ML20012G447
| ML20012G447 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/31/1992 |
| From: | Hebert J Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| JRH-93-36, MN-93-21, NUDOCS 9303020453 | |
| Download: ML20012G447 (15) | |
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MaineYankee RELIABLE ELECTRIOITY FOR MAINE SINCE 1972 ED! SON DRIVE AUGUSTA. MAINE 04330. (207) 622 4E<68 r
February 25, 1993 MN-93-21 JRH-93-36 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, DC 20555
Reference:
(a)
License No. DPR-36 (Docket No. 50-309)
Subject:
Semiannual Radioactive Effluent Release Report Gentlemen:
Enclosed, in accordance with the requirements of Maine Yankee Technical Specification 5.9.1.6, is the Maine Yankee Semiannual Effluent Release Report for the period July to December 1992.
Please contact John Arnold if you have questions or comments.
Very truly yours,
-nq h.
James R. Hebert, Manager Licensing & Engineering Support Department JHA/ jag Enclosures c:
Mr. Charles S. Marschall Mr. E. H. Trottier Mr. Patrick J. Dostie Mr. Thomas T. Martin Mr. Donald Hoxie - DHE Mr. Allan Prysunka - DEP - Oil & Hazardous Waste American Nuclear Insurers 1
020055 m,- -
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9303020453 921231
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PDR ADDCK 05000309 R
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f MAINE YANKEE ATOMIC POWER COMPANY SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1992
1.0 INTRODUCTION
Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid -
l effluents, respectively, for the third and fourth quarters of'1992. Table 3 summarizes the solid waste shipped off-site for burial or disposal during the second half of 1992. Table 4 contains supplementary information.
Appendices A throuah D indicate the status of reportable items per the requirements of Offsite Dose Calculation Manual (ODCM) sections 2.1. 5, 2. 2.6,12..3, 3
2.3.4, 2.5 and Appendix C.
No changes to the ODCM were issued during this period.
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TABLE 1A i
Baine Yankee Atomic Power Station
[ffluent and Waste Disposal Semiannual Report Third and Fourth Ouarters. 1992 Gaseous Effluents - Summation of All Releases Unit Quarter Quarter Est. Total i
3rd 4th Error. %
A. Fission and Activation Gases
- 1. Total release Ci 1.12 E-01 8.67 E-01 2.50 E+01
- 2. Averaae release rate for period uCi/sec 1.42 E-02 1.10 E-Ol_
- 3. Percent of reaulatory limit 5.23 E-05 4.83 E-04 B. Iodines
- 1. Total Iodine-131 Ci 5.97 E-06 1.01 E-05 2.50 E+01
- 2. Averaae release rate for period uCi/sec 7.59 E-07 1.28 E-06
- 3. Percent of reaulatory limit 6.66 E-06 1.13 E-05 C. Particulates
- 1. Particulates with T-1/2 > 8 days Ci 8.70 E-06 2.27 E-05 2.50 E401
- 2. Averaae release rate for period uCi/sec 1.11 E-06 2.89 E-06 l
- 3. Percent of reculatory limit 2.36 E-06 5.23 E-06
- 4. Gross alpha radioactivity Ci 2.71 E-08 4.20 E-08 D. Tritium
- 1. Total release Ci 6.86 E-01 5.66 E-01 2.50 E+01
- 2. Averaae release rate for period uCi/sec 8.72 E-02 7.20 E-02
- 3. Percent of reaulatory limit 3.83 E-04 3.16 E-04 ON/D - Not Detected i
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TABLE 18 Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1992 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th
