Text

Myap Annual Radioactive Effluent Release Rept,Jan-Dec 1997
	ML20217N674
Person / Time
Site:	Maine Yankee
Issue date:	12/31/1997
From:	; Maine Yankee
To:	;
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ML20217N673	List: ML20217N667; ML20217N674; ML20217N682; ML20217N699;
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_ . . .

MAINE YANKEE ATOMIC POWER COMPANY ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 1997

1.0 INTRODUCTION

Tables 1 and 2 summarize the quantity of radioactive gaseous 'and liquid effluents, respectively, for each quarter of 1997. Table 3 summarizes the solid waste shipped off-site for

. burial or disposal during 1997. Table 4 contains supplementary information.

Appendices A through D indicate the status of reportable items per the requirements of Off-site Dose Calculation Manual (ODCM) sections 2.1.5, 2.2.6, 2.3.3, 2.3.4, 2.5 and Appendix C.

There were no changes to the ODCM during 1997.

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I TABLElA Maine Yankee Atomic Power Station I Effluent and Waste Disposal Annual Report First and Second Quarters,1997 Gaseous Effluents - Summation of All Releases )

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

A. Fission and Activation Gases

1. Total release Ci 4.14E+01 N/D* 2.50 E+01 l

l 2. Average release rate for period Ci/sec 5.28E+00 N/D*

l 3. Percent of regulatory limit % 8.36E-03 N/D*

l B. lodines

1. Total Iodine-131 Ci 1.19E-05 N/D* 2.50 E+01 1

2. Average release rate for period pCi/sec 1.51E-06 N/D*

! l l 3. Percent of regulatory limit % 6.64E-06 N/D*

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C. Particulates

1. Particulates with T-1/2 > 8 days Ci 1.63E-05 3.27E-06 2.50 E+01

2. Average release rate for period Ci/sec 2.07E-06 4.16E-07

3. Percent of regulatory limit % 3.64E-05 7.30E-06

4. Gross alpha radioactivity Ci 5.16E-07 N/D* l

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D. Tritium

1. Tc,tal release Ci 1.26E+01 1.19E+01 2.50 E+01

2. Average release rate for period Ci/sec 1.59E+00 1.51 E+00

! 3. Percent of regulatory limit % , 1.43E-02 1.35E-02 l

ll N/D* = Not Detected j

TABLE 1A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report ;

Third and Fourth Quarters,1997 l Gaseous Effluents - Summation of All Reles Unit 3rd 4th Est. Total Quarter Quarter Error, %

A. Fission and Activation Gases l

1. Total release Ci N/D* N/D* 2.50 E+01 ;

2. Average release rate for period pCi/sec N/D* N/D* l

' 3. Percent of regulatory limit % N/D* N/D*

B. Iodines ,

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1. Total Iodine-131 Ci N/D* N/D* 2.50 E+01

2. Average release rate for period pCi/sec N/D* N/D*

3. Percent of regulatory limit % N/D* N/D*

C. Particulates l

1. Particulates with T-1/2 > 8 days Ci 6.18E-06 N/D* 2.50 E+01 l

2. Average release rate for period pCi/sec 7.86E-07 N/D*

3. Percent of regulatory limit % 1.25E-05 N/D*

4. Gross alpha radioactivity Ci NID* 1.23E-07 D. Tritium

1. Total release Ci 2.68E+00 2.79E+00 2.50 E+01

2. Average release rate for period pCi/sec 3.41 E-01 3.55E-01

3. Percent of regulatory limit % 3.07E-03 3.20E-03 l

l N/D* = Not Detected Q _ _

I TABLEIB Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters,1997 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode i 1

Nuclides Released Unit 1st 2nd 1st 2nd 1 Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-85 Ci N/D* N/D* 8.30E+00 N/D*

Krypton-85m Ci N/D* N/D* N/D* N/D*

Krypton-87 Ci N/D* N/D* N/D* N/D*

Krypton-88 Ci N/D* N/D* N/D* N/D*

Xenon-131m Ci N/D* N/D* 3.34E+00 N/D*-

Xenon-133 Ci. 2.90E+00 N/D* 2.69E+01 N/D*

Xenon-133m Ci N/D* N/D* 1.08E-03 N/D*

Xenon-135 Ci N/D* N/D* N/D* N/D*

1 Xenon-135m Ci N/D* N/D* N/D* N/D*

Xenon-138 Ci N/D* N/D* N/D* N/D*

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

Total for period Ci 2.90E+00 N/D* 3.85E+01 N/D*

2. Iodines !

Iodine 131 Ci N/D* N/D* 1.19E-05 N/D*

Iodine-133 Ci N/D* N/D* N/D* N/D*

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

Total for period Ci N/D* N/D* 1.19E-05 N/D*

3. Particulates Strontium-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 Ci N/D* N/D* N/D* N/D*

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

"obalt-60 Ci N/D* 3.27E-06 1.63E-05 N/D*

N/D* = Not Detected

.TABLEIB Maine Yankee Atomic Power Station Effluent and Waste Dis sal Annual Report Thrid and Fourth uarters,1997 Gaseous Effluents - levated Release Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th-Quarter Quarter Quarter Quarter

