ML20246L087

Semiannual Effluent Release Rept for Jan-June 1989. No Changes Made to ODCM

ML20246L087
Person / Time
Site:	Maine Yankee
Issue date:	06/30/1989
From:	Whittier G Maine Yankee
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
GDW-89-284, MN-89-111, NUDOCS 8909060221
Download: ML20246L087 (14)

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'MaineYankee atuxea tacinornon uame suce im

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+i August 29, 1989 MN-89-111 GDH-89-284 Region I UNITED STATES NUCLEAR REGULATORY COMMISSION

' 475 Allendale Road King of Prussia, Pennsylvania 19406 Attention: Mr. William T. Russell, Regional Administrator e

References:

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

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Subject:

Semiannual Effluent Release Report

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Enclosed is the Maine Yankee Semiannual Effluent Release Report for the period January 1,1989 to June 30, 1989. There were no changes to the

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Off-Site Dose Calculation Manual. These reports are submitted in accordance with Technical Specifications 5.9.1.6, 4.13, 3.28, 3.16 and 3.17.

Very truly yours, MAINE YANKEE

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G. D. Whittier, Manager Nuclear Engineering and Licensing GDH:HSD

Enclosure c

Mr. Richard H. Hessman Mr. Eric J. Leeds Mr. Cornelius F. Holden Document Control. Desk 1

Mr. Donald Hoxie - DHE Mr. Allan Prysunka - DEP - Oil & Hazardous Haste American Nuclear Insurers

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SEMIANNUAL EFFLUENT RELEASE REPORT w;. -

January - June, 1989 7

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1.0 INTRODUCTION

l 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 i

summarized on a quarterly basis, i

Appendices A through 0 indicate the status of reportable items per the requirements of Technical Specifications 3.16.C, 3.17.0, 3.28. A. 3.28.8, 4.8.A, 4.13 and 5.9.1.6.

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Effluent and Waste Discosal Semiannual Reoort 7ITT' First and Second Ouarters. 1989 Gaseous Effluents - Summation of All Releases j;, l _. ' '

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' " illfft"c Unit Quarter Quarter Est. Total

., avi.x 1st 2nd Error. %

P-av 3;qf iA. Fission add Activation Gases j

1. Total release Ci 4.29 E-01 2.18 E-01 2.50 E+01

2. Averace release rate for oeriod UCi/ set 5.45 E-02 2.78 E-02.

3. Percent of reculatory limit 1.64 E-04 9.04 E-05 B. Iodines

1. Total Iodine-131 Ci 9.38 E-06 5.39 E-06 2.50 E+01

2. Averaae release rate for oeriod UCi/sec 1.19 E-06 6.84 E-07

3. Percent of reculatory limit 1.05 E-05 6.00 E-06_

C. Particulate

1. Particulate with T-1/224 8 davs Ci 1.46 E-06 1.57 E-07 2.50 E+01

2. Averaae release rate for oeriod UCi/sec 1.85 E-07 1.99 E-08

3. Percent of reculatory limit 4.57 E-07 5.81 E-08

4. Gross aloha radioactivity C1 1.84 E-07 8.18 E-08 l

D. Tritium

1. Total release C1 1.20 E+00 2.12 E+00 2.50 E+01 l

2. Averace release rate for oeriod UCi/sec 1.53 E-01 2.70 E-01

3. Percent of reaulatory limit 6.69 E-04 1.18 E-03 1

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Effluent and Waste Discosal Semiannual Reoort p

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Continuous Mode Batch Mode

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f Nuclides Released Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd Q Z ',.

