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Semiannual Effluent Release Rept,Jul-Dec 1987
	ML20147H505
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1987
From:	Whittier G; Maine Yankee
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	GDW-88-50, MN-88-23, NUDOCS 8803080507
	Download: ML20147H505 (15)
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. MAINE YANKEE ATOMIC POMER COMPANY SEMIANNUAL EFFLUENT RELEASE REPORT July - December, 1987

1.0 INTRODUCTION

Tables 1.through 4 list the recorded radioactive liquid and gaseous effluents and solid waste for the'second six months of the year, with data-summarized on a quarterly basis.

Appendices A through E indicate the status of reportable items per the requirements of Technical Specifications 3.16.C, 3.17.D, 3.28.A 3.28.B. 4.8.A, 4.13 and 5.9.1.6.

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C' TABLE 1A Haine Yankee Atomic Power Station Effluent and Waste Disposal Semiannual Reoort Third and Fourth Ouarters. 1987 ,

Gaseous Effluents - Summation of All Releases _

Unit Quarter Quarter Est. Total 3rd 4th Error. %

A. Fission and Activation Gases

1. Total release Ci 2.34 E-02 1.26 E-02 2.50 E+01

2. Averaae release rate for oeriod UCi/sec 2.98 E-03 1.63 E-03

3. Percent of regulatory limit % 8.96 E-06 4.89 E-Q6_

B. Iodines

1. Total Iodine-131 Ci 2.37 E-05 4.61 E-08 2.50 E+01

2. Average release rate for oeriod uCi/sec 3.01 E-06 5.86 E-09

3. Percent of reaulatory limit 1 2.64 E-05 5.14 E-08 C. Particulates

1. Particulates with T-1/2 l 8 days Ci 5.87 E-06 1.49 E-06 2.50 E+01

2. Averaae release rate for oeriod uCi/sec 7._46 E-07 1.89 E-07

3. Percent of reaulatory limit % 3.62 E-06 1.24 E-07

4. Gross aloha radioactivity C1 1.07 E-08 1.01 E-08 D. Tritium

1. Total release Ci 5.47 E-01 1.06 E+00 2.50 E+01

2. Averaae release rate for oeriod UC1/sec 6.96 E-02 1.35 E-01

3. Percent of reculatory limit % 3.05 E-04 5.91 E-04 8510L-DS

TABLE IB Haine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort Third and Fourth Ouarters. 1987 Gaseous Effluents - Elevated Release Continuous Mode Batch Hode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th

1. Fission Gases Krvoton-85 C1 N/D* N/D* N/D* N/D*

Krvoton-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* 2.34 E-02 1.25 E-02 Xenon-135 Ci N/D* N/D* N/D* 8.99 E-05 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*

Araon-41 Ci N/D* N/D* N/D* N/D*

Xenon-131m Ci N/D* N/D* N/D* N/D*

Unidentified Ci N/D* N/D* N/D* N/D*

Total for oeriod C1 N/D* N/D* 2.34 E-02 1.26 E 2. Iodines Iodine-131 Ci 2.37 E-05 N/D* 1.74 E-10 4.61 E-08 Iodine-133 Ci 1.66 E-04 N/D* 3.86 E-10 1.04 E-07 Iodine-135 Ci N/D* N/D* N/D* N/D*

Total for oeriod Ci 1.90 E-04 N/D* 5.60 E-10 1.50 E-07

3. Particulates Stronti um-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* N/D* N/D*

Cesium-137 C1 2.20 E-06 4.97 E-07 N/D* N/D*

Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D*

Ruthenium-103 Ci N/D* N/D* N/D* N/D*

Cobalt-58 Ci N/D* N/D* N/D* N/D*

Cobalt-60 Ci 1.03 E-06 8.99 E-07 N/D* N/D*

Cadmium-109 C1 N/D* N/D* N/D* 8.56 E-08 Others

N/D - Not Detected 8510L-OS L

TABLE IC

' Maine Yankee Atomic Power Station Effluent and Haste Disposal Semiannual Reoort Third and Fourth Ouarters 1987 Gaseous Effluents - Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the third and fourth quarters of 1987.

