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Semiannual Effluent Release Rept,Jan-June 1987
	ML20237H928
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Site:	Maine Yankee
Issue date:	06/30/1987
From:	; Maine Yankee
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HAINE YANKEE AT0 HIC POWER COMPANY SEMIANNUAL EFFLUENT RELEASE REPORT January - June, 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.

I l' Appentjices A through E indicate the status of reportable items per the requirements of Technical Specifications 3.16.C, 3.17.0, 3.28.A, 3.28.8, 4.8.A, 4.13 and 5.9.1.6.

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TABLE 1A, c" _ Maine Yankee Atomic Power Station l

' Effluent and Haste Disoosal Semiannual Reoort e

First and Second Ouarters. 1987- I Gaseous Effluents - Summation of All Releases Uni t Quarter Quarter Est. Total

> 1st 2nd

Error. %

A. Fission and Activation Gases l 1

1. Total release Ci 5.73 E+02 2.o7 E+02 2.50 E+01

2. Averaae release rate for oeriod UCl/sec 7.29 E+01- 2.63 E+01

3. Percent of reaulatory limit % 2.26 E-01 7.87 E ,

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8. Iodines ]

1. Total-Iodine-131 Ci 5.08 E-04 7.83 E-04 2.50 E+01

2. Averaae release rate for oeriod UCi/sec 6.46 E-05 9.96 E-05

3. Percent of reaulatory limit % 5.67 E-05 8.68 E-04 C. ' Particul ates !

1. Particulate with T-1/2 1 8 days Ci 5.19 E-05 1.1.3 E-03 2.50 E+01 4 UCi/sec 6.60 E-06 1.44 E-04

2. Averaae release rate for'oeriod

3. Percent of reae!atory limit % 5.67 E-05 1.44 E-04

4. Gross aloha radioactivity Ci 1.25 E-07 1.28 E-08 ,

D. Tritium

1. Total release Ci 6.05 E-01 8.50 E-01 2.50 E+01

2. Averace release rate for oeriod uCi/sec 7.69 E-02 1.08 E-01 ;

3. Percent of reaulatory limit % 3.37 E-04 4.74 E-04 ;

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c s TABLE 13 Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Reoort 1 First and Second Ouarters. 1987 !

Gaseous Effluents - Elevated Release' )

l Cor.tinuous Mode Batch Mode I Nuclides Released Uni t_ Quarter Quarter Quarter Quarter !

3rd 4th 3rd 4th j 1

1, Fission Gases Krvoton-85 Ci N/D* N/D* 5.13 E+00 5.80 E-02 Krvoton-85m Ci N/D* N/D* 8.63 E-05 N/D* i Krvoton-87 Ci N/D* N/D* N/D* N/D*

Kryoton-88 Ci N/D* N/D* N/D* N/D*

___ Xenon-133 Ci 4.68 E+01 N/D* 5.09 E+02 2.00 E+02 Xenon-135 Ci N/D' N/D* 1.07 E+01 1.14 E-02 .

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* 1.24 E+00 5.94 E-01 i Araon-41 Ci N/D* N/D* N/D* N/D* t Xenon-131m Ci N/D* N/D* 3.11 E-01 6.88 E+00 l Unidentified Ci N/D* N/D* N/D* N/D*

Total for oeriod Ci N/D* N/D* 5.26 E+02 2.07 E+02 l !

2. Iodines Iodine-131 Ci '5.08 E-04 7.83 E-04 N/D* N/D*

Iodine-133 C1 1.26 E-04 N/D* N/D* N/D* ;

Iodine-135 Ci N/D* N/D* N/D* N/D* !

