ML20206D779

Myap Annual Radioactive Effluent Release Rept,Jan-Dec 1998

ML20206D779
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Site:	Maine Yankee
Issue date:	12/31/1998
From:	Maine Yankee
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NUDOCS 9905040237
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. MAINE YANKEE ATOMIC POWER COMPANY l

l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January- December 1998

1.0 INTRODUCTION

l Tables 1 and 2 summarize the quantityofradioactive gaseous and liquid effluents, respectively, for each quarter of 1998. Table 3 summarizes the solid waste shipped off-site for burial ordisposal during 1998. Table 4 contains supplementary information.

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

4 Revisions of the ODCM made during 1998 are summarized at Appendix E. Pursuant to Technical Specification 5.6.2, a complete copy ofthe revised manual is also included with this report.

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e TABLElA Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First and Second Quarters,1998 Gaseous Effluents - Summation of All Releases 1 Unit 1st 2nd Est.

Quarter Quarter Total Error,%

A. Fission and Activation Gases

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

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

3. Percent of regulatorylimit  % N/D* N/D*

B. Iodines

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

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

3. Percent ofregulatorylimit  % N/D* N/D*

C. Particulates

1. Particulates with T-1/2 > 8 days Ci N/D* N/D* 3.50 E+01

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

3. Percent ofregulatory limit  % N/D* N/D*

4. Gross alpha radioactivity Ci N/D* N/D*

D. Tritium

1. Total release Ci 3.34E+00 3.90E-01 2.50 E+01 ,

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2. Average release rate for period Ci/sec 4.25E-01 4.96E-02

3. Percent ofregulatorylimit  % 3.83E-03 1.09E-03 I

i N/D* = Not Detected l l

TABLE 1A Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Third and Fourth Quarters,1998 Gaseous Effitients - Summation of All Releases Unit 3rd 4th Est.

Quarter Quarter Total Error,%

A. Fission and Activation Geras

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

2. Average release rate [oheriod Ci/sec N/D* N/D*

3. Percent of regulatorylimit  % N/D* N/D*

B. Iodines

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 regulatorylimit  % N/D* N/D*

C. Particulates

1. Particulates with T-1/2 > 8 days Ci N/D* N/D* 3.50 E+01  !

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

3. Percent oDegulatorylimit  % N/D* N/D*

4. Gross alpha radioactivity Ci 2.17E-07 N/D*

D. Tritium

1. Total release Ci 1.04E+00 5.06E-01 2.50 E+01  ;

2. Average release rate for period Ci/sec 1.32E-01 6.43E-02

3. Percent ofregulatorylimit  % 9.11E-03 3.54E-03  !

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l N/D* = Not Detected j

l TABLEIB l Maine Yankee Atomic Power Station Effluent and Waste Dis sal AnnualReport First and Second uarters,1998 Gaseous Effluents - levated Release Continuous Mode Batch Mode Nuclides Released Unit 1st 2nd 1st 2nd ,

Quarter Quarter Quarter Quarter I

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

l 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* l 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* l 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/A** N/D* N/D*

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

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

Total for period Ci N/D* N/A** 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* l 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* l Cobalt-60 Ci N/D* N/D* N/D* N/D* I i

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l N/D* = Not Detected N/A** = Not Applicable (ODCM Revision 7)

c-TABLEIB Maine Yankee Atomic Power Station Effluent and Waste Dis sal Annual Report Third and Fourth uarters,1998 t 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* i

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

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

Iodine-131 Ci N/A*

• N/A** N/D* N/D*

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

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

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

Barium-Lanthanum-140 Ci N/D* N/D* N/D* N/D* l 1

Cobalt-60 Ci N/D* N/D* N/D* N/D* l l

N/D* = Not Detected i N/A** = Not Applicable (ODCM Revision 7)  !

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TABLE 1C Maine Yankee Atomic Power Station

! Effluent and Waste Disposal Annual Report January- December,1998 l_ Gaseous Effluents - Ground Level Releases i

! There were no routine measured gmund level continuous or batch mode gaseous releases during1998.

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Fr, TABLE 2A l Maine Yankee Atomic Power Station  !

l' Effluent and Was 1 Disposal Annual Report First and Sewad Quarters,1998 Liquid Effluents - Summation of All Releases l

Unit 1st 2nd Est.  !

