Text

Semiannual Effluent Release Rept for Jul-Dec 1989
	ML20012B423
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1989
From:	; Maine Yankee
To:	Russell W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
	MN-90-22, SEN-90-43, NUDOCS 9003140379
	Download: ML20012B423 (15)
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.. c MaineYankee-D atuAsts ttecta 57foon uAmt smet ive EDtSON DRIVE

AUGUSTA. MAINE 04336 * (207) 6224868 y

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'i March 1, 1990 NN-90-22 SEN-90-43 Ll-Region'I UNITED STATES NUCLEAR REGULATORY C0tWISSION

.!4 475 Allendale Road King of Prussia, PA-19406

-Attention:

Mr. William T. Russell, Regional Administrator.

Reference:

(a)

License No. DPR-36 (Docket No. 50-309) i T

Subject:

Semiannual Effluent Release Report Gentlemen:

i Enclosed is the Maine Yankee Semiannual Effluent Release Report for the period-July 1, _1989 to December 31, 1989. The report includes the annual reactor

. coolant system activity report. There were no changes to the Off-site Dose

' Calculation _ Manual. These reports are submitted in accordance with Technical Specifications 5.9.1.6 and 5.9.1.38.

Very truly yours, l

seks S. E. Nichols H

Licensing Section Head DS:WSD L

Enclosure c:

Mr. Eric J. Leeds Mr..Cornelius F.iHolden l

EDocumenttControitDesktf l

. Mr. Donald Hoxie - DHE Mr. Allan Prysunka - DEP - Oil & Hazardous Waste American Nuclear Insurers SEN9043.LTR

?00UAlyyCK79 892231 05000309 I

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MAINE YANKEE ' ATOMIC; POWER COMPANY.

I SEMIANNUAL EFFLUENT RELEASE REPORT July - December 1989 1

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1.0 INTRODUCTION

Tables -1 through 4 list the recorded radioactive liquid and gaseous effluents and

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solid waste for the-second'six months of the year,Lwith data summarized on a quarterly basis..

5 Appendices A through E indicate-the status of reportable. items per.the requirements of Technical Specifications 3.16.C, 3;17.0, 3.28. A, 3.28.B _4.8. A, 4.13 and.5.9.1.6.

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TABLE lA-

.i Maine Yankee Atomic Power Station Effluent and Waste Dis)osal Semiannual Report Third and Fourt-1 Ouarters. 1989 Gaseous Effluents - Summation of All Releases

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Unit Quarter

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

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-A. Fission and Activation Gases

l. Total release C1 1.18 E-01 1.68 E+01 2.50 E+01

2. Averaae release rate for period uC1/sec 1.50 E-02 2.14 E+00

3. Percent of reaulatory limit 2.83 E-04 7.53 E-03 B. lodines

l. Total-Iodine-131 Ci 1.21 E-05 1.24 E-04 2.50 E+01

2. Averaae release rate for period uCi/sec 1.54 E-06 1.58 E-05

3. Percent of reaulatory limit 1.35 E-05 1.38 E-01_

C. Particulates

1. Particulates with T-1/2 I 8 days Ci 2.02 E-05 3.58 E-06 2.50 E+01

2. Averaae release rate for period uCi/sec 2.57 E-06 4.55 E-07

3. Percent of reaulatory limit 1.19 E 1.11 E-06

4. Gross aloha radioactivity Ci 2.64 E-07 1.98 E-07

~D. Tritium

1. Total release Ci-1.78 E+00 8.51 E-01 2.50 E+01

2. Averaae release rate for oeriod uCi/sec 2.26 E-01 1.08 E-01 1

3. Percent of reaulatory limit 9.93 E-04 4.75 E-04 l

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L 3 j}f TABLE IB' Maine Yankee Atomic Power Station-Effluent and Waste Disoosal Semiannual Report

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Third and fourth Quarters.-1989 Gaseous Effluents - Elevated Release b