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TABLE 2A ,

Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort Third and Fourth Ouarters. 1987 Liould 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. aloha) Ci 1.19 E-01 7.16 E-02 1.50 E+01

2. Average diluted concentration durina ceriod uC1/ml 9.30 E-10 3.46 E 3. Percent of acolicable limit 1 2.48 E-03 1.97 E-03 B. Tritium

1. Total release Ci 1.42 E+01 6.53 E+01 1.50 E+01

2. Average diluted concentration durina ceriod uCi/ml 1.11 E-07 3.15 E-07

3. Percent of acolicable limit 1 3.72 E-03 1.05 E-02 C. Dissolved and Entrained Gases

1. Total release Ci 5.71 E-03 1.33 E-02 1.50 E+01

2. Average diluted concentration durino ceriod uCi/ml 4.46 E-11 6.43 E-11

3. Percent of acolicable limit 1 2.23 E-05 3.21 E-05 D. Gross Alpha Radioactivity

1. Total release Ci 8.77 E-06 6.98 E-06 1.50 E+01

2. Average diluted concentration durina ceriod UCi/mi 6.85 E-14 3.37 E-14 E. Volume of waste released (prior to dilution) liters 1.86 E+07 7.91 E+06 1.00 E+01 F. Volume of dilution water used 1.00 E+01 durino ceriod liters 1.28 E+11 2.07 E+11 8510L-DS

i TABLE 2B Haine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort Third and Fourth Ouarters. 1987 Liauid 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* 1.69 E-03 Stronti um-90 Ci 2.81 E-03 N/D* 6.39 E-05 2.06 E-05 Cesium-134 Ci N/D* N/D* 6.16 E-04 1.11 E-03 Ceslum-137 Ci N/D* N/D* 3.80 E-03 4.72 E-03 Iodine-131 Ci N/D* N/D* 2.48 E-04 5.87 E-04 Cobalt-58 Ci N/D* N/D* 9.81 E-03 3.95 E-03 Cobalt-60 Ci N/D* N/D* 1.55 E-02 9.78 E-03 Iron-59 Ci N/D* N/D* N/D* N/D*

Zinc-65 Ci N/D* N/D* N/D* N/D*

Manaanese-54 Ci N/D* N/D* 1.28 E-04 N/D*

Chromium-51 Ci N/D* N/D* 1.08 E-03 6.30 E-04 Zirconium-Niobium-95 Ci N/D* N/D* 1.49 E-03 6.24 E-05 Molybdenum-99 Ci N/D* N/D* 3.34 E-05 7.77 E-05 Techneti um-99m Ci N/D* N/D* 6.43 E-05 2.07 E-05 Bari um-Lanthanum-140 Ci N/D* N/D* N/D* 8.63 E-04

. Cerium-141 Ci N/D* N/D* N/D* N/D*

Others Iron-55 Ci N/D* 4.90 E-02 3.85 E-02 Silver-110m Ci N/D* 5.80 E-03 6.78 E-03 Cobalt-57125 Ci N/D* N/D* N/D* 1.72 E-05 Antimony-124 Ci N/D* N/D* 1.16 E-02 2.79 E-04 Antimony-125 Ci N/D* N/D* 1.62 E-02 1.52 E-03 Iodine-132 Ci N/D* N/D* N/D* 2.07 E-05 Iodine-133 Ci N/D* N/D* 3.53 E-04 3.51 E-04 Iodine-135 Ci N/D* N/D* N/D* 1.97 E-04 Tin-113 Ci N/D* N/D* 1.91 E-04 3.02 E-05 Rhuthenium-103 Ci N/D* N/D* 9.89 E-05 1.78 E-05 Cerium-139 Ci N/D* N/D* N/D* 3.54 E-05 Neotunium-239 Ci N/D* N/D* N/D* 4.27 E-05 Strontium-91 Ci N/D* N/D* N / D,* 8.10 E-05 Yttrium-91m Ci N/D* N/D* N/D* 8.52 E-05 Yttrium-92 Ci N/D* N/D* N/D* 1.07 E-04 Unidentified Ci N/D* N/D* N/D' N/D*