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T 1. Fission Gases 7

y Krvoton-85 Ci N/D*

N/D*

N/D*

N/D*

Krvoton-85m Ci N/D*

N/D*

N/D*

3.59 E-04__

L Krvaton-07 Ci N/D*

N/D*

N/D*

N/D*

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L Krvoton-88 Ci N/D*

N/D*

N/D*

N/D*

Xenon-133 Ci N/D*

N/D*

4.26 E-01 2.09 E-01 Xenon-135 Ci N/D*

N/D*

1.45 E-04 8.72 F,,Q3._

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*

2.38 E-03 7.13 E-06.

Xenon-131m Ci N/D*

N/D*

N/D*

N/D*

Arcon-41 Ci N/D*

N/D*

N/D*

N/D*

Unidentified Ci N/D*

N/D*

N/D*

N/D*

l Total for oeriod Ci N/D*

N/D*

4.29 E-01 2.18 E-01l*

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2. Iodines Iodine-131 Ci 9.34 E-06 3.85 E-06 3.93 E-08 1.54 E Iodine-133 C1 1.04 E-05 1.47 E-05 5.21 E-08 3.39 E-06 Iodine-135 Ci N/D*

N/D*

2.02 E-08 1.60 E-06 Total for neriod C1 1.97 E-05 1.86 E-05 1.12 E-07 6.53 E-06 l

3. Particulate Strontium-89 Ci N/D*

N/D*

N/D*

N/D*

l Strontium-90 Ci N/D*

N/D*

N/D*

N/D*

Cesium-134 Ci N/D*

N/D*

N/D*

N/D*

Cesium-137 Ci 5.73 E-07 N/D*

N/D*

1.32 E 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*

Cobalt-60 Ci 8.83 E-07 1.55 E-07 N/D*

8.80 E-10 Others Ci N/D*

N/D*

N/D*

N/D*

• N/D - Not Detected O

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-Maine Yankee Atomic Power Station

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- Effluent and Waste Disnosal Semiannual Renort First and Second Ouarters 1989

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Gaseous Effluents - Ground Level Releases V,

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f li There were.no routine measured' ground level continuous or batch mode gaseous releases' during the first and second quarters of 1989.

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Maine Yankee Atomic Pombt Station Effluent and Haste Disogsal Semiannual Reoort

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First and Second Ouarters. 1989 Liouid Effluents - Summation of All Releases

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Unit Quarter Quarter Est. Total 1st 2nd Error. %

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,,; iA.' Fission and Activation Products

~1. Total release (not including tritium. aases. aloha)

Ci 1.01 E-01 1.49 E-02 1.50 E+01

2. Average diluted concentration durina ceriod uti/ml 5.05 E-10 7.16 E-11

3. Percent of aoolicable limit 7.65 E-03 1.61 E-03 B. Tritium

1. Total release Ci 3.52 E+01 9.59 E+01 1.50 E+01

2. Average diluted concentration durina ceriod UCi/mi 1.76 E-07 4.61 E-07

3. Percent of acolicable limit 5.87 E-03 1.54 E-02 C'

C. Dissolved and Entrained Gases

1. Total release Ci 6.74 E-03 8.38 E-02 1.50 E+01

2. Average diluted concentration durina Deriod UCi/ml 3.37 E-11 a.03 E-10

3. Percent of anolicable limit 1.69 E-05 2.01 E-04 D. Gross Alpha Radioactivity

1. Total release Ci 2.89 E-05 N/D*

1.50 E+01

2. Average diluted concentration durina ceriod UCi/ml 1.45 E-13 N/D*

E. Volume of waste released (prior to dilution) liters 1.54 E+07 7.76 E+06 1.00 E+01 F. Volume of dilution water used durina ceriod liters 2.00 E+11 2.08 E+11 1.00 E+01 h

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'j' Effluent and Haste DisDosal Semiannual ReDort first and Second Ouarters. 1989

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Nuclides Released Unit Quarter Quarter Quarter Quarter

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Strontium-89 Ci N/D*

N/D*

2.50 E-04 N/D*

Strontium-90 Ci N/D*

N/D*

N/D*

N/D*

Cesium-134 Ci N/D*

N/D*

2.65 E-03 9.01 E-05 Cesium-137 Ci 1.23 E-05 4.81 E-05 8.52 E-03 5.78 E-04 Icdine-131 Ci N/D*

N/D*

3.37 E-03 8.94 E-04_

Cobalt-58 Ci N/D*

N/D*

].42 E-02 2.04 E-03 Cobalt-60 Ci 1.40 E-04 1.51 E-04 1.52 E-02 4.20 E-03 Iron-59 Ci N/D*