Quarter Quarter Total Error, %

A. Fission and Activation Products

1. Total release (not including tritiurt, Ci 2.61 E-02 1.26E-01 1.50 gases, alpha) E+01

.2. Average diluted concentration pCi/ml 2.69E-09 8.66E-09 i during period

3. Percent of applicable limit -  % 3.24E-02 2.03E-01 B. Tritium

1. Total Release Ci 3.63E+00 4.03E+01 1.50 E+01

2. Average diluted concentration pCi/ml 3.74E-07 2.76E-06 during period

3. Percent of applicable limit  % 3.74E-02 2.76E-01 C. Dissolved and Entrained Gases

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

2. Average diluted concentration Ci/ml N/D* N/D*

during period

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

D. Gross Alpha Radioactivity

1. Total release Ci 4.82E-06 1.13E-06 1.50 E+01

2. Average diluted concentration pCi/ml 4.96E-13 7.74E-14 during period E. Volume of waste released (prior to liters 5.58E+05 2.36E+06 1.00 dilution) E+01 F. Volume of dilution water used liters 9.71E+09 1.46E+10 1.00 during period E+01 l

N/D* = Not Detected

TABLE 2A Maine Yankee Atomic Power Station l Effluent and Waste Disposal Annual Report Third and Fourth Quarters,1998 i Liquid Effluents - Summation of All Releases  !

Unit ' 3rd 4th Est. l Quarter Quarter Total Error,%

I A. Fissbn and Activation Products i 1. Total release (not including tritiurt, Ci 7.26E-02 5.59E-03 1.50 l l

gases, alpha) E+01

2. Average diluted concentration pCi/ml 4.77E-09 1.13E-09 during period )

I l 3. Percent of applicable limit  %- 1.46E-01 8.71E-03 l B. Tritium

1. Total Release Ci 5.40E+00 2.97E+00 1.50 E+01

, 2. Average diluted concentration pCi/ml 3.55E-07 6.02E-07 l during period

3. Percent of applicable limit  % 3.55E-02 6.02E-02 C. Dissolved and Entrained Gases .

- 1. Total Release Ci N/D* N/D* 1.50  !

l E+01

2. Average diluted concentration pCi/ml N/D* N/D*

during period

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

l D. Gross Alpha Radioactivity l 1. Total release Ci N/D* N/D* 1.50 E+01

2. Average diluted concentration pCi/ml N/D* N/D*

i during period l

E. Volume of waste released (prior to liters 6.24E+05 3.79E+05 1.00 dilution) E+01 l

F. Volume of dilution water used liters 1.52E+10 4.93E+09 1.00 during period E+01 l-j N/D* = Not Detected

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TABLE 2B 1 Maine Yankee Atomic Power Station  !

Effluent and Waste Dis sal Annual Report First and Second uarters,1998 l 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* NiD* l Cesium-134 Ci 6.80E-06 N/D* 3.32E-05 7.81E-04 Cesium-137 Ci 4.19E-05 N/D* 9.53-04 1.71E-02 Iodine-131 Ci N/D* N/D* N/D* N/D*

Cobalt-58 Ci N/D* N/D* 1.08E-04 1.50E-04 Cobalt-60 Ci N/D* N/D* 4.37E-03 2.76E-02 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* 1.18E-05 2.20E-05 Chromium-51 Ci N/D* N/D* N/D* N/D*

Zirconium-Niobium-95 Ci N/D* N/D* 5.57E-06 N/D*

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* N/D* N/D*

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

Others- Iron-55 Ci N/D* N/D* 1.85E-03 1.46E-02 Antimony-125 Ci N/D* N/D* 1.87E-02 6.54E-02 Silver-110m Ci N/D* N/D* 3.13E-05 5.73E-04 Tin-113 Ci N/D* N/D* 2.53E-06 N/D*

Cerium-144 Ci N/D* N/D* N/D* 1.45E-04 Cobalt-57 Ci N/D* N/D* N/D* 1.06E-05 Unidentified Ci N/D* N/D* N/D* N/D*

Total for period (above) Ci 4.87E-05 N/D* 2.61E-02 1.26E-01 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 1

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m-TABLE 2B Maine Yankee Atomic Powcr Station Effluent and Waste Dis sal Annual Report Third and Fourth arters,1998 Liquid E ents 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*

