 Appendix I. The doses or dose commitment to a member of the 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 of fission 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 AND WASTE 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 of particulates 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. Liquid EQluents

1. The concentration of radionuclides in liquid e81uents released at any time &om the 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 of Total Radioactivi A. Fission and Activation Gases:

Noble gases in the building vent and stack gaseous e61uent are continuously monitored.

The flow rate of the stack is continuously monitored and the building vent eBluent flow rates are calculated once a shift based on the configuration of operating exhaust fans. The vent flow is calculated for each release. Gas grab samples of input streams to the stack are taken and analyzed weekly. Gas grab samples of in-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 of a monthly grab sample for each release point.

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EFFLUENT AND WASTE 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 flow rate data are used weekly to verify that release rate limits were not exceeded. The specific activity concentrations and total volume of gaseous effluent are used on a monthly basis to determine the total curies of each 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 of a quarterly particulate filter composite sample for each release point C. Liquid Effluents
1. The gamma ray emitting radionuclide concentrations are determined for each batch by gamma ray spectroscopy analysis of a grab sample. The allowable release rate is calculated for each batch based upon the known dilution flow. The flow rate of the 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 Liquid Waste Monitoring Sampling and Analysis Program is specified in ODCM Sections 1/2.2.1 and 1/2.2.2.

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0 EFFLUENT AND WASTE DISPOSAL ANNUALREPORT SUPPLEMENTAL INFORMATION 4 1995 IV. Batch guarter uarter Quarter uarter

.A. Liquid Units 1 3

1. Number of batches released Each 41 39 72 85
2. Total time for batch released Minutes 10722 10170 18624 21575
3. Maximum time period for a batch release Minutes 328 318 350 320
4. Average time period for a batch release Minutes 262 261 259 254
5. Minimum time period for a batch release Minutes '60 135 135 196
6. Average stream flow during period of release into a flowing stream Cubic feet per second 72194 17405 31320 58367 B.

'- Gaseous None C. Abnormal/Unplanned Releases Number of

'ype Total Activity Releases Releases (Curies)

Liquid None None Gaseous None None

'n explanation of any liquid or gaseous abnormal/unexplained release shall be documented in the summaty.

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EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUIDEFFLUENTS - SUMMATIONOF ALLRELEASES YEAR 1995 Unit guarter Quarter guarter guarter  % Error A. Fission and Activation Products 1 2 3 4 (Does not include tritium, gases, Alpha)

l. Total Release Curies 6.66E-02 1.37E-01 3.45E-Ol 3.85E-Ol 9
2. Average Diluted Concentration Released During Period pCi/ml 2.74E-09 5.66E-09 5.26E-09 4.56E-09
3. Percent of Applicable Limit B. Tritium
1. Total Releases Curies 2.08E+00 2.36E+00 5.93E+00 5.99E+00 6
2. Average Diluted Concentration Released During Period pCi/ml 8.5SE-08 9.77E-08 9.03E-OS 7.10E-08
3. Percent of Applicable Limit 0/

C. Dissolved and Entrained Noble Gases

1. Total Releases Curies 2.78E-04 6.57E-04 3.19E-03 4.95E-03 8
2. Average Diluted Concentration Released During Period pCi/ml 1.14E-11 2.72E-11 4.86E-11 5.87E-11
3. Percent of Applicable Limit D. Gross Alpha Radioactivity
1. Total Releases Curies ND 48
2. Average Diluted Concentration Released During Period pCi/ml ND E. Volume of Liquid Waste to Discharge Canal (Prior to dilution) Liters 4.66E+06 4.33E+06 8.47E+06 1.03E+07 3 F. Volume of Dilution Water 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 limit is expressed in terms of dose. See Tables 5-8.

t EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUID RELEASES FOR YEAR 1995 - BATCH MODE CURIE

~Iaoto e Quarter Quarter Quarter Quarter (Required by Regulatory (REG) Guide 1.21) 1 2 3 4

1. Ba-140 ND ND ND ND
2. Ce-141
3. Co-58 5.33E-04 1.80E-03 3.38E-03 5.93E-03
4. Co-60 2.22E-02 2.87E-02 2.30E-02 2.45E-02
5. Cr-51 ND 3.65E-03 2.29E-02 2.42E-02
6. Cs-134 1.91E-03 2.68E-03 2.73E-03 1.78E-03
7. Cs-137 2.16E-02 3.14E-02 4.32E-02 3.49E-02