N/D*

N/D*

N/D*

Zi nc-65 Ci N/D*

9.39 E-08 N/D*

N/D*

Mancanese-54 Ci N/D*

1.23 E-08 1.22 E-03 3.79 E-04 Chromium-51 Ci N/D*

N/D*

4.27 E-04 N/D*

L' Zi rconium-Niobium-9S Ci N/D*

5.08 E-07 1.05 E-05

.N/D*

Holybdenum-99 Ci N/D*

N/D*

1.57 E-04 1.15 E-05 Technetium-99m Ci N/D*

N/D*

3.73 E-04 9.35 E-06 l

Barium-tanthanum-140 Ci N/D*

9.31 E-07 1.30 E-04 1.21 E-04 Ceri um-141 Ci N/D*

N/D*

N/D*

N/D*

Others Iron-55 Ci N/D*

N/D*

6.85 E-03 2.55 E-03 Silver-110m Ci N/D*

N/D*

1.94 E-03 1.22 E-04 Iodine-133 Ci N/D*

4.74 E-07 9.62 E-04 N/D*

Antimonv-124 Ci N/D*

N/D*

2.79 E-02 1.85 E-03 Antimony-125 Ci N/D*

1.36 E-05 1.67 E-02 1.82 E-03 Ruthenium-103 Ci N/D*

2.28 E-08 N/D*

N/D*

Cobalt-57 Ci N/D*

N/3*

4.51 E-06 N/D*

Tin-113 Ci N/D*

3.85 E-07 2.63 E-05 2.49 E-05

_MDj denti fi ed Ci H/D*

N/D*

N/D*

N/D*

Total for Deriod (above)(1)Ci 1.52 E-04 2.15 E-04 1.01 E-01 1.47 E-02 Xenon-133 C1 1.05 E-04 1.96 E-05 6.53 E-03 8.24 E-02 Xenon-135 Ci N/D*

2.30 E-06 1.02 E-04 3.36 E-04 Xenon-131m Ci N/D*

N/D*

N/D*

2.76 E-04 Xenon-133m Ci N/D*

N/D*

N/D*

7.49 E-04 Krvoton-85m Ci N/D*

2.11 E-06 N/D*

N/D*

KrvDton-88 C1 N/D*

1.33 E-06 N/D*

N/D*

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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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TABLE 3

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Maine Yankee Atomic Power Station fl D uent and Haste D1900111 Semiannual Reoort First and Second Ouarters.19fd Solid Maste and Irradiated Fuel Shioments

.A. Solid Haste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*

6-Month Est. Total Unit

___fsri od Error. %

1. Type of Haste

a. Spent resins, filter sludges, evaporator m3 3.4 i 10 bottoms. etc. - LSA container **.+ w Ci 55.72-

b. Dry. compressible waste, contaminated m3 84.1 i 10 eauioment. etc. - LSA container +.++

C1 1.5

c. Irradiated components, control rods,

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etc.

Ci 0

d.

m3 Ci m3 e.

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

a. Fe-55 35%

elus' or minus 10%

Ni-63.

31%

olus or minus 10%

Co-60 22%

olus or minus 10%

Cs-137 2%

olus or minus 10%

l Ba-137M 2%

olus or minus 10%

Sb-125 1%

olts or minus 10%

b. Cs-137 10%

olus or minus 10%

Co-60 22%

olus or minus 10%

Co-58 11%

olus or minus 10%

Cs-134 3%

olus or minus 10%

Ni-63 14%

olus or minus 10%

Fe-55 26%

olus or minus 10%

Zr-95 5%

olus or minus 10%

Sb-125 2%

olus or minus 10%

3. Solid Haste Disposition Number of Shioments Mode of Transportation Destination From Maine Yankee 5 Trucking over Highway Chem-Nuclear, Barnwell, S.C.

From SEG #

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

B. Irradiated Fuel Shipments (Disposition)

+ Contain?r volume equal to 55 gal ons (drums).