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 4.53E-07 N/D* 1.02E-03 6.86E-05 Iodine-131 Ci N/D* N/D* N/D* N/D*

Cobalt-58 . Ci N/D* N/D* 6.10E-04 N/D*

Cobalt-60 Ci N/D* N/D* 6.31E-02 6.73E-04 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* M'D* N/D*

Chromium-51 Ci N/D* N/D* - NTD* N/D*

Zirconium-Niobium-95 Ci N/D* N/D* N/D* N/D* j Molybdenum-99 Ci N/D* N/D* N/D* N/D* l 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* 2.94E-03 1.08E-03 l Antimony-125 Ci N/D* N/D* 4.83E-03 3.77E-03 '

I Cobalt-57 Ci N/D* N/D* 9.95E-05 N/D*

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

Total for period (above) Ci 4.53E-07 N/D* 7.26E-02 5.59E-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

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TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report First Half,1998 Solid Waste and Irradiated Fuel Shipments

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

6-Month FA.Tdal

1. TypeofWaste.

Unit Period Ener. %

a. Spend resins, filter sludges, etc. Cu.M. 24.7 Ci. 3.09E+02 +/-25

b. Dry compressible waste, contaminated Cu.M. I1.0 equipment, DAW, Cement. Ci. 2.43E+00 +/-25

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

a. Co-60 38.87 % 1.20E+02 Ni-63 23.88 % 7.38E+01

. Cs-137 17.30 % 5.35E+01 l 1

Fe-55 9.09 % 2.81E+01 {

Cs-134 7.20 % 2.22E+01 Sb-125 2.13 % 6.58E+00

b. Co-60 38.41 % 9.33E-01 Fe-55 24.92 % 6.05E-01 Ni-63 21.25 % 5.16E-01 Cs-137 6.55 % 1.59E-01 Cc-144 5.33 % 1.30E-01 l Co-58 2.04 % 4.96E-02 l

TABLE 3 _

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3. Solid Waste Disposition Number of Shioments Mode ofTransoortation Destination 7 Trucking over Highway- Chem-Nuclear, Barnwell, SC 4 Trucking over Highway. Scientific Ecology Group (SEG), Oak Ridge, TN ,

3 Trucking over Highway F.W. Hake, Memphis, TN 1 Trucking over Highway. NSSI Recovery Services,Inc Houston, TX i l

2 Trucking over Highway GTS-Duratek, Oak Ridge, 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 26.7 1.04E+02 +/- 25%

B 8.95 ' 2.08E+02 +/- 25%

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

Container Type Package Volume (Cu. M.)

C-100 Strong Tight Container 2.9 Sealand Strong Tight Container 38.3 Steel Drum Strong Tigh't Container <0.1

' EL-142 High Integrity Container .. 3.7 NUHIC-120 - High Integrity Container 4.5

. Steel Box . Strong Tight Container 32.3 RADLOC-195 High Integrity Container - 5.5 Steel Box - Strong Tight Container 3.8 u -

TABLE 3 Maine Yankee Atomic Power Station Effluent and Waste Disposal Annual Report Second Half,1998 Solid Waste and Irradiated Fuel Shipments y A. _ Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel).

6-Month BtTod

1. TypeofWaste. Unit Period Fmt %

a. Spend resins, filter sludges, etc. Cu.M. 42.0 Ci. 7.37E+02 +/-25

b. Dry compressible waste, contaminated Cu.M. 132.1 equipment, DAW, cement.. Ci. 1.02E+00 +/-25

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

a. Co-60 31.95 % 2.35E+02 Ni-63 30.55 % 2.25E+02 Cs-137 20.18 % 1.49E+02 Fe-55 10.48 % 7.72E+01 Cs-134 3.62 % 2.67E+01

b. Co-60 38.44 % 3.92E-01 Ni-63 20.82 % 2.12E-01 Fe-55 25.18 % 2.57E-01 Co-58 2.09 % 2.13E-02 Cs-137 6.53 % 6.66E-02 Ce-144 5.52 % 5.63E-02 l

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TABLE 3 (Continued) l L . 3.' " Solid Waste Disposition -

. Number of Shioments Mode ofTransoortation Destination 10 Trucking over Highway Chem-Nuclear, Barnwell, SC 18 Trucking over Highway GTS-Duratek, Oak Ridge, TN l

L2 . Trucking over Highway Molten Metal Technologies Oak Ridge, TN l

3. . Trucking over Highway Chem-Nuclear Consolidation Facility Barnwell, SC i

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

- Additional ODCM Appendix C requirements.