. 8. Fe-59

9. I-131 5.13E-05 4.52E-04 8.96E-04 6.25E-04 10., La-140
11. Mn-54 1.15E-02 1.62E-02 2.16E-02 2.69E-02 Op
12. Mo-99 3.33E-05 2.76E-03 1.30E-02 1.36E-02
13. Nb-95 5.46E-05 8.95E-06
14. Sr-89t'~ 1.99E-04 2.15E-04 7.08E-04 8.96E-03
15. Sr-90"> ND 7.71E-05 ND 9.32E-04
16. Tc-99m 3.33E-05 2.70E-03 1.45E-02 1.57E-02
17. Xe-133 1.85E-04 8.11E-05 6.65E-04 9.84E-04
18. Xe-135 9.25E-05 5.76E-04 2.52E-03 3.94E-03
19. Zn-65 3.47E-03 2.32E-03 7.78E-04 1.06E-04
20. Zr-95 Predicted estimation of releases.

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EFFLUENT AND WASTE DISPOSAL ANNUALREPORT LIQUIDRELEASES FOR YEAR 1995 - BATCH MODE CURIE I~toto e Quarter Quarter Quarter Quarter Others (Not Required by REG Guide 1.21) 1 2 3 4

l. Ag-110m 5.33E-04 1.40E-04 7.24E-04 6.93E-04
2. Co-57 ND 2.46E-05 ND Fe-SS"'.

3.99E-04 3.37E-04 8.85E-03 1.69E-03 I-133 ND 8.77E-04 3.28E-03 3.44E-03

5. Na-24 3.57E-03 4.21E-02 1.83E-01 2.20E-01
6. Nb-97 4.13E-04 1.42E-04 7.44E-04 6.62E-04
7. Ru-103 ND 6.85E-04 3.88E-05
8. Sb-124 2.79E-05
9. Ce-144 ND 1.07E-04 ND
10. Sr-92 1.06E-04 3.23E-05 1.02E-04 1.02E-04
11. Ar-41 2.28E-05
12. Kr-87 ND 7.55E-06 ND
13. Zr-97 1.57E-05 ND
14. Mn-56 ND 1.26E-04 3.35E-04 Predicted estimation of releases.

This section of the Annual Report was prepared principally by D. W. Nix.

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EFFLUENT AND WASTE DISPOSAL ANNUALREPORT GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES YEAR 1995 Unit Quarter Quarter Quarter Quarter % Error 1 2 3 4 A. Fission and Activation Gases

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 of Applicable limit B. Io dines
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 of Applicable Limit C. Particulates 1., '

Particulates with half-lives eight days Ci 1.23E-04 6.70E-05 2.10E-05 2.31E-04 35

2. Average release rate for period pCi/sec 1.58E-05 8.52E-06 2.64E-06 2.91E-05
3. Percent of Applicable limit
4. Gross alpha radioactivity Ci D. Tritium
1. Total release Ci 1.93E+00 2.44E+00 3.16E+00 2.84E+00 21
2. Average release rate for period pCi/sec 2.48E-Ol 3.10E-01 3.98E-Ol 3.57E-01
3. Percent of Applicable Limit Applicable Limits are expressed in terms of dose. See Tables 1-4.

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EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - ELEVATED RELEASE CURIES Quarter Quarter Quarter Quarter 1 2 3 4

1. Fission Gases Kr-85m 8.77E-Ol 2.73E-Ol 8.85E-01 2.17E+00 Kr-85 Kr-87 1.46E+00 Kr-88 4.31E-01 7.23E-02 7.82E-01 3.06E+00 Xe-'133 1.42E+00 6.46E-01 1.39E+00 2.88E+00 Xe-135m 1.46E-01 1.48E-01 4.75E-01 Xe-135 5.21E-02 3.96E-02 2.89E+00 Xe-138 3.38E-01 1.83E-01 9.95E-01 Others (specify)

Ar-41 5.94E-02 1.02E-01 1.17E+00 Xe-137 1.09E+00 Total for Period 3.32E+00 9.91E-01 4.62E+00 1.51E+01