1. Fission Gases

- Krypton-85 Ci N/D* N/D* N/D* N/D*

Krypton-85m . Ci N/D* N/D* N/D* N/D*

Krypton-87 Ci N/D* N/D* N/D* N/D*

Krypton-88 Ci N/D* N/D* N/D' N/D*

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

Xenon-133 Ci N/D* N/D* N/D* N/D*

Xenon-133m Ci N/D* N/D* N/D* N/D*

Xenon-135 Ci N/D* N/D* N/D* N/D*

Xenon-135m Ci N/D* N/D* N/D* N/D*

Xenon-138 ' Ci N/D* .N/D* N/D* N/D*

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

' Total for period Ci N/D* N/D*- N/D* N/D*

2. Iodines -

Iodine-131 Ci N/D* N/D* -N/D* N/D*

Iodine-133 Ci N/D* N/D* N/D* N/D*

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

Total for period Ci N/D* N/D* N/D* N/D*

3. Particulates Strontium-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 Ci 7.45E-07 N/D* N/D* N/D* I Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D*

Cobalt-60 Ci 5.44E-06 N/D* N/D* N/D*

- N/D* = Not Detected

i TABLEIC-Maine Yankee Atomic Power Station Effluent and Waste Disnosal Annual Report

! January - Decca ber,1997 Gaseous Effluents - Grocad Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during 1997.

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TABLE 2A l

Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters,1997 Liquid Effluents - Summation of All Releases Unit 1st Quarter 2nd Quarter- Est. Total l Error, % '

A. Fission and Activat i Products

1. Total release (not including tritium, Ci 4.84E-02 2.69E-02 1.50 E+01 gases, alpha)

2. Avgrage diluted concentration during pCi/ml 5.36E-09 2.96E-09 I penod

3. Percent of applicable limit % 6.13E-02 5.85E-02 B. Tritium

1. Total Release Ci 7.04E+01 3.92E4 01 1.50 E+01

2. Avgrage diluted concentration during pCi/ml 7.79E-06 4.31 E-06 penod

3. Percent of applicable limit % 7.79E-01 4.31E-01 C. Dissolved and Entrained Gases !

1. Total Release Ci 2.22E-02 N/D* 1.50 E+01

2. Avprage diluted concentration during pCi/ml 2.46E-09 N/D*

penod

3. Percent of applicable limit % 1.23E-03 N/D*

D. Gross Alpha Radioactivity

.1. Total release Ci N/D* 4.15E-07 1.50 E+01

2. Avgrage diluted concentration during pCi/ml N/D* 4.56E-14 i penod l I

E. Volume of waste released (prior to liters 3.86E+06 1.81E+06 1.00 E+01 dilution)

F. Volume of dilution water used during liters 9.04E+09 9.10E+09 1.00 E+01 period l

N/D* = Not Detected

i TABLE 2A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters,1997 Liquid Effluents - Summation of All Releases Unit 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission and Activation Products

1. Total release (not including tritium, Ci 4.00E-03 9.63E-03 1.50 E+01 gases, alpha)

2. Avprage diluted concentration during Ci/ml 3.42E-10 6.64E-10 penod

3. Percent of applicable limit % 3.37E-03 1.82E-02 B. Iritium

1. Total Release Ci 2.22E+00 1.55E+01 1.50 E+01

2. Avprage diluted concentration during pCi/ml 1.90E-07 1.07E-06 penod

3. Percent of applicable limit . % 1.90E-02 1.07E-01 C. Dissolved and Entrained Gases

1. Total Release Ci N/D* N/D* 1.50 E+01

2. Avprage diluted concentration during pCi/ml N/D* N/D*

penod

3. Percent of applicable limit % N/D* N/D*

D. Gross Alpha Radioactivity

1. Total release Ci N/D* N/D* 1.50 E+01

2. Avprage diluted concentration during pCi/ml N/D* N/D*

penod E. Volume of waste released (prior to liters 5.12E+05 5.16E+05 1.00 E+01 dilution)