Continuous Mode Batch Mode Nuclides Released Unit. -Quarter Quarter Quarter Quarter-

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3rd 4th 3rd 4th'

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

N/D*

Krvoton-85m Ci 5.25 E-03 6.04 E-03 1.36 E-06 1.43 E-02 Krvoton-87 Ci 1.25 E-02 1.36 E-02 N/D*

8.52 E Krvoton-88 Ci 9.33 E-03 1.04 E-03 N/D*

5.76 E-03 Xenon-133 C1 4.36 E-02 4.22 E-02 3.71 E-03 1.54 E+01 Xenon-135 Ci 7.03 E-03 8.32 E-02 1.28 E-04 8.30 E-01 Xenon-135m Ci 1.51 E-02 4.00 E-02 N/D*

3.42 E-04 Xanon-138 Ci 6.72 E-03 1.83 E-02 N/D*

N/D*

Xenon-133m Ci N/D*

N/D*

3.73 E-05 1.77 E-01 Xenon-131m Ci N/D*

N/D*

1.10 E-01 Arcon-41 Ci 1.46 E-02 2.33 E-02 1.32 E-05 1.61 E-02 Unidentified Ci N/D*

N/D*

2.26 E+00 Total for oeriod Ci 1.14 E-01 2.28 E-01 3.89 E-03 1.66 E+01-

2. Iodines lodine-131 C1 1.21 E-05 8.66 E-06 1.31 E-08 1.15 E-04 Iodine-132 Ci N/D*

N/D*

5.80 E-09 9.56 E-05 Iodine-133 Ci 6.02 E-05 1.46 E-05 3.12 E-08 2.54 E-04 Iodine-134 Ci N/D*

N/D*

6.28 E-06 Iodine-135 Ci N/D*

N/D*

2.71 E-08 1.12 E-04 Total for oeriod Ci 7.23 E-05 2.33 E-05 7.72 E-08 5.83 E-04

3. Particulates Strontium-89 Ci N/D*

N/D*

Strontium-90 Ci N/D*

N/D*

Cesium-134 C1 N/D*

N/D*

Cesium-137 C1 3.46 E-07 2.29 E-07 N/D*

1.27 E-06 Barium-Lanthanum-140 Ci N/D*

N/D*

2.36 E-10 Manaanese-54 Ci 8.23 E N/D*

N/D*

Coba' t-58 C1 8.14 E-06 N/D*

N/D*

Cobalt-60 Ci 6.58 E-07 N/D*

N/D*

2.08 E-06 Ruthenium-103 Ci 1.10 E-05 N/D*

N/D*

10N/D - Not Detected

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TABLE 1C n

. Baipe Yankee Atomic-Power Station

> ~ m Effluent and Waste Disposal Semiannual Reoort J.,

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Third and fourth Quarters 1989 i

Gaseous Effluents - Ground Level Releases I

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There were no routine measured ground-level continuous or batch mode gaseous releases during the third and fourth quarters of 1989.

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. TABLE 2A a c; Maine Yankee Atomic Power Station Effluent and Waste Dissosal Semiannual Reoort Third and Fourt i Quarters. 1989 l

Liouid-Effluents - Summation of All Releases Unit Quarter.

Quarter Est. Total 3rd 4th Error. %

LA. Fission and Activation Products

1. Total release (not including l

1:

tritium. aases. alpha)

-Ci 2.82 E-02 3.85 E-02 1.50 E+01 I.

