ML20204G103
| ML20204G103 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/30/1988 |
| From: | Maine Yankee |
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| Shared Package | |
| ML20204G096 | List: |
| References | |
| NUDOCS 8810240052 | |
| Download: ML20204G103 (13) | |
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MAINE YANKEE ATOMIC POWER COMPANY SEMIANNUAL EFFLUENT RELEASE REPORT January - June, 1988 l
1.0 INTRODUCTION
Tables 1 through 4 list the recorded radioactive liquid and gaseous effluents and solid waste for the first six months of the year, with data summarized on a quarterly basis. ,
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Appendices A through D indicate the status of reportable items per the requirements of Technical Specifications 3.16.C. 3.17.D. 3.28 A 3.28.8. 4.8.A.
4.13 and 5.9.1.6. ,
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. . *e TABLE 1A Maine Yankee Atomic Power Station Effluent and Waste Discosal Semiannual Report First and Second Ouarters. 1988 Gaseous Effluents - Summation of All Releases 4
Unit Quarter Quarter Est. Total 1st 2nd Error. %
A. Fission and Activation Gases
- 1. Total release Ci 8.87 E-02 2.13 E-02 2.50 E+01
- 2. Averace release rate for neriod uCi/see 1.13 E-02 2.71 E-03
- 3. Percent of reaulatory limit 1 3.43 E-05 8.59 E-06 B. Iodines
- 1. Total Iodine-131 C1 2.17 E-08 3.22 E-08 2.50 E+01
- 2. Averace release rate for eeriod UCi/see 2.76 E-09 4.10 E-09
- 3. Percent of reaulatory limit i 2.42 E-08 3.60 E ,
C. Particulates
- 1. Particulates with T-1/2 1 8 days C1 2.25 E-06 1.13 E-06 2.50 E+01
- 2. Averace release rate for eeriod uCi/see 2.86 E-07 1.44 E-07
- 3. Percent of reaulatorv limit 1 1.26 E-02 6.14 E-03_
- 4. Gross aloha radioactivity C1 1.15 E-08 1.09 E-08
- 0. Tritium
- 1. Total release Ci 1.58 E+00 1.35 E+00 2.50 E.01
- 2. Averaae release rate for eeriod UCi/see 2.01 E-01 1.72 E-01
- 3. Percent of reaulatory limit % 8.8) E-04 7.54 E-04 8510L-OS
TABLE 18 Maine Yankee Atomic Power Station Effluent and Nas.te Discosal Semiannual Recor.t First and Second Ouarters. 1988 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st "no
- 1. Fission Gases Krveton-85 Ci N/D* N/D* 7.53 E-02 N/D*
Krveton-85m Ci N/D* N/D* N/D* N/D*
Krvoton-87 Ci N/D* N/D* N/D* N/D*
Krvoton-88 Ci N/D* N/D* N/D* N/D*
Xenon-133 Ci N/D* N/D* 1.3D E-02 2.07 E-02 Xenon-135 Ci N/D* N/D* 4.24 E-04 5.81 E-04E Xenon-135m Ci N/D* N/D* N/D* N/D*
Xenon-138 Ci N/D* N/D' N/D* N/D*
Xenon-133m Ci N/D* N/D* N/D* N/D*
Arcon-41 Ci N/D* N/D* N/D* N/D*
Xenor-131m Ci _ N/D* N/D* N/D* N/D*
Unidentified Ci N/D* N/D* N/D* N/D*
Total for eeriod Ci N/D* N/D* 8.87 E-02 2.13 E 2. Iodines Iodine-131 Ci N/D* N/D* 2.17 E-08 3.22 E "
Iodine-133 Ci N/D* N/D* 4.54 E-08 6.44 E Iodine-135 Ci N/D* N/D* N/D* N/D*
Total for oeriod Ci N/D* N/D* 6.71 E-0B 9.66 E-0B
- 3. Particulates 4
Strontium-89 Ci N/D* N/D* N/D* N/D*
Strontium-90 Ci N/D* N/D* N/D* N/D* ____
N/D* N/D* N / D;-
Cesium-134 Ci N/D*
1 Ce s i um-137 Ci N/D* N/D* N/D* N/D*
Barium-Lanthanum-140 Cl N/D* N/D* N/D* N/D*
Others Ci N/D* N/D* N/D* N/D*
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- N/D - Not Detected
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TABLE 1C Maine Yankee Atomic Power Statioq Effluent and Maste Disnosal Semiannual Renort First and Second Quarters 198E Gateous Effluents Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the First and Second quarters of 1988.