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

'A .143 5.36E+01 +/- 25%

B 30.8 6.85E+02 +/- 25%

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

Container Type Package Volume (Cu. M.)

' EL-142 High Integrity Container 3.7 Sealand Strong Tight Container 38.3

, CNSI Small Overpack High Integrity Container 0.8 B-25 Steel Box Strong Tight Container 2.9 21-300 MT Poly Liner High Integrity Container 8.9 Steel Drum - High Integrity Container 0.3 l

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r TABLE 4 Sunnlemental Information  !

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1. Regulatorv Linits Effluent Concentration

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. a. . Fission and activation gases: 10CFR20; Appendix B, Table 2, Column 1 i I

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

c. ' Particulates,(with half l

lives greater than 8 days) 10CFR20; Appendix B, Table 2, Column 1 L d. Liquid effluents: 10CFR20; Appendix B, Table 2, Column 2 . ,

e.' Total noble gas concentration: 2E-04 pCi/ml  !

l' 2. Averane Enerav-Not Anolicable

3. Measurements and Anoroximations of Radioactivity

a. Fission and Activation Gases Continuous Discharge - Primary Vent Stack and Fuel Building Exhaust Vent samples are  !

analyzedmonthly. Activitylevelsdeterminedareassumedconstantforthesurveillanceinterval. I The continuous Fuel Building Exhaust Vent monitor reading is used as a basis for increasing periodic sample frequency.

Batch Discharges -The waste gas hold-up drums were purged and removed from service in 1997 in preparation for decommissioning. There were no discharges from this system in 1998. With the permanent cessation ofpower operations and the removal ofthe nuclear fuel, containment purgingoperationsarenolongerrequired. ContainmentventilationisdirectedtothePrimary Vent Stack, and sampled as described above.

- b. Iodines The requirement to sample the Primary Vent Stack foriodine was deleted by ODCM Revision 7 in March,1998,

c. Particulates Primary Vent Stack and Fuel Building Exhaust Vent particulate totals are taken from a minimum l

' ofweekly measurements ofcontinuously collected in-line particulate filters. The estimate total L error for the particulate measurement has been increased to 35%. This estimated error is based on a detailed evaluation ofsampling uncertainties with the newly installed particulate samplers.

In the decommissioning configuration, credit is not taken for HEPA filtration. Without verification testing ofthe filters, it must be assumed that sample line plate-out may increase by up to a factor ofthree. Measured particulate and alpha activityhas, therefore, been adjusted to account for this

possibility.

y TABLE 4 L (Continued) j d. - Liauid Effluents l

Until October,1998 when the Circulating and Service Water Systems were pennanently removed

_ from service, during periods ofdischarge, ramples ofsecondary systems liquid effluents were analyzed weekly for gross alpha, tritium, dissolved gases, and gamma emitting isotopes.

l Each batch ofpotentiallyradioactive liquid is analyzed for gross alpha, tritium, dissolved gases, and gamma emitting isotopes prior to discharge.

l Composite samples are made ofliquid effluents for a quarterly analysis of Strontium-9h Strontium-89, and Iron-55,

4. Batch Releases

a. Liauids

1. Number of batch releases: 62

2. Total time period for batch releases: 672 hours0.00778 days <br />0.187 hours <br />0.00111 weeks <br />2.55696e-4 months <br />,42 minutes

3. Maximum time period for a batch release: 227 hours0.00263 days <br />0.0631 hours <br />3.753307e-4 weeks <br />8.63735e-5 months <br />,10 minutes

! 4. Average time period for batch releases: 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, 51 minutes

5. Minimum time period for a batch release: 10 minutes

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

7. Maximum gross release concentration ( Ci/ml): 2.90E-08 l g

b. Gaseous )

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1. Number of batch releases: 1 i

2. Total time period for batch releases: 304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br />,40 minutes ,

3. Maximum time period for a batch release: 304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br />,40 minutes i

4. Average time period for batch releases: 304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br />,40 minutes 1

5. Minimum time period for a batch release: 304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br />,40 minutes

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6. Maximum gross release rate (pCi/sec): No detected activity '

5. Unolanned Releases i

a. Liquid I There were no abnormal liquid releases during the reporting period.