F. Volume of dilution water used during liters 1.17E+10 1.45E+10 1.00 E+01 period i

N/D* = Not Detected L

TABLE 2B Maine Yankee Atomic Power Station Effluent and Waste Dis sal Annual Report First and Second uarters,1997 Liquid E uents Continuous Mode Batch Mode Nuclides Released Unit 1st 2nd 1st 2nd Quarter Quarter Quarter Quarter Strontium-89 Ci N/D* N/D* N/D* N/D*

Strontium-90 Ci N/D* N/D* N/D* N/D*

Cesium-134 Ci 3.40E-07 N/D* 2.86E-05 2.16E-04 Cesium-137 Ci 3.99E-07 N/D* 4.05E-04 2.46E-03 Iodine-131 Ci N/D* N/D* 1.61E-04 N/D*

Cobalt-58 Ci N/D* N/D* 4.61 E-03 1.59E-03 Cobalt-60 Ci N/D* N/D* 9.92E-03 5.27E-03 Iron-59 Ci N/D* N/D* 1.35E-04 N/D*

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

Manganese-54 Ci N/D* N/D* 3.16E-05 1.85E-06 Chromium-51 Ci N/D* N/D* 1.37E-03 2.75E-04 Zirconium-Niobium-95 Ci N/D* N/D* 6.81 E-04 2.14E-04 Molybdenum-99 Ci N/D* N/D* N/D* N/D*

Technetium-99m Ci N/D* N/D* N/D* N/D*

Barium-Lanthanum-140 Ci N/D* N/D* 2.03E-04 N/D*

Cerium-141 Ci .N/D

N/D* N/D* 7.42E-07 Others- Iron-55 Ci N/D* N/D* 1.63E-02 3.47E-03 Antimony-124 Ci N/D* N/D* 3.70E-03 1.98E-03 Antimony-125 Ci N/D* N/D* 8.71E-03 1.06E-02 Silver-110m Ci N/D* N/D* 2.11 E-03 7.79E-04 Tin-113 Ci N/D* N/D* 2.18E-05 1.62E-05 Ruthenium-103 Ci N/D* N/D* 1.55E-05 N/D*

Cerium-144 Ci N/D* N/D* N/D* 1.36E-05 Unidentified Ci N/D* N/D* N/D* N/D*

Total for period (above) Ci 7.39E-07 N/D* 4.84E-02 2.69E-02 Xenon-133 Ci 3.62E-05 N/D* 1.93E-02 N/D*

Xenon-135 Ci N/D* N/D* N/D* N/D*

Xenon-131m Ci N/D* N/D* 2.90E-03 N/D*

N/D* = Not Detected

TABLE 2B l

Maine Yankee Atomic Power Station Effluent and Waste Dis sal Annual Report Third and Fourt uarters,1997 Liquid E uents Continuous Mode Batch Mode Nuclides Released Unit 3rd 4th 3rd 4th Quarter Quarter . Quarter Quarter 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* 1.69E-06 7.77E-05 j Cesium-137 Ci N/D* N/D* 9.91 E-05 1.80E-03 Iodine-131 Ci N/D* N/D* N/D* N/D* :

Cobalt-58 Ci N/D* N/D* 1.64E-04 2.85E-04 Cobalt-60 Ci N/D* N/D* 6.35E-04 1.65E-03 Iron-59 Ci N/D* N/D* N/D* N/D*

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

Manganese-54 Ci N/D* N/D* N/D* N/D*

Chromium-51 Ci N/D* N/D* N/D* N/D* i Zirconium-Niobium-95 Ci N/D* N/D* N/D* N/D* )

Molybdenum-99 Ci N/D* N/D* N/D* N/D*

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Technetium-99m Ci N/D* N/D* N/D* N/D* )

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

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

Other - Iron-55 Ci N/D* N/D* 1.93E-03 4.33E-04 Antimony-124 Ci N/D* N/D* 4.78E-05 N/D*

Antimony-125 Ci N/D* N/D* 1.05E-03 5.33E-03 Silver-110m Ci N/D* N/D* 7.17E-05 5.67E-05 Unidentified Ci N/D* N/D* N/D* N/D*

Total for period (above) Ci N/D* N/D* 4.00E-03 9.63E-03 Xenon-133 Ci N/D* N/D* N/D* N/D*

Xenon-135 Ci N/D* N/D* N/D* N/D*

N/D* = Not Detected i

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l TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First Half,1997 ,

Solid Waste and Irradiated Fuel Shipments A. - Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel). ]