_ Total for oeriod (above)(1)Ci 2.81 E-03 0.00 E-01 1.16 E-01 7.16 E . Xenon-133 Ci N/D* N/D* 5.08 E-03 1.23 E-02 Xenon-135 Ci N/D' N/D* 6.25 E-04 9.91 E-04 Xenon-135M Ci N/D* N/D* N/D* 5.21 E-05 N/D* - Not Detected (1) - Total for period does not include unidentified in this summation but is included in Table 2A, Item A1.

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a TABLE 3 Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Report Third and Fourth Ouarters. 1987 Solid Haste and Irradiated Fuel Shioments A. _ Solid Haste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*

Unit 6-Month Est. Total Period Error. %

1. Type of Haste

a. Spent resint. filter sludges, evaporator m3 4.48 1 10 bottoms. etc - LSA container **.+++ Ci 4.90

b. Dry compressible waste, contaminated m3 eauioment. etc. - LSA container +.++ Ci c. Irradiated components, control rods, m3 etc. Ci d. m3 C1

e. m3 C1

2. Estimate of Major Nuclide Composition (By Type of Haste)***

a. Co-134 15% olus or minus 101 Cs-137 56% olus or minus 10%

Fo-55 10% elus or minus 10%

.Ni-63 5% olus or minus 10%

H-3 10% olus or minus 10%

b. 3. Solid Haste Disposition Number of Shioments Mode of Transoortation Destination

~

1 Trucking over Highway Chem-Nuclear, Barnwell, S.C.

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)

Solid waste is Class A, as defined in 10CFR61.55. 4.48 m3, 4.90 Ci

Solid waste is Class B, as defined in 10CFR61.55 0 m3 O Ci

Solid waste is Class C, as defined in 10CFR61.55 0 m3,, O Ci

- Solidification agent is cement.

- - Excluding nuclides with half-lives less than 12.8 days.

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TABLE 4 Sucolemental Information j l

1. -Reaulatory Limits Maximum Permissible Concentration

a. Fission and activation gases: 10CFR20; Appendix B Table 2 Column 1

b. Iodines: 10CFR20; Appendix B, Table 2, Column 1

c. Particulates, (with half lives greater than 8 days) 10CFR20; Appendix B, Table 2 Column 1 d.- Liquid effluents: 10CFR20; Appendix B. Table 2, Column 1

e. Total noble gas concentration 2E-04 uCi/ml

2. Averaae Enerav - Not Aeolicable

3. Measurements and Aceroximations of Radioactivity

a. Fission and Activation Cases Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels determined are assumed constant for the surveillante interval. The continuous vent stack monitor reading is used as a basis for increasing

. periodic sample frequency.

Batch Olscharges - 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 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 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 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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TABLE 4 (Continued)

4. Batch Releases I

a. Liouids j

1. Number of batch releases: 87

2. Total time period for batch releases: 445 hours0.00515 days 0.124 hours 7.357804e-4 weeks 1.693225e-4 months , 27 minutes

3. Maximum time period for a batch release: 59 hours6.828704e-4 days 0.0164 hours 9.755291e-5 weeks 2.24495e-5 months , O minutes

4. Average time period for batch releases: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , 7 minutes

5. Minimum time period for a batch release: 19 minutes

6. Average steam flow during periods of release of effluents into a flowing stream: N/A

7. Maximum gross release concentration (uCi/ml): 1.16 E-06

b. Gaseous

1. Number of batch releases: 16

2. Total time period for batch releases: 21 hours2.430556e-4 days 0.00583 hours 3.472222e-5 weeks 7.9905e-6 months , 51 minutes

3. Maximum time period for a batch release: 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 53 minutes

4. Average time period for batch releases: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 22 minutes

5. Minimum time period for a batch release: 1 minute

6. Maximum gross release rate (uCi/sec): 2.63 E+01

5. Abnormal Releligt

a. Liould 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 Purae On-line containment purge was not employed during the reporting period. Total on-line purge time for 1987 was 107 hours0.00124 days 0.0297 hours 1.76918e-4 weeks 4.07135e-5 months and 27 minutes.