2. Average diluted concentration durina period uCi /ml 1.36 E-10 2.12 E-10

3. Percent of anolicable limit 1.35 E-04 2.09 E-03

-B. Tritium

1. Total release Ci 1.07 E+02 1.84 E+02-1.50 E+01 l

2. Average diluted concentration durina neriod uti/ml 5.17 E-07 1.01 E-06

3. Percent of aonlicable limit 1.72 E-02 3.37 E-02 C. Dissolved and Entrained Gases

1. Total release C1 2.92 E-04 1.02 E-01 1.50 E+01

2. Average diluted concentration durina ceriod uCi/ml 1.41 E-12 5.60 E-10

3. Percent of anolicable limit 7.05 E-07 2.80 E-04

.D. Gross Alpha Radioactivity

1. Total release Ci 2.81 E-07 5.84 E-07 1.50 E+01

2. Average diluted. concentration durina ceriod uC1/ml 1.36 E-15 3.21 E-15 E. Volume of waste released (prior to dilution) liters 7.16 E+06 1.29 E+07 1.00 E+01 F. Volume of dilution water used durina ceriod liters 2.07 E+11 1.82 E+11 1.00 E+01 EFRLSRPT.DS i

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Maine Yankee Atomic Power Station

' Effluent and Waste Disposal Semiannual Report i

Third and Fourth Quarters. 1989 Liould Effluents Continuous Mode Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd 4th

' Strontium Ci N/D*

N/D*

4.58 E-04 Strontium-90 Ci N/D*

N/D*

Cesium-134-Ci N/D*

N/D*

1.17 E-04 1.10 E-03

._ Cesium-137 Ci 2.81 E-06 4.40 E-06 7.68 E-04 6.03 E-03 lodine-131 Ci' N/D*

2.94 E-07 5.94 E-06 7.25 E-04 Cobatt-58' Ci 8.40 E-08 6.62 E-06 1.71 E-03 8.61 E-03 Coba t-60 Ci-3.31 E-05 2.62 E-04 9.65 E-03 5.06 E-03 Iron-59 Ci N/D*

N/D*

Zinc-65 Ci N/D*

N/D*

i Manamnese-54 Ci N/D*

1.18 E-06 1.21 E-05 2.38 E-04 l'

Chromium-51 Ci 1.70 E-05 3.39 E-06 N/D*

4.14 E-05 Zirconium-Niobium-95 Ci 9.88 E-07 1.53 E-06 3.67 E-06 2.57 E-05 Molybdenum-99 Ci N/D*

N/D*

Technetium-99m Ci N/D*

N/D*

3.25 E-05 Barium-Lanthanum-140 Ci 8.59 E-07 N/D*

4.52 E-05 5.28 E-04 Cerium-141 Ci N/D*

N/D*-

N/D*

Others Iron-55 Ci N/D*

N/D*

9.08 E 3.30 E-03 S11ver-110m Ci N/D*

N/D*

3.88 E-03 1.75 E-03 i

Iodine-133 C1 2.20 E-07 N/D*

N/D*

1.86 E-04 Antimony-124 Ci N/D*

N/D*=

3.45 E-04 4.28 E-03 Antimony-125 C1 3.41 E-06 N/D*

2.42 E-03 3.94 E-03_

Tellurium-132 Ci 6.08 E-07 2.99 E-08 N/D*

9.06 E-08 Cerium-144 Ci 4.58 E-06 2.18 E-06 N/D*

N/D*

L Cobalt-57 Ci N/D*

4.05 E-07 2.47 E-05 1.29 E-05 Tin-113 Ci N/D*

N/D*

4.72 E-05 N/D*

Lanthanum-142 Ci 1.68 E-06 8.82 E-08 N/D*

N/D*

t Tellurium-133m Ci 6.75 E-06 1.34 E-06 N/D*

N/D*

Barium-139 C1 4.87 E-05 N/D*

N/D*

Yttrium-91m Ci 1.23 E-06 N/D*

N/D*

5,66 E-05 Ruthenium-103 Ci N/D*

9.09 E-07 N/D*

N/D*

Iodine-135 Ci N/D*

N/D*

2.21 E-05 Strontium-91 Ci N/D*

N/D*

5.13 E-05_

Tellurium-134 Ci N/D*

N/D*

1x74 E-03 c

l' Unidentified Ci N/D*

N/D*

Total for oeriod (above)(1) Ci 1.22 E-04 2.84 E-04 2.81 E-02 3.82 E-02 Xenon-133 C1 4.74 E-06 3.22 E 2.49 E-04 9.93 E-02 Xenon-133m Ci 5.80 E-06 7.14 E-07 N/D*

