ML20236D384
| ML20236D384 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/31/1988 |
| From: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BYR-89-35, NUDOCS 8903230078 | |
| Download: ML20236D384 (21) | |
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EFFLUENT AND WASTE DISPOSAL SFNIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS, 1988 i
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Yankee Atomic Electric Company Rowe, Massachusetts 2990T 8903230078 881231
{DR ADOCK 05000029
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Yankee Atomic Electric Company, Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report-Third and Fourth Quarters, 1988 Gaseous Effluents - Summation of All Releases
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Unit Quarter Quarter Est. Total -i n 3 4 Error, %~
A. Fission and Activation Gases 1
! 1. Total release Ci 5.39E+01 3.79E+01 5.50E+01 l l 2. Average release rate for period uCi/sec 6.86E+00 4.82E+00
- 3. Percent of Tech. Spec. J imit (1)(4) % 4.84E-01 1.78E-01 !
I B. Iodines ~ )
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- 1. Total Iodine-131 Ci 5.91E-06 4.01E-05 2.50E+01
- 2. Average release rate for period uCi/sec 7.51E-07 5.10E-06 3.-Percent of Tech. Spec. limit (2)(4) % 7.24E-01 5.90E+00 .
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1 C. Particulate I
- 1. Particulate with T-1/2 > 8 days C1 3.72E-06 1.32E-06 3.00E+01 ,
- 2. Average release rate for period uCi/sec 4.73E-07 1.68E-07
- 3. Percent of Tech. Spec. limit % (3) (3)
- 4. Gross alpha radioactivity C1 3.00E-08 9.00E-09 D. Tritium
- 1. Total release Ci 9.40E-01 1.09E+00 23.00E+01 ,
- 2. Average release rate for period uCi/sec 1.20E-01 1.39E-01 l l 3. Percent of Tech. Spec. limit % (3)- (3) l l
l (1) Technical Specification 3.11.2.2.a for gamma air _ dose. Percent values for Technical Specification 3.11.2.2.b for beta air dose are approximately the same.
(2) Technical Specification 3.11.2.3.a for dose from I-131, tritium, and radionuclides in particulate form.
(3) Per Technical Specification 3.11.2.3, dose contribution from tritium and particulate are included with I-131 above in Part B.
(4) Percent of Technical Specification, Limit is based on conservative plant quarterly dose determinations. These values will be upr'ated pending issuance l' of the supplemental report which will include the annual dose summary.
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. . IMLE_lH Yankee Atomic Electric Companya_Rowe. Massachusetts Effluent _and_Wanic_Dispnaal Semiannual _ Rep. ort Third and Fourth Quarters. 1988 Sageous Effluents - Elevated Release Continuana_Mosie Batch Mode Nuclides Released Mnit_ Quarter Quarter Quarter Quarter 3 4 3* 4
- 1. Fisalon_Daats Krypton-85 C1 2.89E-02 3.37E-01 3.67E1QQ__
Kryplon-85m C1 6.12E-01 1.03E-01 1.35E-03
___Krypinn-87 Ci 5.10E-01 9.34E-02 <1.25E-02 Krypton-88 C1 1.09E+00 1.83E-01 <1.33E-02 Xenonel)3 C1 2.71E+Q1 1.84E+01 7.74E+00 Xenon-135 C1 1.17E+01 2.45E+00 1.97E-01 Xenon-133m C1 1.15E+01 3.14E+00 <8.02E-03
. Xenon-138 Ci 2.65E-01 1.95E-02 <1.23E-02
___Kenon_-133m Ci 6.12E-01 2.01E-01 4.46E-02
___ Argon-37 Ci 9.16E-02 1.70E-01 3.40E-01
___ Argon-41 C1 3.33E-01 5.58E-02 <5.06E-03 Carbon-14 C1 5.05E-03 6.23E-02 5.60E-01 Xenon-131m C1 6.55E-03 1.08E-01 1.08E-02 i Unidentified Ci l
Total for period Ci 5.39E+01 2.53E+01 1.26E+01 l
l 2. Iodines j Iqdine-131 Ci 5.91E-06 2.29E-05 1.72E-05 !
l Iodine-133 C1 1.16E-05 7.52E-07 5.68E-07 l l Iodine-135 Ci <6.96E-07 <4.51E-08 <3.41E-08 l Total for period Ci 1.75E-05 2.37E-05 1.78E-05 at_Patticulates .