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i 6-Month Est. Total

1. Type of Waste. Unit Period Error. % _.

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a. Spend resins, filter sludges, etc. Cu.M. 1.3 Ci. 2.34E+00 +/-25 ,

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b. Dry compressible waste, contaminated Cu.M. 3.8 equipment, DAW, Cement. Ci. 8.76E-02 +/-25 4

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2. Estimate of major nuclide composition (by type of waste).

a. Co-60 44.80 % 1.05E+00 Fe-55 39.55 % 9.25E-01 Ni-63 11.69 % 2.74E-01 H-3 1.32 % 3.08E-02 Cs-137 1.06 % 2.48E-02

b. Co-60 31.10 % 2.74E-02 Ni-63 23.59 % 2.07E-02

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Fe-55 20.47 % 1.79E-02 I Co-58 14.11 % 1.24E-02 Cs-137 6.18 % 5.41 E-03 Ce-144 2.03 % 1.78E-03 Cr-51 1.01 % 8.80E-04 ,

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TABLE.3

- (Continued)

. 3. Solid Waste Disposition..

Number _ofShipments Mode _ofIransportation Destination 1 Trucking over Highway Chem-Nuclear, Barnwell, SC 5 Trucking over Highway Scientific Ecology Group (SEG), Oak Ridge, TN -

1 Trucking over Highway F.W. Hake, Memphis,- TN B. Irradiated Fuel Shipments (Disposition): None Shipped.

Additional ODCM Appendix C requirements.

. Volume Est. Activity >

Solid Waste Class (Cu. M.) (Ci) Est. Total Error A 4.6 2.58E-01 +/- 25%

B 0.0 0.00E+00 +/- 25%

C' O.5 2.17E+00 +/- 25%

Container. Type Package Volume (Cu.~ M.)

C-100 Strong Tight Container 2.9 Sealand Strong Tight Container 38.3 CNSI Small Overpack High Integrity Container 0.8 NUHIC-55 High Integrity Container 0.5

TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Second Half,1997 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel).

6-Month - Est. Total

1. Type of Waste. Unit Period Error,L

a. Spend resins, filter sludges, etc. Cu.M. 9.0 Ci. 2.26E+02 +/-25

b. Dry compressible waste, contaminated Cu,M. 9.3 equipment, DAW, Cement. Ci. 8.88E-02 +/-25

2. Estimate of major nuclide composition (by type of waste).

a. Ni-63 33.78 % 7.53E+01 Cs-137 25.84 % 5.76E+01 Co-60 19.51 % 4.35E+01 Fe-55 12 ?8 % 2.76E+01 Cs-134 7.22% ' l.61E+01 Sb-125 1.26 % 2.81 E+00

b. Co-60 33.86 % 3.01 E-02 Ni.63 25.68 % 2.28E-02 Fe-55 18.27 % 1.62E-02 Co-58 7.90 % 7.01 E-03 Cs-137 8.64 % 7.67E-03 Ce-144 2.28 % 2.02E-03 H-3 1.99 % 1.76E-03 i

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i TABLE 3-(Continued) 1 l

3.- ' Solid Waste Disposition .

Number _ofShipments _ ' Mode.of_ Transportation Destination

! 2- Trucking over Highway- Chem-Nuclear, Barnwell, SC l- 1 Trucking over Highway.:- Scientific Ecology. Group

!~ > (SEG), Oak Ridge, TN i

1 Trucking over Highway Diversified Scientific Services Oak Ridge, TN -

1 Trucking over Highway Alaron Corporation, Wampum, PA R

B. Irradiated Fuel Shipments (Disposition): None Shipped.

1 Additional ODCM Appendix C requirements.

Volume Est. Activity Solid Waste Class (Cu. M.) - - (Ci) Est. Total Error' )

A 9.3 8.88E +/- 25%

B 9.0 2.26E+02 +/- 25% ;

C 0.0 0.00E+00 - - +/- 25%

1 Container Type Package Volume (Cu. M.)

C-100 Strong Tight Container 2.9 Sealand Strong Tight Container 38.3 Steel Drum - Strong Tight Container 0.2 Steel Drum Strong Tight Container <0.1 Sealand Strong Tight Container - 77.0

- NUHIC-120 High Integrity Container 4.5 l

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i TABLE _4 I l

Supplementallnformation

1. Regulatory 11mits Effluent _ 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 2

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

2. Average _ Energy _NotApplicable

3. Measurementsand App.mximations of. Radioactivity

a. Fission and Activation Gases ,

Continuous Discharge - Vent stack samples are analyzed monthly. Activity levels detemiined are assumed constant for the surveillance interval. The continuous vent stack monitor reading is used as a basis for increasing periodic sample frequency.