- 1. Fission Gases Krvoton-85 Ci N/D*
N/D*
N/D*
N/D*
KrVDton-85m Ci 2.47 E-06 1.97 E-04 N/D*
N/D*
t Krypton-87 Ci 3.97 E-06 1.82 E-04 N/D*
N/D*
Krvoton-88 Ci N/D*
9.90 E-06 N/D*
N/D*
Xenon-133 Ci 9.94 E-02 6.92 E-01 2.84 E-04 2.58 E-04 Xenon-135 Ci 1.18 E-02 1.68 E-01 1.08 E-05 8.50 E-06 Xenon-135m Ci 1.46 E-04 5.08 E-03 N/D*
N/D*
Xenon-138 Ci N/D*
8.47 E-04 N/D*
N/D*
Xenon-133m Ci N/D*
N/D*
N/D*
N/D*
Aroon-41 Ci N/D*
5.73 E-04 5.95 E-06 6.75 E-06 r
Xenon-131m Ci N/D*
N/D*
N/D*
N/D*
l Unidentified Ci N/D*
N/D*
N/D*
N/D*
Total for Deriod Ci 1.11 E-01 8.67 E-01 3.01 E-04 2.73 E-04 i
- 2. lodines Iodine-131 Ci 5.96 E-06 1.01 E-05 1.09 E-08 1.60 E-08 lodine-133 Ci 4.05 E-05 5.58 E-05 2.17 E-08 2.44 E-08 lodine-135 Ci N/D*
N/D*
N/D*
N/D*
i Total for period Ci 4.65 E-05 6.59 E-05 3.26 E-08 4.04 E-08
- 3. Particulates Strontium-89 Ci N/D*
N/D*
N/D*
N/D*
Strontium-90 Ci N/D*
N/D*
N/D*
N/D*
Cesium-134 Ci N/D*
3.57 E-07 N/D*
N/D*
l Cesium-137 Ci 5.95 E-06 2.15 E-05 N/D*
N/D*
l Barium-Lanthanum-140 Ci N/D*
N/D*
N/D*
N/D*
Zinc-65 Ci N/D*
N/D*
N/D*
N/D*
Cobalt-58 Ci N/D*
N/D*
N/D*
N/D*
l Cobalt-60 Ci 2.75 E-06 8.69 E-07 N/D*
N/D*
t Others-Ci CN/D - Not Detected Le \\9 hm\\9371 I
TABLE IC Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report Third and Fourth Ouarters 1992 Gaseous Effluents - Ground Level Releases 1
There were no routine measured ground level continuous or batch mode gaseous releases during the third and fourth quarters of 1992.
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c TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters.1992 Liouid Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3rd 4th Error. %
A. Fission and Activation Products
- 1. Total release (not including tritium. aases. alpha)
Ci 1.55 E-02 1.19 E-02 1.50 E+01
- 2. Average diluted concentration durina Deriod uCi/ml 7.95 E-?1 5.52 E-Il
- 3. Percent of aoolicable limit 4.13 E-04 4.03 E-04 B. Tritium
- 1. Total release Ci 7.12 E+01 1.00 E402 1.50 E+01 i
- 2. Average diluted concentration durina period uCi/ml 3.65 E-07 4.63 E-07 l
- 3. Percent of applicable limit 1.21 E-02 1.54 E-02 C. Dissolved and Entrained Gases
- 1. Total release Ci 2.84 E-03 5.01 E-03 1.50 E+01
- 2. Average diluted concentration durina period uti/ml 1.45 E-11 2.32 E-11
- 3. Percent of acolicable limit 7.27 E-06 1.16 E-05 D. Gross Alpha Radioactivity
- 1. Total release Ci N/D*
4.25 E-07 1.50 E+01
- 2. Average diluted concentration durino period uti/ml N/D*
1.97 E-15 l
i E. Volume of waste released (prior to dilution) 1.i t ers 2.07 E407 1.69 E+07 1.00 E+01 I
F. Volume of dilution water used durina period liters 1.95 E+11 2.16 E+11 1.00 E+01 i
cN/D - Hot Detected f
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TABLE 2B Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report First and Second Ouarters. 1992 Liouid Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th Strontium-89 Ci N/D*
N/D*
N/D*
N/D*
Strontium-90 Ci N/D*
N/D*
N/D*
N/D*
Cesium-134 Ci N/D*
N/D*
4.40 E-04 7.59 E-04 Cesium-137 Ci N/D*
N/D*
1.63 E-03 2.63 E-03 Iodine-131 Ci N/D*
N/D*
1.18 E-04 1.60 E-04 Cobalt-58 Ci N/D*
N/D*
5.22 E-04 1.09 E-03 Cobalt-60 Ci 4.73 E-05 N/D*
1.54 E-03 1.80 E-03 1ron-59 Ci N/D*
N/D*
N/D' N/D*