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. . *o TABLE 2A Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual ReDort First and Second Ouarters. 1988 Liauld Effluents - Summation of All Relea111 Unit Quarter Quarter Est. Total
- 1st 2nd Error. %
A. Fission and Activation Products
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- 1. Total release (not including .
tritium. antes. aleha) Ci 2.19 E-02 1.23 E-02 1.50 E+01
- 2. Average diluted concentration durina ceriod uCi/ml 1.05 E-10 5.96 E-11
- 3. Percent of acolicable limit % 1.15 E-03 1.28 E-03 B. Tritium
- 1. Total release Ci 7.78 E+01 1.24 E+02 1.50 E+01
- 2. Average diluted concentration durina eeriod UC1/ml 3.74 E-07 5.99 E-07.
- 3. Percent of acolicable limit % 1.25 E-02 2.00 E-0Z_
C. Dissolved and Entrained Gases
- 1. Total release Ci 9.22 E-03 6.20 E-03 1.50 E+01
- 2. Average diluted concentration during eeriod uC1/ml 4.43 E-11 2.99 E-11
- 3. Percent of acolicable limit 1 2.21 E-05 1.50 E-05
- 0. Gross Alpha Radioactivity
- - 1. Total release Ci 9.43 i-07 1.95 E-06 1.50 E.0!__
- 2. Average diluted concentration durina ceriod UCi/ml 4.53 E-15 9.42 E-15 E. Volume of waste released (prior to dilution) liters .9.22 E+06 1.22 E+07 1.00 Et01
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F. Volume of dilution water used durina geriod liters 2.08 E+11 2.07 E+11 1_QQ..E+01 1
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TABLE 2B Maine Yankee 1.tomic Power Sta110D Effluent and Haste Disnosal Semiannual Reeort Elett and Second Ouarters. 1988 Linuld Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter i ist 2nd 11.1 2nd i
_ Strontium-89 Ci N/D* N/D* N/D* N/D*
Strontium-90 Ci N/D* N/D* N/D* 7.26 E Cesium-134 C1 N/D* N/D* N/D* 3.97 E Cesium-137 C1 N/D* N/D* _ _ _ _ 2.26_E_-04 2.71 E-03 l Iodine-13) Ci N/D* N/D* 6.78 E-04 6.31 E-04 C1 N/D* N/D* N/D* N/D*
1 Cobalt-58 Cobalt-60 Ci N/D* N/D* 7.35 E-04 1.95 E-03 Ci N/D* N/D* N/D* N/D*
_ Iron-59 N/D*
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_Zine-65 Ci N/D* N/D* N/D*
Ci N/D* N/D* N/D* N/D' Man 9AD11e-54 Chromium-51 Ci N/D' N/D* N/D* N/D*
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l Zi rconium-Niobium-95 Ci N/D* N/D* N/D* N/D*
, Molybdenum-99 Ci N/D* N/D* 1.80 E-05 N/D*
Technetium-99m Ci N/D* N/D* 2.59 E-05 N/D* ,
Barium-Lanthanum-14D Ci N/D* N/D* N/D* N/D*
Ci N /.D* N/0* N/D* N/D* i
_ Cerium-141 Others Iron-55 Ci N/D* N/D* 1.76 E-02 4.87 E-03 i Silver-110m Ci N/D* N/D* 1.99 E-03 9.30 E-04 Antimony-125 Ci N/D* N/p* 6.18 E-04 7.69 E-04 L Unidentified Ci N/D* Nr0* N/D* N/D* -
Total for_ceriod (above)(1)Ci 0.00 E-01 2.19 E-02 1.23 E-02_
1 f s Xenon-133 C1 N/D* N/D* 9.07 E-03 6.09 E t j Xenon-135 Ci N/D* N/D* 1.45 E-04 1.72 E-04 l 4
i l N/D* - Not Detected
- (1) - Total for period does not inciude unidentified in this summation but is l 9
included in Table 2A, Item A1. ,
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TABLE 3 Maine Yankee Atomic Power Station ,
Effluent and Waste Disoosal Semiannual Regant First and Second Ouartert. 1988 Solid Waste and Irradiated Fuel Shiomeq11 A. Solid Haste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*
Unit 6-Month Est. Total Period Error. %
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- 1. Type of Hasts
- a. Spent resins, filter sludges, evaporater m3 10.99 1 10 bottoms. etc. - LSA container **.+++ C1 351.25
- b. Dry compressible waste, contaminated m3 38.83 10 eautement. etc. - LSA container +.++ Ci 46.51
- c. Irradthted*
components, control rods, m3 etc. Ci d. m3 ' '
Ci '
- e. 133 Ci
- 2. Estimate of Major Nuclide Composition (By Type of Haste)***
- a. Cs-134 6% elus or minus 10%
Cs-137 19% olus or minus 10% .