Eatch 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. 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. LiquidEffluents Samples of secondary systems liquid effluents are analyzed weekly for gross alpha, tritium, dissolved gases, and gamma emitting isotopes.

Each batch release is analyzed for gross 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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14. BatchReleases ;

a. : Liquids L

L 1.- Number of batch releases: 96

2. Total time period for batch releases: 558 hours0.00646 days 0.155 hours 9.22619e-4 weeks 2.12319e-4 months ,1 minute

3. Maximum time period for a batch release: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ,27 minutes

4. Average time period for batch releases: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ,48 minutes l- - 5. Minimum time period for a batch release: 20 minutes

6. . Average stream flow during periods of release of effluents into a

)

' flowing stream: N/A )

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7.' Maximum gross release concentration (pCi/ml): .1.24E '

- b. Gaseous

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- 1. -Number ofbatch releases: 55

2. Total time period for batch releases: 8572 hours0.0992 days 2.381 hours 0.0142 weeks 0.00326 months ,4 minutes ..

3. Maximum time period for a batch release: 1690 hours0.0196 days 0.469 hours 0.00279 weeks 6.43045e-4 months ,15 minutes

4. Average time period for batch releases: 155 hours0.00179 days 0.0431 hours 2.562831e-4 weeks 5.89775e-5 months ,51 minutes

5. Minimum time period for a batch release: 25 minutes .

6. Maximum gross release rate ( Ci/sec): 3.98E+03 3

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5. Unplanned. Releases <

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a. Liquid !

There were no abnormal liquid releases during the reporting period.

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

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6. On-Line_Containmentfurge ;

l On-line containment purge was not utilized during 1997, i i

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- APPENDIXA Radioactive _Effluentifonitoringlnstrumentation ,

L Requirement: Radioactive effluent monitoring instrumentation channels are required to be. <

L . operable in accordance with ODCM Sections 2.3.3 and 2.3.4. With less than the.

minimum number of channels operable and reasonable efforts lto retum' the i instrument (s) to operable status within 30 days being unsuccessful, ODCM

! Sections 2.3.3 and 2.3.4 requires an explanation for the delay in correcting the .

inoperability in the next Annual Effluent Release Report.

Response: The Service Water radiation monitor was out of service for the entire period of this

,. report. This condition resulted from three causes:

! . ' Lack of vacuum priming required to supply sample to the monitor. This was -

a result of the plant in shut down condition for the entire year, with the l vacuum priming system out of service.

. Inoperable sample pump due to mechanical failure. ;

- Insufficient sensitivity of the existing monitor, with inadequate margin to l establish the required setpoint in the low dilution flow environment.

Vacuum priming has been restored and the sample pump has been replaced, i: restoring the monitor to operation. Because the instrument sensitivity issue is still unresolved, however, the unit has not been declared operable and the remedial

action remains in effect. A replacement radiation monitor with greater sensitivity, which will provide sufficient setpoint margin, has been purchased to resolve this

l. issue. Installation of the replacement monitor is anticipated by May 31,1998.

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The Primary Vent Stack flow r::te meter remained inoperable for the entire penod of this report. Delay we.s experienced in scheduling a contract vendor, and performing the required traverse of the stack to verify the calibration of the unit.

The traverse was completed in December,1997, but the results did not meet the accuracy requirements, and were not accepted. A calibration by an alternate i methodology is scheduled for May,1998.

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I; AEP.ENDIX.B Liquid Radwastelreatment System Requirement: With radioactive liquid waste being discharged without treatment with estimated ;

doses in excess of the limits in ODCM Section 2.1.5, a report must be submitted to the Commission in the Annual Effluent Release Report for the period. ,

Response: The requirements of ODCM Section 2.1.5 were met during this period and, therefore, no report is required.

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APPENDIX.C GaseousRadwaste_TreatmentSystem -

. Requirement: With radioactive gaseous waste being discharged without treatment with doses in excess of the limits in ODCM Section 2.2.6, a report must be submitted to the

Commission in the Annual Effluent Release Report for the period.

' Response: The requirements of ODCM Section' 2.2.6 were met during this period and, therefore, no report is required.

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k AEPENDIX_D -

l Lowerlimit ofDetection for. Radiological Analyses

! Requirement: ODCM Section 2.5 requires that when unusual circumstances result in LLD's higher than required, the reasons shall_ be documented in the Annual Radioactive Efiluent Release Report.

l l Response: All samples were counted in such a manner as to satisfy the specified a priori lower limits of detection.

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ML20217N674

Text

1.0 INTRODUCTION

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