Total for oeriod Ci 6.34 E-04 7.83 E-04 N/D* N/D*

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3. Particulate Strontium-89 Ci N/D* N/D* N/D* N/D*

Strontium C1 N/D* N/D* N/D* N/D* ;

Cesium-134 Ci N/D* 5.59 E-06 N/D* N/D* i l Cesium-137 Ci N/D* 2.53 E-05 N/D* N/D*

Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/0* ._

Ruthenium-103 Ci N/D* 9.81 E-04 N/D* N/D*

Cobalt-58 Ci N/D* 3.84 E-06 N/D* N/D* 0 Cobalt-60 Ci 1.08 E-06 3.59 E-05 N/D* N/D*

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oN/D - Not Detected l

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, TABLE IC ,

Maine Yankee Atomic Power StatioD Effluent and Haste Discosal Semiannual Reoort first and Second 00arters 1987 Gaseous Effluents - Ground Level Releasos 1 i

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There were no routine measured ground level continuous or batch mode gaseous l l

releases during.the first and second quarters of 1987.

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- l s TABLE 2A Maine Yankee Atomic Power Station Effluent and Haste Discosal Semiannual Renori First and Second Ouarters. 1987 Liauid Effluents - Summation of All Releasg1 Unit Quarter Quarter Est. Total !

1st 2nd Error. % j A. Fission and Activation Products

1. Total release (not including tritium. aases. aloha) Ci 7.80 E-02 6.12 E-01 1.50 E+01

2. Average diluted concentration durina ceriod uCi/ml 3.82 E-10 1.30 E-08

3. Percent of acolicable limit % 7.05 E-02 3.35 E-01

8. Tritium

1. Total release Ci 2.97 E+01 8.51 E+00 1.50 E+01

2. Average diluted concentration during ceriod uCi/ml 1.46 E-07 1.80 E-07 3 t

3. Percent of_Apolicable limit % 4.85 E-03 6.01 E-03 C. Dissolved'and Entrained Gases.

1. Total release Ci 1.35 E+00 1.33 E-01 1.50 E+01

2. Average diluted concentration irina ceriod UCi/ml 6.62 E-09 2.82 E-09

3. Percent of aoolicable limit % 3.33 E-03 1.41 E-03 D. Gross Alpha Radioactivity

1. Total release Ci 3.44 E-06 2.09 E-05 1.50 E+01

2. Average diluted concentration durina ceriod UCi/ml 1,69 E-14 4.43 E-13 E. Volume of waste released (prior to dilution) liters 1.30 E+07 1.92 E+07 1.00 E+01 F. Volume of dilution water used durina Deriod liters 2.04 E+11 4.72 E+10 1.00 E*01 4

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, TABLE 2B q Maine Yankee Atomic-Power Station Effluent and Haste Discosal Semiannual Reoort First and Second Ouarters. 1937 i Liauid Effluents l l

Continuous Mode Batch Mode J Nuclides Released Uni t Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd Strontium-89 Ci N/D* N/D* N/D* 1.30 E-03 l Strontium-90 Ci N/D* N/D* N/D* 3.76 E-04 )

_ Cesium-134 Ci N/D* N/D* 3.37 E-04 7.16 E-03 ]

Cesium-137 Ci N/D* N/D* 6.20 E-03 2.41 E-02 l Iodine-131 Ci N/D* N/D* 4.26 E-02 4.25 E-02 l.

Cobalt-58 Ci N/D* N/D* 1.31 E-04 1.34 E-01 l Cobalt-60 Ci N/D* N/D* 1.22 E-02 1.26 E-01 Iron-59 Ci N/D* N/D* N/D* N/D*

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

Mancanese-54 Ci N/D* N/D* N/D* 3.31 E-03 Chromium-51 Ci N/D* N/D* 5.30 E-04 1.12 E-02

)

Zirconium-Niobium-95 Ci N/D* N/D* 4.23 E-05 2.07 E-03 Molybdenum-99 Ci N/D* N/0* 2.11 E-04 2.93 E-05 Technetium-99m Ci N/D* N/D* 3.07 E-04 3.68 E-05 l Bari um-Lanthanum-140 Ci N/D* N/D* 1.76 E-03 3.08 E-03 Cerium-141 Ci N/D* N/D* N/D* 4.54 E-04 t Others Antimonv-122 Ci 2.45 E-05 5.16 E-05 Antjmonv-124 Ci N/D* 7.55 E-02 Antimonv-125 Ci N/D* N/D* 6.31 E-04 1,41 E-02