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

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l I B L.E 4 I (Continued)

6. On-Line Containment Puree Since the plant has permanently ceased power operation and the nuclear fuel has been removed from the reactor, on-line containment purging is no longer applicable.

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APPENDIX A J 1

Radioactive Effluent Monitorine Instrumentation Reauirement: Radioactive effluent monitoring instrumentation channels are required to be operable in accordance with ODCM Sections 2.3.3 and 2.3.4. With less than the minimum number ofchannels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful, ODCM Sections 2.3.3 and 2.3.4 requires an ,

explanation for the delayin correcting the inoperabilityin the next Annual Effluent Release Report.

Resoonse: The Service Water radiation monitor reported out ofservice, and described in the 1997 j annual report was replaced with a new unit with greater sensitivity. The new unit was placed in service on July 16,1998.

Measurement of the ventilation flows discharging to the Primary Vent Stack, also discussed in the 1997 annual report were completed, and the Primary Vent Stack flow rate meter was declared operable on August 12,1998. I

APPENDIX B Liauid Radwaste Treatment System Reauirement: 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.  !

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Resoonse: The requirements ofODCM Section 2.1.5 were met during this period and, therefore,

. no report is required.

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m APPENDIX C Gaseous Radwaste Treatment System Reauirement: With radioactive gaseous waste being discharged without treatment with doses in excess ofthe limits in ODCM Section 2.2.6, a report must be submitted to the Commission in the Annual Effluent Release Report for the period.

Resoonse: The requirements of 0DCM Section 2.2.6 were met during this period and, therefore, no report is required.

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a APPENDIX D l

Lower Limit of Detection for Radiological Analyses Reauirement: ODCM Section 2.5 requires that when unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Amiual Radioactive Effluent Release Report.

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

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p APPENDIX E i Summary of Off-Site Dose Calculation Manual Revisions Revision 5, approved January 21,1998 Con ected various typographical enurs and inserted applicable references to Technical Specifications

- Special Reports previously omitted. Radiological Environmental Monitoring Pmgmm (REMP) sample station distances and directions from the plant in Table 5.1, Radiological Environmental Monitoring Stations, were corrected based on results fmm the Global Positioning Survey. Containment Purge was deletal from Table 2.7, Gaseous Waste Sampling and Analysis Pmgmm, while Tritium sampling and analysis was added to the Primary Vent Stack surveillance, also in Table 2.7.

Revision 6, approved February 11,1998 Upgraded the methodology fordetermining Liquid Efiluent Monitor setpoints (intemal and extemal) in Section 6.1 by providing specific equations.

Revised the ODCM to be consistent with Amendment 161 of the Technical Specifications by:

Relocating the description of the Radiological Environmental Monitoring Program from Technical Specifications to ODCM Section 2.4.

=: Relocating the sample and analysis requirements for the incineration ofradioactive waste oil to a new ODCM Table 2.8, Radioactive Waste Oil Incineration Sampling and Analysis Porgram. i

. Included the requirement for the Estimated Dose and Meteorological Summary Report in the I list of routine reports in Appendix C. l Revised the specifications to reflect the "new" 10 CFR Part 20, Appendix B.

Revised the liquid and gaseous effluent by:

Deleting Steam Generatorblowdown monitoring and related Action n:quimments forinoperable ,

monitors in Table 2.1, Radioactive Liquid Effluent Monitoring Instrumentation, and the sample and analysis requirements in Table 2.6, Radioactive Liquid Waste Sampling and Analysis Program.

• Deleting the Waste Gas Holdup system Noble Gas Activity monitor and flow rate measurement, and the related Action requirement for inoperable instruments in Table 2.2, Radioactive GaseousEffluentMonitoringInstrumentation. Also,deletedtheWasteGasStorageTank sampling and analysis mquirements and associated notations in Table 2.7, Radioactive Gaseous Waste Sampling an6 Analysis Program.

-. . Deleting the Condenser Noble Gas Activity monitor from Table 2.2, Radioactive Gaseous Effluent Monitoring Instrumentation.