Zinc-65 Ci N/D*
N/D*
N/D*
6.25 E-06 Manaanese-54 Ci N/D*
N/D*
N/D*
2.34 E-05 Chromium-51 Ci N/D*
N/D*
1.45 E-05 5.87 E-04 Zirconium-Niobium-95 Ci N/D*
N/D*
N/D*
1.01 E-04 Molybdenum-99 Ci N/D*
N/D*
N/D*
N/D*
Technetium-99m Ci N/D*
2.35 E-08 N/D*
N/D*
Barium-Lanthanum-140 Ci N/D*
N/D*
4.49 E-06 2.13 E-05 i
Cerium-141 Ci N/D*
1.84 E-06 2.40 E-06 N/D*
Others-Iron-55 Ci N/D*
N/D*
4.27 E-03 2.79 E-03 Iodine-133 Ci N/D*
N/D*
4.61 E-06 N/D*
Antimony-122 Ci N/D*
N/D*
5.42 E-06 2.99 E-06 Antimony-124 Ci N/D*
N/D*
2.60 E-04 2.79 E-04 Antimony-125 Ci N/D*
N/D*
9.67 E-04 1.11 E-03 Silver-110M Ci N/D*
N/D*
5.61 E-03 5.19 E-04 Tin-113 Ci N/D*
N/D*
2.06 E-06 3.44 E-05 Mancanese-56 Ci 5.59 E-06 N/D*
N/D*
N/D*
Sodium-24 Ci 4.84 E-05 N/D*
N/D*
N/D*
Ruthenium-103 Ci N/D*
N/D*
N/D*
1.16 E-05 Unidentified Ci N/D*
N/D*
N/D*
N/D*
Total for period (above)(1) Ci 1.01 E-04 1.86 E-06 1.54 E-02 1.19 E-02 Xenon-133 Ci 1.11 E-05 N/D*
2.73 E-03 4.26 E-03 Xenon-135 Ci 9.98 E-06 9.14 E-06 6.53 E-05 1.42 E-04 Xenon-133m Ci N/D*
N/D*
2.00 E-05 N/D*
Xenon-135m Ci N/D*
N/D*
N/D*
1.59 E-05 Krypton-85 Ci N/D*
5.87 E-04 N/D*
N/D*
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TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Report i
Second Half.1992 Solid Waste and Irradiated Fuel Shioments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)
Unit 6-Month Est. Total Period Error. %
- 1. Type of Waste
- a. Spent resins, filter sludges, etc.
m' 41.6 i
Ci' 4.93 E+02 25
- b. Dry compressible waste, contaminated m'
110.4 eouipment. DAW. cement.
Ci' 7.26 E-01 25
- c. Irradiated components, control rods, m*
1.7 etc.
Ci' 7.54 E+03 25
- d. Other Waste: Oil Solvent m'
l.05 Ci' l.18 E-01 25 l
i
- 2. Estimate of major nuclide composition (by type of waste)*
- a. Ni-63 39.8%
1.97 E+02 l-Cs-137 26.8%
1.32 E+02 Co-60 21.4%
1.06 E+02 i
Fe-55 4.9%
2.40 E+01 1
Cs-134 3.6%
1.77 E+01 Co-58 2.1%
1.02 E401
- b. Co-60 39.2%
2.78 E-01 Fe-55 30.2%
2.14 E-01 Ni-63 19.2%
1.36 E-01 Cs-137 8.6%
6.13 E-02 Co-58 1.11%
7.86 E-03 i
Cs-134 1.44%
1.02 E-02
- c. Co-60 51.5%
3.88 E+03 Fe-55 28.4%
2.14 E403 H-3 11.7%
8.79 E+02 Ni-63 7.02%
5.29 E+02
- d. Co-60 95.5%
1.09 E-01 H-3 3.3%
3.7 E-03 t
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TA3LE 3 (Continued) 3.. Solid' Waste Disposition Number of Shioments Mode of Transoortation Destination 14 Trucking over highway Chem-Nuclear, Barnwell, S.C.
4 Trucking over highway Quaucex, Oak Ridge, TN" 4
Trucking over highway Scientific Ecology Group (SEG), Oak Ridge, TN*
1 Trucking over highway DSSI, Kingston, TN B. Irradiated Fuel Shipments (Disposition): None shipped Additional 0DCM Appendix C requirements.
Solid Waste Class" Volume (m')
Est. Activity (Ci)
Est. Total Error A
134.2 5.96 E0
+/- 25%
B 24.2 4.07 E+02
+/- 25%
C 5.8 7.26 E+03
+/- 25%
Package Container Tvoe Volume (m')
B-88 Strong Tight Container 2.9 55 gal. Drum (17H)
Strong Tight Container 0.2 85 gal. Drum Strong Tight Container 0.3 14-195 Liner Steel Liner 5.9 Sealand Strong Tight Container 38.3 Sealand Strong Tight Container 76.6 Small Overpack High Integrity Container 0.8 Medium Overpack High Integrity Container 1.1 Huhic-120 High Integrity Container 4.5 CNS-355 Steel Liner 1.6
- Estimated
- Excluding nuclides whose percent abundance is less than one percent.