Fe-55 30% olus or minus 10% '
Ni-63 7% olus or minus 10% .
Co-60 29% elus or minus 101 CO-58 3% elus tr.minus 10%
Hn-54 2% olus or minus 10% ;
- b. C1-137 35% olus or minus 10% !
Co-60 18% olus or minus 10% r Co-58 15% olus or minus 10% '
Cs-134 171 elus or minus 10% ,
Ni-63 8% olus or minus 101 Fe-55 5% D1us or minus 10%
i S. Solid Haste Disposition 4
Rymber of Shioments Mode of Transportation Egstination ,
l 11 Trucking over Highway Chem-Nuclear, Barnwell, S.C. l L
B. Irradiated fuel Shipments (Disposition)
+ Container volume equal to 55 gal ons (drums).
++ Container volume equal to 110 ft (boxes). '.
- +++ Container volume equal to 170 ft (liners) (HIC)
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- Solid waste is Class A, as defined in 10CFR61.55. 34.36 m3, 39 Ci ;
- Solid waste is Class B, as defined in 10CFR61.55 10.04 m3, 325 Ci :
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- Solid waste is Class C, as defined in 10CFR61.55 5.42 m3, 34 Ci
- Solidification agent is cement.
- Excluding nuclides with half-ilves less than 12.8 days.
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TABLE 4 Sunnlemental Information
- 1. Reaulatory Limits Maximum Permissible Concentration
- a. Fission and activation gases: 10CFC20; Appendix B. Table 2, Column 1
- c. Particulates .(with half lives greater than 8 days) 10CFR20; Appendix 8. Table 2, Column 1
- d. Liould effluents: 10CFR20; Appendix 8. Table 2, Column 1
- e. Total noble gas concentration 2E-04 uC1/ml
> 2. Average Enerav - Not Aeolicable
- 3. Measurements and Aceroximations of Radioactivity
- a. Fission and Activation Cases Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels determir.ed are assumed coastant for the surveillance interval. The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency.
Batch Discharges - Direct measurements of the waste gas hold-up drums are taken prior to discharge. Containment vents and purges are analyzed by direct measurement of the containment atmosphere at periodic intervals during discharge. ,
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- b. Iodines
. Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal fliter. I l c. Particulates l Primary vent stack particulate tctals are taken from a minimum of weekly j
measurements of an in-line particulate filter.
$ d. Licuid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes.
Each batch release is analyzed for gross beta-gamma, alpha, tritium, ;
dissolved gases, and gamma emitting isotopes prior to discharge.
Composite samples are made of secon'dary and primary system liquid effluents for a quarterly analysis of Strontium,90 and Strontium-89.