1.47 E-03 Xenon-131m C1 2.53 E-05 8.10 E-07 N/D*

3.25 E-04 Xenon-135 C1

-6.56 E-06 2.60 E-06 N/D*

1.24 E-03 Krvoton-88 Ci 5.87 E-08 2.67 E-07 N/D*

N/D*

l Krvoton-87 Ci N/D*

1.04 E-05 N/D*

N/D*

N/D* - Not Detected i

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(1) - Total for period does not include unidentified in this summation but is L

included in Table 2A, Item A1, t

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TABLE 3' Maine' Yankee Atomic Power Station l

Effluent and Waste Disposal Semiannual Report Third and Fourth Ouarters. 1989 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. %

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1. Type of Waste-l

a. Spent resins, filter sludges, evaporator m'

19.9 i 10 bottoms. etc. - LSA container **.+++

Ci 175.14 b.- Dry compressible waste, contaminated m'

87.7 1 10 eouinment. etc. - LSA container +.++

Ci 4.0

c. Irradiated components, control rods, m'

0 etc.

Ci 0

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C1 e.

m' Ci

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

a. Co-60

-33.1%-

olus or minus 10%

Cs-137 22.6%

olus or minus '10%

Cs-134 16.9%

olus or minus 10%

Fe-55 14.4%

olus or minus~ 10%

Ni-63 4.4%

olus or minus 10%

Co-58 3.8%

olus or minus 10%

C 1.5%

olus or minus 10%

Mn-54 1.2%

olus or minus 10%

b. Fe-55 26%

olus or minus 10%

<Co 22%

olus or minus 10%

Ni-63

'14%

olus or'minus 10%

Co-58 11%

olus or minus 10%-

Co-137 10%

olus or minus 10%

Zr-95 5%

olus or minus 10%

Co-134 3%

olus or minus 10%

'l Sb-125-2%

olus or minus '10%

. 3.-Solid Waste Disposition a

Number of Shioments Mode of Transoortation Destination

.From Maine Yankee 9 Trucking over Highway Chem-Nuclear, Barnwell, S.C.

From SEG #

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

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-B. Irradiated Fuel. Shipments (Disposition)

+ Standard SEG Container equal to 45ft'

. ++ Container volume equal to 110 ft* (boxes).

+++ High Integrity Containers with volumes of 28, 58 or 170 ft'

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Solid waste 19 Class A, as defined in 10CFR61.55.

92.6 m',

4.14 Ci

Solid waste is Class B, as defined in 10CFR61.55 14.2 m',

172.1 Ci

-Solid waste is Class C, as defined in 10CFR61.55 0.8 m',

2.9 Ci o* Solidification agent 11s cement.

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

.SEG performs super compacting of DAW.

EFRLSRPT.DS

TABLE 4 Suonlemental Information

{

1.

Reaulatory limits

{

Marian = Permissible Concentration i

a.

Fission and activation gases:

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

Iodines:

10CFR20; Appendix B, Table 2, Column 1 l

c.

Particulates, (with half lives greater than 8 days) 10CFR20; Appendix B, Table 2, Column I d.

Liquid effluents:

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

Total noble gas concentration 2E-04 uCi/ml l

2.

Averana Enerov - Not Aeolicable 3.

Measurements and Anoroximations of Radioactivity a.

Fission and Activation Cases Continuous Discharge - Vent stack samples are analyzed monthly. Activity lovels 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 tie 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. Liouid Effluents Samples of secondary systems' liquid effluents are analyzed weekly for gross beta-gamma, alpha, tritium, dissolved gases, and gamma emitting 'sotopes.

Each %tch release' is analyzed for gross beta-gamma, alpa, tritium, dissolved gasu, and gamma emitting isotopes prior to discharge.

Comg::ite 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 (CCntinued) 4.

Batch Releases a, Liouids 1.