, Silver-110M Ci N/D* N/D* 1.71 E-03 8.51 E-03 Iodine-133 Ci N/D* N/D* 9.29 E-04 2.08 E-03 Ru thenium-103 Ci N/D* N/D* 1,66 E-05 1.66 E-03 i Tel l urium-L32 Ci N/D' N/D* 3.11 E-05 N/d* 1 Ce ri um-144 Ci N/D* N/D* N/D* 5.94 E-04 Tin-113 Ci N/D* N/D* N/D* 1,57 E-04 Cobalt-57 Ci N/D* N/D* N/D* 2.71 E-4 1

. Iron-55 Ci N/D* N/D* 1.02 E-02 1.53 E-01 1

_, . iden ti fi ed Ci N/D* 1.00 E-04 N/D* N/D* l Total for oeriod (above)(1)Ci 0.00 E+01 0.00 E-01 7.80 E-02 6.12 E-01 l

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Xenon-133 Ci N/0* N/D* 1.32 E+00 1.32 E-01 I Xenon-135 Ci N/D* N/D* 6.13 E-03 1.24 E-04 Xenon-131M Ci N/D* N/D* 1.36 E-02 N/D*

Xenon-133M Ci N/D* N/D* 1.45 E-02 4.93 E-04 Krvoton-85M Ci N/D* N/D* 1.32 E-04 N/D* l N/D* - Not Detected (1) - Total for period does not include unidentified in this summation but is

ncluded in Table 2A, Item A1.

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' TABLE 3 1 i

Maine Yankee Atomic Power Station )

Effluent and Haste Discosal Semlannual Renort J

First and Second Ouarters.'1987 .

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

Unit 6-Honth Est. Total

_?eriod Error. %

1. Type of Haste !

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a. Spent resins, filter sludges, evaporator m3 10.11 1 10 bottoms. etc. - LSA container **.+++ Ci 183.34

b. Dry compressible waste, contaminated m3 60.41 10 i eauioment. etc. - LSA container +.++ C1 1.32

c. Irradiated components, control rods, m3 etc. Ci

d. m3 Ci

e. m3 Ci

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

a . Co-60 23% + 10%

10%

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Cs-137 12% +

Fe-55 10% +. 10% 1 Ni-63 37% + 10% l H-1 , 17% + 10%

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b. Co-60 14% + 10% q 1

Cs-137 29% + 10% . _

Ni-63 23% + 10% !

Fe-35 26% + 10% l Cs-124 8% + 10% (

3. Solid Haste Disposition Number of Shioments Mode of Transportation Destination )

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

2 Trucking over Highway U.S. Ecology, Richland, WA B. Irradiated Fuel Shipments (Disposition)

+ Container volume equal to 55 gal ons (drums).

++ Container volume eaual to 110 ft (boxes).

n + Container volume equal to 170 ft (liners) (HIC)

Solid waste is Class A, as defined in 10CFk61.55. 60.41 m3, 1.32 Ci

Solid waste is Class B, as defined in 10CFR61.55 10.11 m3, 183.34 Ci i

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

- Solidification agent is cement.

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

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TABLE 4 l -

Sucolemental Information

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 1 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/mi

2. Averaae Enerav - Not Acolicable

3. Measurements and Acoroximations of Radioactivity

a. Fission and Activation Cases L

Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels 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 Discharcjes - Direct measurement's of the waste gas hold-up drums are l taken prior to discharge. Containment vents and purges are analyzed by I direct measurement of the containment atmo;phere at periodic intervals l during dis::harge. ]

b. . Iodines l

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

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c. Particulate l Primary vent stack particulate totals are taken from a minimum of weekly l measurements of an in-line particulate filter. l

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 l

effluents for a qucrterly analysis of Strontium =90 and Strontium-89.

Primary system liquid effluents are also analyzed quarterly for Iron-55.