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APPENDIX A Radioactive liquid Effluent Monitorina Instrumentation Reauirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.28.A. 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 3.28.A requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

Resoonte: During this reporting period, two effluent monitors were inoperable in excess of 30 days when required to be operable.

As reported previously, the air ejector monitor was continued as inoperable following replacement with a different, moisture resistant detector until a primary calibration was performed.

This was accomplished and the monitor was returned to service on September 10, 1987.

Similarly, the original tube failed during calibration of the primary vent stack gas monitor on July 1, 1987. Again, a component substitution was required, and the monitor was considered inoperable until a primary calibration was completed on August 20, 1987.

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&PPENDIX B Liauid Radwaste Treatment System Reauirement: With radioactive liquid waste being discharged without 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.

Resoonse: The requirements of Technical Specification 3.17.C.1 were met during this period and, therefore, no report is required.

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APPENDDLC Gaseous Radwaste Treatment System Reautrement: Hith radioactive gaseous waste being discharged without treatment with doses in excess of the limits in Technical Specifications t 3.18.D.1, a report must be submitted to the Commission in the Semiannual Effluent Release Report for the period.

Resoonse: The requirements of Technical Specification 3.18.D.1 were met during this period and, therefore, no report is required.

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APPENDIX D Lower Limit of Detection for Radioloaical Analyses Reautrement: Technical Specification 4.13 requires that when unusual circumstances result in LL0s higher than required, the reasons shall be documented in the Semiannual Radioactive Effluent Release Report.

Resoonse: Analyses were performed in such a manner that the stated LLD's were

achievable under routine conditions. On several occasions, with liquid samples, however, the presence of detected higher energy isotopes caused a compton background elevation. This interference was sufficient to make the specified LLD's in those liquid samples unattainable. On all occasions, the specified LLO's were attained on the gaseous samples.

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) APPENDIX E Reactor Coolant System Activity Reauirements: Technical Specific ulon 5.9.1.3.B requires that a report, covering the results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.2, be submitted annually for the previous calendar year.

The-report shall include (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result to include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the iodine-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radiolodine limit. <

Resoonse: Primary coolnat activity did not exceed the limits of Specification 3.2 during the reporting period and, therefore, no report is required.

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9 MaineYankee RE(LABLE ELECTRCTY FOR WME SME '972 EolSON oRIVE

AUGUSTA, MAtNE 04330 .(207) 623 3521 February 29, 1988 HN-88-23 GDH-88-50 Region I United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Attention: Mr. Hilliam T. Russell, Regional Administrator

References:

(a) License No. DPR-36 (Docket No. 50-309)

Subject:

Semiannual Effluent Release Report Gentlemen:

Enclosed is the Maine Yankee Semiannual Effluent Release Report. The report includes the annual reactor coolant system activity report. There were no changes to the Off-Site Dose Calculation Manual. These reporte are submitted in accordance with Technical Specifications 5.9.1.6 and 5.9.1.38.

This report covers the period from July 1, 1987 to December 31, 1987.

Very truly yours, HAINE YANKEE AT0 HIC POWER COMPANY k/2.0 &

G. D. Whittier, Manager Nuclear Engineering and Licensing GDH/bjp Enclosure cc: Mr. Richard H. Hessman Mr. Cornelius F. Holden Mr. Pat Sears Document Control Desk Mr. Donald Hoxie - DHE Hr. John Brochu - DEP American Nuclear Insurers ,

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ML20147H505

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