Primary system liquid efflutits are also analyzed quarterly for Iron-55. l 1
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4 TABLE 4 (Continued)
- 4. Batch Releases
- 4. .Liouids
- 1. Number of batch releases: 49 i
- 2. Total time period for batch releises: 135 hears, 16 minutes
- 3. Maximum time period for a batch rslease: 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, 15 minutes
- 4. Average time period for batch releases: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 46 minutes ,
- 5. Minimum time period for a batch release: 59 minutes '
- 6. Average steam flow during periods of release of effluents into a flowing stream: N/A :
- 7. Maximum gross release concentration (uC1/ml): 4.05 E-08 l
- b. Gaseous
- 1. Number of batch releases: 9
- 2. Total time period for batch releases: 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 16 r.inutes
- 3. Maximum time period for a batch reltnse: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 10 minutes i
- 4. Average time period for batch releases: 42 minutes
- 5. Minimum time period for a batch release: 7 minutes >
- 6. Maximum gross release rate (uC1/sec): 4.18 E+01
- 5. Abnormal Releases
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There were no abnormal liquid releases during th6 reporting period,
- b. Caseous There were no abnorm &1 gaseous releases during the reporting period.
- 6. On-line Containment Purce On-line containment purge was not employed during the reporting period. Total ,
on-line purge time for 1987 was 107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br /> and 27 minutes.
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APPENDIX A Radioactive Liauid Effluent Monitorina Instruhentation .
Reauirement: Radioactive liquid effluent monitoring iristrdmentation channels are !
required to be operable in ar.cordance with Technical Specification !
3.28.A. With less than the minimum number of channals operable and * '
reasonaole efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.28.A requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report. ;
i Reseense: During this reporting period, two effluent monitors were inoperable in excess of 30 days when required to be operable. l
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' The servicewater monitor was declared inoperable in order to j perform primary calibaration. This effort was dolcyed by the l necessity to design and fabricate a test fixture that would 3
accurately duplicate the inservice geometry. After that was i j accomplished, further delay resulted from the necessity to i specially make a standard source to fit into the test fixture. $
The monitor then was successfully calibrated and returned to ;
service on April 15, 1988.
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- On January 13, 1988, the air ejector monitor failed and was declared inoperable. The detector for t'is monitor is located in a harsh, high moisture environment. As a result, the detectors in the past have had a high failure rate. Actions had r been taken on the most recent previous fal. lure to address the i i problem. Those actions proved to be inadequate; therefore, with j this failure, it was determined that an environmental shield was ,
required. Lead time required to fabricate that shield and !
procure new trarsfer calibration sources delayed the repair.
4 The monitor remained out of service at the end of the reporting l period.
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APPENDIX B Liauid Radwaste Treatment Syst2m Reauirement: Hith radioactive liquid waste being discharged withodt treatment with estimated doses in excess of the limits in Technical Specification 3.17.C.1, a report must be submitted to the Commission in the Semiannual Effluent Release Report for the period. ,
Resoonsu The requirements of Technical Sper.ification 3.17.C.1 were met during this period and, therefore, no report is required.
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APPENDIX C i Gaseous Radwaste Treatment System -
Reauirement: Hith radioactive gaseous waste being discharged without treatment i
with doses in excess of the limits in Technical Specifications 3.18.D.1, a report must be submitted to the Commission in the Semiannual Effluent Release Report for the period.
Resnonse: The requirements of Technical Specification 3.18.0.1 were met during this period and, therefore, no report is required.
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APPENDIX D ,
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' Lower Limit of Detection for Radiolcaical Analyses
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Itvaut rement: Technical Specification 4.13 requires that when unusual circumstances .
I result in LLDs higher than required, the reasons shall be documented !
in the Semiannual Radioactive Effluent Release Report. j
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Reseonte: Analyses were performed in such a manner that the stated LLD's were l achievable under routine conditions. On occasien, with 11guld i i
samples, however, the presence of detected higher energy isotopes caused a compton background elevation. This interference was i sufficient to make some of the specified LLD's in those 11guld !
samples unattainable. This occurred in 8 semples for Zn-65. 5 for !
Fe-59 and 2 for Cs-137. The specified LLD's were attained on all except one gaseous sample. That exception occurred when alternate i primary vent stack sampling had to be utilized, the duration of W.tich ;
was too short to provide samples sufficient to meet the LLD limits, t f
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