ML20206C563

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Radioactive Effluent Release Rept 41 for Jan-Dec 1998 for Pbaps,Units 1 & 2
ML20206C563
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1998
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20206C549 List:
References
41, NUDOCS 9905030074
Download: ML20206C563 (20)
v • d • e


Text

PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 RADIOACTIVE EFFLUENT RELEASE REPORT NO. 41 JANUARY 1,1998 THROUGH DECEMBER 31,1998 l

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Submitted to The United States Nuclear Regulatory Conunission i Pursuant to l Facility Operating Licenses DPR-44 and DPR-56

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9905030074 990420 PDR ADOCK 05000277 i R PDR ,

TABLE OF CONTENTS SECTION PAGE I. Introduction 1 II. Tables lA. Gaseous Effluents - Summation of All Releases 4

18. Gaseous Effluents for Release Point - Main Stack 6 1C. Gaseous Effluents for Release Point -

Unit 2, Unit 3 Roof Vents and Aux Boiler Stacks 8 2A. Liquid Effluents - Summation of All Releases 10 2B. Liquid Effluents 12 Ill. Classes of Solid Radioactive Waste Shipments 14 IV. Attachments A. Supplemental Information 15 Technical Concurrences: (for accuracy of information) so

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Wistry / Ra(waste Manager AYd

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1. . INTRODUCTION In accordance with the Reporting Requirements of Technical Specification 5.6.3 I l applicable during the reporting period, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station Units 2 and 3 for the period January 1, 1998 through December 31,1998. The notations E and E- are used to denote positive l and negative exponents to the base 10, respectively.

The release of radioactive materials during the reporting period was within the Offsite Dose Calculation Manual Specification limits.

l The Offsite Dose Calculation Manual (ODCM) was revised during the reporting L period. ODCM Revision 11, approved on 4/16/98 and issued July 1,1998, included the following changes:

1. Requirements for monitoring and processing gaseous effluents were clarified,
a. ODCMS 3.8.C.5 : The APPLICABILITY statement was changed.
b. ODCMS 3.8.C.5 : Auxiliary Boilers waste oil burning exhaust added. '
c. ODCMS BASES : New section to define significant releases.

i 2. Incorporate REMP (Radiological Environmental Monitoring Program) changes.

a. ODCM Table VII.A-1 : Changed the 2 air particulate / iodine sampling station designation to 1C and distance from SE at 4,661 to SSE at 4,513 feet.
3. Particulate and lodine dose calculations changes.
a. ODCM IV.A.2 : The Iodine-131 method for calculating dose rates was deleted. The isotopic method was retained.
b. ODCM Table IV. A.2 : The critical organs used to determine the dose rates were changed from child thyroid and child lung to child thyroid and teenager lung,
c. ODCM IV. A.2 : Auxiliary boiler stack release equation was moved from IV.F to IV.A.2.
d. ODCM IV.C : The Iodine-131 method for calculating dose was deleted.

The isotopic method was retained.

e. ODCM Table IV.C.1 : The critical organs used to determine dose were I

changed from infant thyroid and infant liver to infant thyroid, infant liver and infant bone.

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f. ODCM IV.C : Auxiliary boiler stack release equation was moved from IV.F to IV.C.
4. Added Laundry Drain Filter as a Treatment path.
a. ODCMS 3.8.B.4 : Added floor drain filter to list of radwaste subsystems used for processing liquid effluent releases,
b. ODCMS 4.8.B.4.5 : Requirement added to demonstrate operability of the laundry drain filter.
c. ODCMS Bases : Added a section to the Liquid Radwaste Effluents section to clarify types of water to be processed by the laundry drain l filter i

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5. Administrative and Minor Technical Changes.

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a. ODCM 111.B : The term discharge structure was changed to discharge i pathway.
b. ODCM IV.E.1 : Removed sections referencing equipment no longer j used.
c. ODCM Table Vll. A-1111. Waterborne Surface : Compensatory action frequency changed from daily to once per calendar day.
d. ODCM Vil : Updated the Offgas Radwaste Treatment System and Ventilation Exhaust Waste Treatment System Diagrams.
e. ODCMS 3.8.C : References to equipment that is no longer used was deleted.
f. ODCMS 3.8.B.4 : The word or was removed from 3.8.B.4.c.
g. ODCMS 3.8.C.4 : Gross activity was changed to activity in the Required Compensatory Measure A.2.
h. ODCMS 3.8.E.3 : The alternate to the EPA Environmental Radioactivity Intercomparison Studies Program was changed to an Interlaboratory Comparison Program traceable to NIST.
i. ODCMS 3.10.3 : The option for submitting the meteorological data in the Radiation Dose Assessment Report was clarified.