___Sitantium:89 C1 <2.77E-07 <2.27E-0] <1.71E-07 Strontium-90 Ci <2.04E-08 <7.17E-08 <5.41E-08 j Cesium-134 Ci <2.71E-07 <5.99E-07 <4.52E-07 Cealumsl37 C1 4.17E-07 2.01E-07 1.51E-07 Barium:Lan.thanum-140 C1 <8.12E-07 <1.73E-06 <1.31E-06 0
___line-65 Ci <iti&E-07 <1.40E-06 <1.06E-06 l Cohalt-58 Ci <2.93E-07 <6.50E-07 <4.90E-07 Cohal t-60 C1 3.30E-06 5.51E-07 4.11E-07 Iran-59 Ci <5.BfE-07 <1.31E-06 <9.85E-07 Chromium-51 Ci LL.65E-06 <3.56E-06 <2.69E-06 Zitcnnium:Hiobium-95 Ci <4.78E-07 <1.03E-06 <7.74E-07 )
Cerium-141 C1 <2.19E-07 <4.85E-07 <3.66E-07 l Cetium-144 Ci <9.40E-07 <2.09E-06 <1.58E-06 !
___Antimonyrl24 Ci <2.58E-07 (6.04E-07 <4.56E-07 l Manganeae-54 Ci <2.89E-07 (6.78E-07 <5.12E-07 i Silver:110m C1 <2.65E-07 <5.63E-07 <4.25E-07 l
___Molyhdenum-99 Ci <ttE6E-06 <3tB5E-06 <2.90E-06 !
Ruthenium-103 C1 <2.29E-07 <4.74E-07 <3.57E-07 l l Tatal_for_ period C1 3.72E-06 7 12E-07 5.66E-07 j
- There were no batch mode releases during this reporting period. j
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se- , ~n IABLE 10 Xankie Atomic Electric Company. Rowe. Massachusetts Elflugnt and Waste Disposal Semiannual Report Third and Fourth Ouarters. 1988 Gaseous Effluents - Ground
- Level Releases-There were no routine measured ground level continuous or batch mode. gaseous releases during the third or: fourth quarters of 1988.
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TABLE 2A Yankee _ Atomic _ Electric Company. Rowe. Massachusetts Efiluent and Waale Disposal Semiannual _ Report Ihlid and Fourth Ouarters. 1988 Li, quid Effluents - Summation of All Releaseg Unit Quarter Quarter Est. Total 3 4 Error. %___
A. Fission and Activation Products
- 1. Total release (not including tritium, gases. alpha) C1 3.04E-02 8.72E-03 2.00E+01
- 2. Average diluted concentration during_perind uCilG1 4.90E-10 2.75E-10
- 3. Pergent of app 1* cable limit (1) % 3.46E-04 2.20E-05 B. Tritium
- 1. Total rele.ase C1 6.62E+01 1.88E+01 1.00E+01
- 2. Average diluted concentration during_ECrlod uC1/ml 1.07E-06 5.93E-07
- 3. Percent of ap.plicable limit (1) % 3.57E-02 1.98E-02 C. Dissolved and Entrained Gases
- 1. Total release Ci 3.42E-02 1.84E-02 2.00E+01
- 2. Average diluted concentration during_p.eriod uC1/mi 5.51E-10 5.8QE-1Q_
- 3. Percent of applicable limit (2) % 2.76E-04 2.90E-04 D. Gross Alpha Radioactivity l _Iolal_ release i C1 6.97E-08 <1.97E-06 3.50E+01 E. Volume of waste released (prior to
___ dilution) liters 6.98E+06 4.67E+06 3.00E+01 F. Volume of dilution water used during_ period liters 6.20E+10 3.17E+10 7.00E+00 (1) Concentration limits specified in 10CFR, Part 20, Appendix B, Table II, Column 2 (Technical Specification 3.11.1.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.
(2) Concentration limits for dissolved and entrained noble gases is 2E-04 microcuries/ml (Technical Specification 3.11.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.