• Revising tle Turbine Building sump sampling and analysis in Table 2.6, Radioactive Liquid L Waste Sampling and Aru , sis Progran .byeliminating Iodine-131 and Dissolved and Entrained Gases, and adding the requirement for quarterlyIron-55 analysis E

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E APPENDIX E l (Continued)

Revision 7, approved March 11,1998 I

Clarified the requirements for monitoring and surveillance ofthe Primary Vent Stack continuous J l releases in the defueled condition by

Deleting the requirement for continuous Iodine sampling in Table 2.2, Radioactive Gaseous i

Effluent Monitoring Instrumentation and Table 2.7, Radioactive Gaseous Waste Sampling and Analysis Program.

Revising the requirement in Table 2.2 from a " Flow Rate" measuring device to a " Flow" measuring device.

Revising the corrective action in Table 2.2 if the particulate sampler becomes inoperable,  ;

specifying immediate actions to suspend operations that increase the potential for particulate  !

releases, and defining a specific response time in which to commence sampling with auxiliary equipment.

l Revision 8, approved April 1,1998 Incorporated the new gaseous release pathway via the Fuel Building Exhaust Vent, to include:

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Recognition ofmultiple gaseous release pathways, to include both the Primary Vent Stack and the Fuel Building Exhaust Vent Added Fuel Building Exhaust Vent monitors / samplers to Table 2.2, Radioactive Gaseous Effluent Monitoring Instrumentation Added Fuel Building Exhaust Vent sampling and analysis requirements to Table 2.7, Radioactive Gaseous Waste Sampling and Analysis Program l Added Fuel Building Exhaust Vent dose calculation equations and supporting Dose Factors fbr l Dose Rates to the Total Body and Skin from Noble Gases and to the Critical Organ from .

Radiciodines and Particulates, and Gamma and Beta Air Dose and Dose to the Critical Organ in Section 4.0, Gaseous Effluent Dose Calculations and Appendix A, Basis for the Dose l Calculation Methods.

.- Revised Figure 6.2, Maine Yankee Gaseous Radwaste System to reflect the new release j pathway. ,

Changed the REMP Sample Location maps, Figures 5.1 through 5.4, with new revisions based on

' locations determined by the Global Positioning survey.

l Revision 9, approved June 29,1998 Revisedthefrequencyof thecontinuousgaseousn:lcasetritiumsurveillancesinTable2.7, Radioactive Gaseous Waste Sampling and Analysis Program. Changed the frequency ofthe Primary Vent Stack sample from continuous to monthly, and the Fuel Building Exhaust Vent sample from continuous to weekly.

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l APPENDIX E l

[ (Continued)

Revision 10, approved August 19,1998 -

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Eliminated the requirement for continuous monitoring of noble gases in the Primary Vent Stack by:

Deleting the requirement for the Noble Gas Activity Monitor specified in Table 2.2, Radioactive Gaseous Effluent Monitoring Instrumentation n Deleting the requirement for continuous analysis for noble gas in Table 2.7, Radioactive  !

. Gaseous Waste Sampling and Analysis Program.

Deleted reference to the Primary Vent Stack air particulate monitor in Figure 6.2, Maine Yankee Gaseous Radwaste System.

Revision 11, approved November 10,1998 Incorporated minor administrative changes for consistency with Amendment 161 ofthe Technical Specifications by deleting or changing reference to specific Technical Specifications that no longer exist or no longer apply, or by revising wording to be consistent with the revised terminology in the-Technical Specifications.

Eliminated the specific requirements for gross gamma or gross beta analysis in the Radiological Efiluents Control Program (ACTION 2 of Table 2.1, Radioactive Liquid Effluent Monitoring Instrumentation, and ACTION 5 of Table 2.2, Radioactive Gaseous Effluent Monitoring

- Instrumentation), and replaced it with the requirement analyze instead for " radioactivity".

Eli:ninated reference to the Charcoal Filters in the Ventilation system in Figure 6.2, Maine Yankee Gaseous Radwaste System.

- Revised the liquid dose calculation equations to account for releases without Circulating or Service Waterdilution flow bypmviding a mimmum dilution flow rate based on tidal flushing. This value, used for the calculation offactor K in equation 3-1 in Section 3.1, Liquid Efiluent Dose to an Individual was j incorporated into the definition of K.

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