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. 1 TABLE 4 ;

(Continued) l

4. Batch Releases

a. Licuids

1. Number of batch releases: 112

2. Total time period for batch releases: 845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months , 52 minutes

3. Maximum time period for a batch release: 157 hours0.00182 days 0.0436 hours 2.595899e-4 weeks 5.97385e-5 months , 10 minutes

4. Average time period for batch releases: 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , 33 minutes

5. Minimum time period for a batch release: 2 minutes

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

7. Maximum gross release concentration (uC1/ml): 2.23 E-05

b. Gaseous l '. Number of batch releases: 52 l

-2. Total time period for batch releases: 2319 hours0.0268 days 0.644 hours 0.00383 weeks 8.823795e-4 months , 17 minutes !

3. Maximum time period for a batch release: 608 hours0.00704 days 0.169 hours 0.00101 weeks 2.31344e-4 months , 6 minutes

4. Average time period for batch releases: 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months , 36 minutes

5. Minimum time period for a batch release: 15 minutes

6. Maximum gro'ss release rate (uCi/sec): 3.74 E+04

5. Abnormal Releases

a. Liquid (See Appendix B)

b. Gaseous (See Appendix B)

6. On-Line Containment Purae On-line containment purge was employed for a total of 107 hours0.00124 days 0.0297 hours 1.76918e-4 weeks 4.07135e-5 months and 27 minutes during the reporting period.

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4 APPENDIX A Radioactive Liauid Effluent Monitorina Instrumentation Requirement: 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 chanr.els 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 j

in the next Semiannual Effluent Release Report. !

l Reinonig: As of January 10, 1987, the air ejector monitor had been inoperable !

in excess of 30 days. Several attempts were made to restore tne l monitor to operation by replacing the detector, in kind. These proved unsuccessful with continued moisture induced failures.

Ult 3mately, the detector was replaced with a different model, designed to be moisture resistant. Due to the lack of appropriate response curves, however, it has yet to be declared operable. To rectify this, a primary source calibration is scheduled in the near 1 future.

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APPENDIX B Unolanned Radioactive Effluent Releases

.Reauiremeqti Technical Specification 5.9.1.6 requires that the Semlannual Effluent Release Report shall include a list and description of unplanned releases from the site-to-site boundary of radioactive materials in i gaseous and liquid effluents made durir.g the reporting period.

Resoonse: During the reporting period, there were two abrormal radioactive l

effluent releases, one liquid and one gaseous. Each of these is described below.

j a. On February 25, 1987, a leak occurred in a Refueling Water l Storage Tank heater flangs. Approximately 3400 gallons was released to a storm drain which leads to the normal plant I

discharge before the leak was isolated. Activity associated with this release was determined to be 0.0874 curies, and was well within regulatory limits. The specific isotopic activities assor.iated with this release are included in Tables 2A and 28.

b. Gaseous While administratively releasing Haste Gas Tank-D on June 18,

- 1987, approximately.300 cubic feet from Haste Gas Tank-E was i

, inadvertently released. Upon recognition of the problem, the release of Tank-D was immediately secured, which stopped both releases. Investigation found imprcporly seated valves in a common header to both tanks. The release was determined to have been less than 6 uCi. This activity is incorporated in Tables lA and 18.

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APPENDIX C Liauid Radwaste Treatment System !

BJtauirement: 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.

Bm ponse:. 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 0 Gaseous Radwaste Treatment System Bgauirement: With 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

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Semiannual Effluent Release Report for the period. l Resoonse: The requirements of Technical Specification 3.18.0.1 were met during .

-this period and, therefore, no report is required. '

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-APPENDIX E )

1 Lower Limit of Detection for Radioloalcal Analyses Roautrementi 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.

RRsoonse: Analyses were performed in such a manner that the stated LLO's were achievable under routine conditions. On several occasions, however, the presence of detected higher energy isotopes caused a Compton background elevation. This interference was sufficient to make the specified LLO's in those liquid samples unattainable.

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ML20237H928

Text

1.0 INTRODUCTION

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