- Processor, Waste is intermittently shipped for disposal.
' As defined by 10 CFR 61.55.
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TABLE 4 Sucolemental Information l
1.
Reaulatory Limits Maximum Permissible Concentration a.
Fission and activation gases:
10CFR20; Appendix B, Table 2, Column 1 b.
10CFR20; Appendix B, Table 2, Column I c.
Particulates, (with half l
lives greater than 8 days) 10CFR20; Appendix B, Table 2, Column 1 l
d.
Liquid effluents:
10CFR20; Appendix B, Table 2, Column 1 e.
Total noble gas concentration 2E-04 uti/ml 2.
Averaae Enerav - Not Applicable 3.
Measurements and Approximations of Radioactivity a.
Fission and Activation Cases Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels determined are assumed constant 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.
b.
Iodines Primary vent stack iodine totals are taken from a minimum of weekly measurements l
of an in-line charcoal filter.
c.
Particulates Primary vent stack particulate totals are taken from a minimum of weekly measurements of an in-line particulate filter.
d.
Liauid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross i
beta-gamma, alpha, tritium, dissolved gases, and gamma emitting isotopes.
Each batch release is analyzed for gross beta-gamma, alpha, tritium, dissolved i
gases, and gamma emitting isotopes prior to discharge.
Composite samples are made of secondary and primary system liquid effluents for a quarterly analysis of Strontium-90 and Strontium-89.
Primary system liquid effluents are also analyzed quarterly for Iron-55.
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i TABLE 4 l
(Continued) 4..
Batch Releases i
a.
Liouids l
1.
Number of batch releases: 41 2.
Total time period for batch releases:
152 hours0.00176 days <br />0.0422 hours <br />2.513228e-4 weeks <br />5.7836e-5 months <br />, 57 minutes 3.
Maximum time period for a batch release: 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> 4.
Average time period for batch releases:
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 44 minutes 5.
Minimum time period for a batch release:
I hour, 9 minutes 6.
Average stream flow during periods of release of effluents into a flowing stream: N/A 7.
Maximum gross release concentration (uCi/ml): 7.01 E-08 b.
Gaseous i
1.
Number of batch releases:
11 2.
Total time period for batch releases:
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 49 minutes 3.
Maximum time period for a batch release:
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 19 minutes 4.
Average time period for batch releases:
48 minutes 5.
Minimum time period for a batch release:
15 minutes 6.
Maximum gross release rate (uci/sec):
1.18 E-01 5.
Unplanned Releases a.
Liouid There were no abnormal liquid releases during the reporting period.
b.
Gaseous There were no abnormal gaseous releases during the reporting period.
6.
On-Line Containment Purce On-line containment purge was not utilized during the reporting period. Total time that on-line purge was employed during 1992 was 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />, 47 n.inutes.
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APPENDIX A Radioactive Effluent Monitoring _ Instrumentation Reauirement:
Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Sections 2.3.3 and 2.3.4.
With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, ODCM Sections 2.3.3 and 2.3.4 requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.
Response
The requirements of ODCM Sections 2.3.3 and 2.3.4, governing operability of
[
radioactive effluent monitoring instrumentation, were met for this reporting period and no report is required.
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APPENDIX B Liouid Radwaste Treatment System Reauirement:
With radioactive liquid waste being discharged without treatment with estimated doses in excess of the limits in ODCM Section 2.1.5, a report must be submitted to the Commission in the Semiannual Effluent Release i
Report for the period.
Response
The requirements of ODCM Section 2.1.5 were met during this period and, therefore, no report is required.
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i APPENDIX C Gaseous Radwaste Treatment System Reouirement:
With radioactive gaseous waste being discharged without treatment with I
doses in excess of the limits in ODCM Section 2.2.6, a report must be submitted to the Commission in the Semiannual Effluent Release Report for the period.
Response
The requirements of ODCM Section 2.2.6 were met during this period and, therefore, no report is required.
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APPENDIX D Lower Limit of Detection for Radioloaical Analyses Reouirement:
ODCH Section 2.5 requires that when unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.
Response
All samples were counted in such a manner as to satisfy the specified a priori lower limits of detection.
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