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TABLE 2B Yankee Atomic Electric Company,-Rowe, Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters, 1988 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3 4 3 4 Strontium-89 Ci (2.20E-04 <1.42E-04 <2.37E-05 <1.32E-05 Strontium-90 Ci (3.38E-05 <2.23E-05 <6.50E-06 <4.88E-06 Cesium-134 Ci 2.51E-06 3.91E-05 3.85E-04 1.52E-04 Cesium-137 Ci 5.53E-06 6.74E-05 4.27E-04 1.89E-04 Iodine-131 Ci (2.08E-05 (1.31E-05 3.34E-05 1.96E-04 Cobalt-58 Ci <2.35E-05 <1.31E-05 <8.10E-06 <9.05E-06 Cobalt-60 Ci 1.70E-05 6.18E-06 2.39E-05 3.96E-05 Iron-59 Ci <4.59E-05 <2.71E-05 <1.50E-05 <1.70E-05 Zinc-65 Ci <5.04E-05 <2.88E-05 <1.71E-05 <1.89E-05 Manganese-54 C1 1.92E-06 <1.34E-05 <8.38E-06 3.66E-06 l Chromium-51 Ci (1.72E-04 <1.05E-04 <9.94E-05 <8.38E-05 Zirconium-Niobium-95 Ci <3.92E-05 <2.31E-05 <1.49E-05 <1.53E-05 )
Molybdenum-99 Ci <1.65E-04 <9.65E-05 <6.29E-05 <6.23E-05 ^
, Technetium-99m Ci 1.57E-06 2.89E-06 <1.06E-05 <9.03E-06 l Barium-Lanthanum-140 Ci <7.40E-05 <4.51E-05 <4.30E-05 <3.60E-05 l Cerium-141 Ci <2.99E-05 <1.77E-05 <1.70E-05 <1.44E-05 Ruthenium-103 Ci <2.16E-05 <1.31E-05 <1.23E-05 <1.01E-05 Cerium-144 Ci <1.36E-04 <8.15E-05 <7.84E-05 <6.52E-05 Iodine-133 Ci <2.15E-05 <1.32E-05 1.10E-06 <1.03E-05 Selenium-75 Ci <2.40E-05 <1.43E-05 <1.34E-05 <1.16E-05 Silver-110m Ci <2.23E-05 <1.36E-05 <1.02E-05 <1.01E-05 Antimony-124 Ci <2.09E-05 <1.36E-05 1.76E-06 <1.31E-05 Carbon-14 C1 - -
2.94E-02 6.94E-03 Iron-55 Ci <5.13E-04 <4.04E-04 1.50E-04 1.08E-03 Cesium-136 Ci <2.24E-05 <1.27E-05 (7.86E-06 <8.E6E-06 Antimony-125 Ci <5.73E-05 <3.71E-05 <3.83E-05 <3.07E-05 Unidentified Ci Total for period (above) Ci 2.85E-05 1.16E-04 3.04E-02 8.60E-03 Xenon-133 Ci 4.03E-06 <3.54E-05 2.37E-02 1.44E-02 Xenon-135 C1 1.30E-03 (1.08E-05 6.95E-05 5.41E-06 l Xenon-131m Ci (7.53E-04 <4.54E-04 8.98E-04 4.41E-04 l
Xenon-133m C1 <1.44E-04 <8.64E-05 1.01E-04 2.60E-05 Krypton-85 Ci <7.64E-03 <4.18E-03 8.12E-03 3.52E-03 2990T l
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-TABLE 3 Yankee Atomic Electric Company Rowe, Massachusetts Effluent and Waste Disposal Semiannual-Report Third and Fourth Quarters, 1988 Solid Waste and Irradiated Fuel Shipmento A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)
Unit 6-Month Est. Total i Period Error, %
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- 1. Type of Waste
- a. Evaporator bottoms *, Class A waste, ed 1.70E+01 l LSA container, 55 gallon (drums) Ci 3.05E+00 3.00E+01' j
- b. Dry compressible waste, contaminated m3 6.54E+01 J equipment, etc., Class A waste, Ci 9.15E-01 zl.00E+02. l' LSA, 105 ft3 (boxes)
- c. Irradiated components, control rods, m3 3.25E+00 etc., Class C waste, STL LIN HIC, Ci 8.81E+03 5.00E+01 57.4 ft3
- d. Dewatered spent resin, Class B waste, m3 3.40E+00 Poly HIC, 120.3 ft3 Ci 4.08E+01 5.00E+01
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- 2. Estimate of Major Nuclide Composition (By. Type of Waste)**
Cesium-137 2.09E+01% Niobium-95 2.77E+00% Cesium-137 5.86E+01% 1 Iron-55 1.91E+01% Nickel-63 2.05E+00% Cesium-134 2.00E+01%
Cesium-134 1.78E+01% Iron-59 1.63E+00% Iron-55 6.67E+00%
Cobalt-60 3.08E+00% Manganese-54 1.11E+00% Cobalt-60 6.03E+00%
Nickel-63 1.64E+00% Nickel-63 3.73E+00%
Niobium-95 1.40E+00% c. Silver-110m 3.82E+01% Strontium-90 1.98E+00% )
Iron-55 2.74E+01% Manganese-54 1.38E+00%
- b. Cesium-137 3.23E+01% Cobalt-60 2.43E+01% Cerium-144 1.15E+00%
Cesium-134 2.97E+01% Nickel-63 6.30E+00%
Iron-55 2.65E+01% Antimony-125 3.25E+00%
- 3. Solid Waste Disposition ,
Number of Shipments Mode of Transportation Destination 7 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None
- Solidification agent is cement.
- Excluding nuclides with half-lives less than 12.8 days.