2. Io dines 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

EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - ELEVATED RELEASE CURIES guarter guarter guarter 1 2 4

3. Particulates t ~

Sr-89' 7.74E-06 Sr-90~~

Cs-134 Cs-137 Ba-140 La-140 Others (specify)

Rb-89 4.78E-02 Y-91m 2.06E-04 Sr-91 3.79E-04 Cs-138 1.35E-01 ND 2.7 3E-02 Ba-139 1.90E-03 8.08E-04 6.39E-04 2.94E-02 La-140 ND 4.87E-06 Ba-140 2.27E-05 TOTAL FOR PERIOD 1.36E-O] 8.08E-04 6.39E-04 1.05E-01

4. Tritium 4.88E-02 6.41E-02 9.01E-02 1.08E-01 Includes all nuclides, even those with less than an eight day half-life.

" Predicted estimation of releases.

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EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - GROUND RELEASE CURIES Quarter Quarter Quarter uarter 1 2 3

1. Fission Gases Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 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

EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - GROUND RELEASE CURIE S Quarter Quarter Quarter uarter 1 2 3

3. Particulates 1.22E-05

'r-89"'r-90~

Cs-134 Cs-137 Ba-140 ND La-140 Others (specify)

Co-60 5.82E-06 Total for Period 1.22E-05 5.82E-06 I

4. Tritium 4.72F 05 3.18E-01 6.43E-01 2.68E-01 (1) Include all nuclides even those with less than an eight day half-life.

(2) Predicted estimation of releases.

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0 EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - MIXEDMODE RELEASE S 'URIE Quarter Quarter Quarter uarter 1 2 3

1. Fission Gases Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 Xe-135m Xe-135 3.25E-04 Xe-138 Total for Period 3.25E-04
2. Io dines 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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EFFLUENT AND WASTE DISPOSAL ANNUALREPORT YEAR 1995 GASEOUS EFFLUENTS - MDKDMODE RELEASE

'URIES guarter guarter Quarter uarter 1 2 3

3. Particulates ~ ~

Sr-89' 2.91E-05 Sr-90~ ~

Cs-134 Cs-137 7.55E-06 2.20E-05 1.42E-05 2.81E-05 La-140 Ba-140 2.03E-05 Others (specify)

Mn-54 1.06E-05 8.23E-07 6.81E-06 Cr-51 3.07E-05 Na-24 1.04E-03 Mo-99 , 3.18E-06 4.36E-05 Tc-99m 3.18E-06 4.36E-05 Co-60 6.81E-05 3.20E-05 6.76E-06 1.17E-04 Y-91m 2.93E-04 Ba-139 8.77E-03 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 of releases This section of the Annual Report was prepared principally by D. W. Nix.

DROWNS FERRY NUCLEAR PLANT ANNUALEFFLUENT AND WASTE DISPOSAL REPORT 1995 SOLID WASTE AND IRRADIATEDFUEL Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

T e of Waste Units Amount Error %

a. Spent resins, filter sludges m 1.22E+02 evaporator bottoms, etc. Ci 2.88E+02 +/-25.0 Diy compressible waste, contaminated m3 1.68E+02 equipment, etc. Ci 3.07E+00 +/-25.0
c. Irradiated components, control rod m3 4.19E+Ol drives, shroud head bolts, etc. Ci 2.54E+04 +/25.0
d. Cartridge filters 1113 6.10E+00 Ci 1.04E+02 +/-25.0
2. Estimate of Major Nuclide Composition by Waste Type
a. Spent resins, filter sludges, evaporator bottoms, etc.

Nuclide ~Percents e Activi Curies

1. Cobalt (I) 4.17E+Ol 1.20E+02
2. Cesium137 (I) 1.59E+01 4.57E+Ol
3. Nickel (2) 1.24E+01 3.58E+Ol
4. Manganese54 (I) 9.58E+00 2.76E+Ol
5. Iron55 (2) 9.49E+00 2.73E+01
6. Zinc65 (I) 4.55E+00 1.31E+01
7. Silverl (1) 2.95E+00 8.51E+00
8. Chromium51 (I) 1.68E+00 4.84E+00
9. Cesium134 (1) 9.68E41 2.79E+00
10. Cobalt58 (I) 6.91E41 1.99E+00
11. Other <1.0 3.70E41
b. Dry compressible waste, contaminated equipment, etc.

