Text

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*

Krvoton-85m Ci N/D*

N/D*

3.59 E-04__

L Krvaton-07 Ci N/D*

N/D*

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L Krvoton-88 Ci 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*

Xenon-138 Ci 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*

Arcon-41 Ci N/D*

N/D*

Unidentified Ci 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*

l Strontium-90 Ci N/D*

N/D*

Cesium-134 Ci 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' Zinc-65 Ci N/D*

N/D*

Cobalt-58 Ci 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 - Not Detected O

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4. 43Li._;. JABLE 1C

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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

05051-DS

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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*

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*

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*

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*

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*

2.76 E-04 Xenon-133m Ci 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.

05051-DS

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.

C1

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.

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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(Continued) j$' -

4.

Batch Releases e

a.

Liouio's 1.

Number of batch releases: 57 2.

Total time period for batch releases:

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

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

Average time period for batch releases:

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 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 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months , 53 minutes 3.

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

Average time period for b&tch releases:

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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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05051-0S

_ _ _ _ _

ML20246L087

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1.0 INTRODUCTION

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ML20246L087

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1.0 INTRODUCTION

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