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APPENDIX A Radia&ctive Liquid Effluent Monitoring' Instrumentation Raguirsment: . Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance'with Technical 'I l
With less than the minimum number of Specification 3.3.3.6.
channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.3.3.6.b requires an explanation for the delay in correcting the inoperability in the j 1
next Semiannual Effluent Release Report.
Reaponse: Since'the requirements of Technical Specification 3.3.3.6 ,,
governing the operability of radioactive liquid effluent I monitoring instrumentation were met for this reporting period, ]
no response is required.
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APPENDIX B Radioactive faseous Effluent Monitnring Instrumentation Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.7. 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, Technical Specification 3.3.3.7.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.
Reaponte: Since the requirements of Technical Specification 3.3.3.7 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required.
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1 APPENDIX C f
Liquid Holdup Tanks-Requirement: Technical Specification 3.11.1.4 limits lthe quantity of radioactive material contained in any outside temporary tank.
With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification:
3.11.1.4, a description of the events leading to-this condition-is required in the next Semiannual Effluent Release Report.
Response: The limits of Technical Specification 3.11.1.4 were not exceeded during this reporting period.
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e APPENDIX D.
Radiological Environmental Monitoring Pronram Requirement: The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.4.12.1. With milk or fresh leafy vegetation samples no longer available from one or more of the required sampic locations, Technical Specification 3.4.12.1.c requires the identification of the new location (s) for obtaining replacement sample (s) in the next Semiannual Effluent Release Report and' inclusion of revised Off-Site Dose Calculation Manual figure (s) and table (s) reflecting the new location (s).
Reapanan: All required milk and fresh leafy vegetation samples were available during this reporting period.
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APPENDIX E Land Use Census Requirement: A land use census is conducted in accordance with Technical Specification 3.12.2. With a land use census identifying a.
location (s) which yields at least a.20 percent greater dose or dose commitment than the values currently being calculated ~in Technical Specification 4.11.2.3, Technical Specification 3.12.2.a requires the identification of the new location (s) in the next Semiannual Effluent Release Report.
Response: The land use census for this reporting period did not identify E any locations yielding at least a 20 percent-greater dose or dose commitment than the values currently being' calculated in Technical Specification 4.11.2.3.
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Requirement: With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from which samples are currently being obtained in accordance with Technical Specification 3.12.1, Technical Specification-3.12.2.b requires that the location (s) be added to the program if l permission from the owner to collect samples can be obtained and if sufficient sample volume is available. The identification of the new location (s) is required in the next Semiannual Effluent Release Report.
Responan: No changes were made in the Radiological Environmental Monitoring Program as a result of the 1988 land use census.