++ Contalair volume equal to 110 f t (boxes).

m Contal' ar volume equal to 170 ft (liners) (HIC)

• Solid waste is Class A, as defined in 10CFR61.55.

84.1 m3, 1.5 Ci

• Solid waste is Class B, as defined in 10CFR61.55 0.8 m3, 6.76 Ci

• Solid waste is Class C, as defined in 10CFR61.55 2.6 m3, 48.96 Ci

• • Solidification agent is cement.

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

1. SEG performs super compacting of DAH.

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Sucolemental Information G'

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1.. Reaulatory Limits Maximum Permissible Concentration

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a.

Fission and activation gases:

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

Iodines:

10CFR20; Appendix B. Table 2, Column 1 c.

Particulate, (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 uC1/mi

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2.

Averace Eneray - Not Aeolit.able 3.

Measurements and Anoroximations of Radioactivity a.

Fission and Activation Cases

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Continuous Discharge - Vent stack samples are analyzed monthly. Activity 1evels determined are assumed constant for the surveillance interval. The l

continuous vent stack monitor reading is used as a basis for increasing 0~

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periodic sample frequency.

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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.

Icdines l

Primary vent stack iodine totals are taken from a minimum of weekly measurements of an in-line charcoal filter.

c.

Particulate Primary vent stack particulate totals are taken from a minimum of weekly 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 fs analyzed for gross beta-gamma, alpha, tritium, di_ssolved 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

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4.

Batch Releases e

a.

Liouio's 1.

Number of batch releases: 57 2.

Total time period for batch releases:

187 hours0.00216 days <br />0.0519 hours <br />3.091931e-4 weeks <br />7.11535e-5 months <br />, 50 mirastes 3.

Maximum time period for a batch release: 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />. 5 minutes 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 />, 18 minutes 5.

Minimum time period for a batch release:

15 minutes 6.

Average stream flow during periods of release of effluents into a flowing stream: N/A 7.

Maximum gross release concentration (uCi/ml):

1.71 2-07

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l b.

Gaseous 1.

Number of batch releases:

12 2.

Total time period for batch releases:

104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, 53 minutes 3.

Maximum time period for a batch release: 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, 22 minutes 4.

Average time period for b&tch releases:

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 44 minutes 5.

Minimum time period for a batch release:

15 minutes 6.

Maximum gross release rate (uC1/sec):

1.13 E+03 5.

Abnormal Releases a.

Licuid 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.

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APPENDIX A 3

Radioactive Effluent Henitorina Instrumentation Recoirement: Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specificat'ons 3.28.A &

B.

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 Specifications 3.28.A &

B requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

Resoonse:

The requirements of Technical Specifications 3.28.A and 3.28.B.

governing operability of radioactive effluent monitoring instrumentation, were met for this reporting period, and no report is required.

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id APPENDIX B p".

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'f-Linuid Radwaste Treatment System-F-

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R'eauirement: With radioactive liquid waste being discharged without treatment with i ~

estimated doses in excess of the limits in Technical Specification 3.17.C.1, a report must be submitted to--the Commission in the i

- Semiannual Effluent Release Report for the period.

a; 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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APPENDIX C Gaseous Radwaste Treatment System Requirement: Mith radioactive gaseous waste being discharged without treatment 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.D.1 were met during this period and, therefore, no report is required.

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APPENDIX D

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ii-Lower Limit of Detection for Radiological Analyses

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Requirement:' Technical Specification 4.13 requires that when unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Semiannual Radiaattive Effluent Release Report.

Resoonse:

Analyses were performed in such a manner that the stated LLD's were achievable under routine conditions. On occasion, with liquid samples, however, the presence of detected higher energy isotopes l

caused a compton background elevation. This interference was sufficient to make some of the specified LLD's in those liquid samples unattainable. This occurred in four (4) of the samples for I

Zinc-65, and one (1) for Iron-59. All other isotope LLD's were met.

On all occassions, the specified LLD's were attained on the gaseous samples.

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