Number of batch releases:

75 2.

Total time period for batch releases:

143 hours0.00166 days 0.0397 hours 2.364418e-4 weeks 5.44115e-5 months , 37 minutes 3.

Maximum time period for a batch release:

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 8 minutes 4.

Average time period for batch releases:

I hour, 55 minutes 5.

Minimum time period for a batch release:

15 minutes 6.

Average stream flow during periods of release of effluents into a flowing i

stream: N/A 7.

Maximum gross release concentration (uCi/ml):

2.33 E-07

b. Gaseous l.

Number of batch releases:

30 2.

Total time period for batch reenses:

352 hours0.00407 days 0.0978 hours 5.820106e-4 weeks 1.33936e-4 months , 31 minutes 3.

Maximum time period for a batch release: 105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months , 28 minutes 4.

Average time period for batch releases:

11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , 45 minutes 5.

Minimum time period for a batch release:

15 minutes 6.

Maximum gross release rate (uC1/sec): 8.50 E+02 f

5.

Abnormal Releases

a. Liouid

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On October 19, 1989 while in the process of transferring waste resin, water inadvertently overflowed from the vent on the top of the resin storage tank.

Approximately 15 gallons escaped from the building and was released down a nearby storm drain. Activity associated with this release was determined to be less than 0.001 curies, and was within regulatory limits. The specific isotopic i

activity associated with the release is included in Tables 2A and 28.

b. Gaseous There were no abnormal gaseous releases during the reporting period.

6.

On-line Containment Purae On-line containment purge was employed for 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months and 20 minutes during this reporting period, which is the total time it was utilized during 1989.

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i 4PPENDIX A Radioactive Effluent Monitorino Instrumentation Reauirement:

Radioactive effluent monitoring instrumentation channels are required to be i

operable in accordance with Technical Specifications 3.28.A & B, With less than the minimum number of channels operable and reasonable efterts to return the instrument (s) to operable status within 30 days bcing i

unsuccessful, Technical Specifications 3.28.A & B requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

Resnonse:

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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I APPENDIX B L,iouid Radwaste Treatment System I

Reoutrement:

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 Con. mission in the Semiannual Effluent Release Report for the period.

Resoonse:

The requirements of Technical Specification 3.17.C.1 were met during this l

period and, therefore, no report is required.

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4 APPENDIX C Gaseous Radwaste Treatment System I

Reauirement:

With radioactive gaseous waste being discharged without treatment with i

doses in excess of the limits in Technical Specifications 3.18.D.1, a 4

L..

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

.i period and, therefore, no report is required.

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APPENDIX D j

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Lower Limit of Detection for Radioloaical Analyses i

Reouirement:

Technical Specification 4.13 requires that when unusual circumstances result in LLD's higher than required, the reasons shall be documented in

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the Semiannual Radioactive Effluent Release Report.

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Resoonse:

Analyses were performed in such a manner that the stated LLD's were achievable under routine conditions. On one occasion the LLD's for Iron-59 and Zinc-65 in a liquid samsle was not met.

This was determined to be due to the presence of. detected ligher energy isotopes which caused a comptom background elevation. All other isotope LLD's in that sample were met. On all occasions, the specified LLD's were attained on the gaseous

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samples.

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APPENDIX E 4

P Reactor Coolant System Activity l

Rgouirements:

Technical Specification 5.9.1.3.B requires that a report, covering the I

results of specific activity analysis in which the primary coolant l

exceeded the limits of Specification 3.2, be submitted annually for j

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 radiciodine performed prior to l

exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.

Each result to include date and time of sampling and the radiciodine concentrations; 3 Clean-up systam flow history i

starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the f rs)t sample-in which the limit was 1

exceeded; (4) Graph of the iodine-131 concentration and one other radiciodine 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 radiciodine limit.

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

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ML20012B423

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Subject:

1.0 INTRODUCTION

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ML20012B423

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Reference:

Subject:

1.0 INTRODUCTION

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