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v APPENDIX F 1 Process Control Progr_mn i
Re.quirement: Technical Specification 6.14.1 requires that licensee initiated changes to the Process Control Program be submitted to the Con: mission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made.
Response: There was no licensee initiated change (s) to the Process Control.. j l
Program during this reporting period. ,
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6 APPENDIX G Off-Sits _ Damp Calculation Manual' Requirement: Technical Specification 6.15.2 requires that licensee initiated changes to the Off-Site Dose Calculation Manual be submitted to the Commission in the Semiannual-Radioactive Effluent Release Report for the period in which the change (s) was made effective.
Responsg: There were no licensee initiated changes to the Off-Site Dose Calculation Manual during this reporting period.
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APPENDIX H 'j
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Radioactive Liquid. Gaseous. and Solid Waste Treatment Systems 1
,I Requirement: Technical Specification 6.16.1 requires that. licensee initiated .
major changes to the radioactive waste-systems (liquid, gaseous, and solid) be reported to the Commission in the- Semiannual I
Radioactive Effluent Release Report for-the period in which the i evaluation was reviewed by the Plant Operation Review Committee.
Reaganan: There were no licensee initiated major changes to the !
radioactive waste systems (liquid, gaseous, and solid) during this reporting period.
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APPENDIX I
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Supplemental Information -
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Third and Fourth Ouarters. 1988 l I
- 1. Technical Specification Limits - Dose and Dose Rate .
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Technical Specification and Category Limit-
- a. u Noble Gases l
I 3.11.2.1 Total body dose rate 500 mrem /yr i 3.11.2.1 Skin dose rate 3000 mrem /yr 3.'11.2.2 Gamma air dose 5 mrad in a quarter 3.11.2.2 Gamma air dose 10 mrad in a year 3.11.2.2 Beta air dose 10 mrad in a quarter j 3.11.2.2 Beta air dose 1 20 mrad in a year
- b. Iodine-131. Tritium and Radionuclides j in Particulate Form With Half-Lives ]
Greater Than 8 Daya I
3.11.2.1 Organ dose rate 1500 mrem /yr 3.11.2.3 Organ dose 7.5 mrem in a quarter 3.11.2.3 Organ dose 15 mrem in a year I c. Liquida 3.11.1.2 Total body dose 1.5 mrem in a quarter 3.11.1.2 Total body dose 3 mrem in a year 3.11.1.2 Organ dose 5 mrem in a quarter 3.11.1.2 Organ dose < 10 mrem in a year l
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- 2. Technical _Specificellon Limits - Concentration j l
1 Technical Specification and Category Limii !
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- a. Noble Gases No MPC limits
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- b. Iodine-131. Tritium and Radionuclides No MPC limits in.farti al. ate Folm With Half-Liygg l
GER A M D'GL. S .DBSA
- c. Li_quida 3.11.1.1 Total cum of the fraction of MPC (10CFR20, Appendix B, Tables II, Column 2), excluding noble gases less than: 1.0 3.11.1.1 Total noble gas concentration 2E-04 uC1/cc l
l l 3. Meanutements and Approximations of Total _ Radioactivity l
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- a. Noble casns
" Continuous discharges" are determined by indirect measurement.
Primary gas samples are taken periodically and analyzed. It is assumed that in primary to secondary leakage all gases are ejected through the air ejector. In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during l l flashing or liquid waste processing. " Batch dischargeo" are determined by direct measurement. Errors associated with these measurements are estimated to be 155 percent.
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Iodines are continuously monitored by drawing a sample from the ;
primary vent stack through a particulate filter and charcoal j cartridge. The filter and charcoal cartridge are removed and
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analyzed weekly. The errors associated with these measurements are-estimated to be f25 percent. I 1
- c. Particulate I
The particulate filter described in (b) above is analyzed weekly.
The errors associated with the determination of particulate effluents
-are estimated to be i30 percent.