Nuclide ~Percents e Activi Curies

1. Cobalt60 (2) 4.61E+01 1.42E+00
2. Iron55 (2) 2.92E+01 8.96E41
3. Cesium137 (2) 1.43E+01 4.39E41
4. Manganese54 (2) 6.96E+00 2.14E41
5. Nickel (2) 2.82E+00 8.66E42
6. Other <1.0 1.44E42 E2-16

DROWNS FERRY NUCLEAR PLANT ANNUALEFFLUENT AND WASTE DISPOSAL REPORT 1995 SOLID WASTE AND IRRADIATEDFUEL Solid Waste Shipped OQ'site for Burial or Disposal (Not Irradiated Fuel)

(Continued)

2. Estimate of Major Nuclide Composition by Waste Type (Continued)
c. Irradiated components, control rod drives, shroud head bolts, etc.

Nuclide ~Percenta e Activi Curies

1. Cobalt60 (2) 5.90E+01 1.50E+04
2. Iron55 (2) 3.17E+01 8.05E+03
3. Nickel (2) 5.71E+00 1.45E+03
4. Manganese " (2) 3.46E+00 8.79E+02
5. Nickel59 (2) 3.60E42 9.14E+00 6.- Chromium51 (2) 3.18E42 8.08E+00
7. Other <1.0 2.35E+01
d. Cartridge filters Nuclide ~Percenta e Activi Curies
1. Cobalt 60 (I) 9.41E+01 9.74E+01
2. Iron (2) 1.83E+00 1.90E+00
3. Nickel63 (2) 1.66E+00 1.71EWO
4. Chromium51 (I) 1.00E+00 1.04E+00
5. Cesium137 (I) 6.30E41 6.52E41
6. Manganese54 (I) 1.83E41 1.89E41
7. Other <1.0 6.37E41 (I) Measured (2) Calculated E2-17

BROWNS FERRY NUCLEAR PLANT ANNUALEFFLUENT AND WASTE DISPOSAL REPORT 1995 SOLID WASTE AND IIUUJ)IATEDFUEL Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

(Continued)

3. Solid Waste Disposition Number of Shi ments Mode of Tran ortation Destination 28 Sole Use Truck Chem Nuclear Systems, Inc, Disposal Site, Barnwell, SC Sole Use Truck American Ecology, Oak Ridge, TN 31 Sole Use Truck Scientific Ecology Group, Oak Ridge, TN 16 Sole Use Truck Chem Nuclear Systems, Inc.,

Processing Facility, Barnwell, SC Number of Shi ments Mode of Tran ortation Destination None N/A N/A E2-18

BROWNS FERRY NUCLEAR PLANT ANNUALEFFLUENT AND WASTE DISPOSAL REPORT 1995 SOLID WASTE AND IRRADIATEDFUEL Description of Shipments Number of Type Type Number of Container Waste

~Shi ments Container Quantity A-LSA Containers Volume ~e 32 Strong Tight 120 See Note DAW Container (STC)

Liner/Cask B 1.63 Irradiated Hardware 14 A-LSA 14 5.83 Dewatered Resin 2 HIC/Cask >A-LSA 3.41 Cartridge Filters HIC/Cask >A-LSA 5.83 Dewatered Resin HIC/Cask A-LSA 3.41 Dewatered Resin HIC/Cask >A-LSA 3.41 Dewatered Resin 16 DOT7A A 16 9.10 Control Rod Drives Solidification Agents Used: None Absorbents Used: None NOTE: The 32 shipments of waste packaged in strong tight containers consisted of the following:

T~enf STC Number of Packa es VolumeEachPacka e m 40'Sealand" 13 72.5 20'Sealand" 19 36.3 Metal Box 84 2.66 Metal Box 1 4.08 Metal Box 1 3.12 Metal Box 2 2.89 E2-19

EFFLUENT AND WASTE 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 of radioactive material to the environment from Browns Ferry has been a small fraction of the 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 of the continuous air monitors each shift (BFPER951320).

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