- d. Liould Effluents i
Liquid effluents are determined;by direct' measurement. In line j l
composite samples are analyzed for strontium-89, strontiun990, gross j alpha activity and carbon-14. There is no compositing of samples for l tritium or dissolved fission gas analysis. For continuous discharges composite samples are used for gamma isotopic analysis. A gamma isotopic analysis is performed on a representative sample for each batch release using the Marinelli Beaker geometry. The errors
, associated with these measurements are as follows: fission and l I
activation products, 120 percent; tritium, fl0 percent; dissolved 1 1
fissiongases,120 percent;alphaActivity,i35 percent. )
- 4. Batch Releagga l I
- a. Li.quida Ihird Quarter Number of batch releases: 25 Total time period for batch releases: 8,681 minutes Maximum time period for a batch release: 1,345 minutes Average time period for batch releases: 347 minutes Minimum time period for a batch release: 210 minutes Average stream flow during period (Sherman Dam): 331 cfs Average discharge rate: 20.8 gpm I-3 2990T f
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fourth Ouarter 1
-Number of batch releases: 32 Total- time period for batch releases: 9,346 minutes Maximum time period for a batch release: 875 minutes Average time period for batch releases: 292 minutes 1 1
Minimum time period for a batch release: 10 minutes 4 Average stream flow during period (Sherman Dam): 602 cfs Average discharge rate: 22.1 gpm
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There were no batch releases during the third quarter. l l
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Fourth Ouarter Number of batch releases: 4 l 1
Total time period for batch releases: 1,351 minutes i Maximum time period for a batch release: 600. minutes l Average time period for batch releases: 338 minutes Minimum time period for a batch release: 38 minutes c
- 5. Abnormal Releassa l
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- a. Liquid Technical Specification 6.9.5.b requires the reporting of any l
unplanned releases from the site to the site boundary of radioactive material in gaseous and liquid effluents made during the reporting 3 period. l I-4 2990T
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Description of Occurrence: At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />, November 23, 1988, following the completion of OP-2000.223, " Hydrostatic Test for the Replacement of Pipe between VD-V-692 and VD-V-1150", S/G No. 2 blowdown line was returned to service. In accordance with OP-2000.223, the blowdown line was aligned to TV-401B, which was closed. During the previous day all blowdown line isolation valves were checked closed, including VD-V-608, which isolates the blowdown line of S/G No. 2. While realigning valves to return S/G No. 2 blowdown line to service, the Shift Supervisor assumed that VD-V-608 was closed since_it had not been operated during the execution of OP-2000.223. The Shift Supervisor ordered the Control Room Operator to open TV-401B to normalize the header. Contrary to the assumption, VD-V-608 had been opened and, therefore; created a flowpath from S/G No.2, via the blowdown header, to the 001 circulating water outlet and Sherman Pond. An Auxiliary Operator (AO) noticed the noise created by the flow through the blowdown header and immediately notified the Control Room. The A0 was ordered to close VD-V-608 which terminated the release. The level in S/G No.2 decreased from
~20 feet to ~12 feet, resulting in a release of approximately 2,000 gallons.
1 The release was not planned, but was monitored and recorded by the {
Steam Generator Blowdown Monitor (RIRM-108). Subsequent radionuclides analyses of the remaining water in the steam generator indicated no j l positive activity values. The release did not exceed the requirements of 10CFR50.73. Corrective action has been implemented !
to prevent reoccurrence. i
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i There were no nonroutine gaseous releases during the reporting period. I 1
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'YpIVKEE ATOMIC ELECTRIC COMPANY l
'fy"llo"g"go','g*;"g" '
N 580 Main Street, Bolton, Massachusetts 01740-1398
.Yauxes
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February 27, 1989 BYR 89-35 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Reference:
(a) License No. DPR-3 (Docket No. 50-29)
Subject:
Semiannual Effluent Release Report
Dear Sir:
Enclosed please find the tables summarizing the quantities of radioactive liquid and gaseous effluents and solid waste released from the Yankee plant at Rowe, Massachusetts for the third and fourth quarters of 1988 submitted in accordance with Technical Specification 6.9.5.b.1. The summary of the estimates of off-site radiation doses resulting from plant effluents during 1988 will be provided in a supplemental report in accordance with Technical Specification 6.9.5.b.2.
We trust that this information is satisfactory; however, should you have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY George Papanic, PJ Senior Project Engineer-Licensing GP/b11/0224v Enclosures cc: USNRC Region I USNRC Resident Inspector, YNPS h
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