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l The station Process Control Program (PCP) was revised on 1/31/98. The incorporated changes were: 1

1. Added commitments for tracking purposes.
2. Several changes that apply only to Limerick.

The noble gas Total Curie and Air Dose values in this report were generated by using baseline isotopic noble gas grab sample data in conjunction with the continuous noble

_ gas effluent monitor information.

There was one unplanned release of liquid radioactive material.

There was one abnormal gaseous radioactive material release event.

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l EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

! Table 1 A Page 1 of 2 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST. ERROR 1 2 TOTAL %

A. Fission & activation gases

1. Total release Ci 1.07E2 1.05E2 18.8
2. Average release rate for period pCi/see 1.47El 1.24El 18.8
3. Ganuna Air Dose Millirad 2.26E-2 2.27E-2 18.8 Percent of Technical Specification  % 2.26E-1 2.27E-l 18.8 l
4. Beta Air Dose Millirad 1.55E-2 1.59E-2 18.8 l Percent of Tecimical Specification  % 7.75E-2 7.95 E-2 18.8 l

B. kxlines

1. Total iodine-131 Ci 1.84E-4 1.93E-4 22.9
2. Average release rate for period pCi/sec 2.54E-5 2.28E-5 22.9
3. Critical Organ dose Millirem 8.59E-4 1.28E-3 22.9 Percent of Technical Specification  % 5.73E-3 8.53E-3 22.9 C. Particulates i
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 9.13 E-5 8.50E-5 22.9 and Strontium 89-90)
2. Average release rate for period uCi/sec 1.26E-5 1.00E-5 22.9
3. Average Gross Alpha Radioactivity Ci 1.82E-6 3.07E-6 22.9 D. Tritium
1. Total release Ci 0 2.23E2 23.5
2. Average release rate for period uCi/sec 0 2.63El 23.5 l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

Table 1 A Page 2 of 2 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST. ERROR 3 4 TOTAL %

A. Fission & activation gases

1. Total release Ci 7.20El 1.77E2 18.8
2. Average release rate for period pCi/sec 9.16E0 2.25El 18.8
3. Gamma Air Dose Millirad 1.29E-2 3.83E-2 18.8 Percent of Technical Specification  % 1.29E-1 3.83E-1 18.8
4. Beta Air Dose Millirad 9.17E-3 2.67E 2 18.8 Percent of Technical Specification  % 4.59E-2 1.34E-1 18.8 B. lodines
1. Total iodine-131 Ci 5.52E-4 2.17E-4 22.9
2. Average release rate for period pCi/sec 7.02E-5 2.76E-5 22.9
3. Critical Organ dose Millirem 5.75E-3 1.38E-3 22.9 Percent of Technical Specification  % 3.83E-2 9.20E-3 22.9 C. Particulates l
1. Particulates with half-hves greater than 8 days (includes Alpha Ci 1.35E-4 1.71 E-4 22.9 and Strontium 89-90)
2. Average release rate for period uCi/sec 1.72E-5 2.17E-5 22.9

! 3. Average Gross Alpha Radioactivity Ci 6.97E-6 5.81E-6 22.9 D. Tritium

1. Total release Ci 6.38E0 0 23.5
2. Average release rate for period uCi/sec 8.1 I E-l 0 23.5 i

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r-EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

Table IB Page 1 of 2

. Gaseous Effluents for Release Point - Main Stack Continuous M(xle Batch Mode Nuclides Released Units a

Quarter Quarter Quarter Quarter 1 2 1 2

1. Fission gases i

Krypton - 85M Ci 7.90E0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 6.0l E-1 0 0 0 Xenon - 135 Ci 1.77E0 0 0 0 4 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 0 1 I

Unidentified Ci 9.32E0 1.68El 0 0 i Total for Peri (xl Ci 1.96El 1.68E1 0 0

2. hxlines hxline - 131 Ci 1.84 E-4 1.93E-4 0 0 lodine - 133 Ci 4.94 E-4 6.34E-4 0 0 kxline - 135 Ci 0 0 0 0 Total for Period Ci 6.78E-4 8.27E-4 0 0 .
3. Particulates Strontium - 89 Ci 6.75E-5 5.73 E-5 0 0 Strontium - 90 Ci 1.93E-7 1.40E-7 0 0 Barium - 140 Ci 4.69E-6 4.62E-6 0 0 Cobalt - 57 Ci 0 2.67E-7 0 0 l l

TOTAL FOR PERIOD Ci 7.24E-5 6.23E-5 0 0 i

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r EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

Table IB Page 2 of 2 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Uni.s

. Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 0 0 0 0 Xerx>n - 135 Ci 3.71EO 0 0 0 Xenon - 135M Ci 1.55E0 0 0 0 Xenon - 138 Ci 0 0 0 0 Unidentified Ci 1.76El 2.99El 0 0 Total for Period Ci 2.29El 2.99El 0 0
2. hxlines hxline - 131 Ci 1.63E-4 1.66E-4 0 0 lodine - 133 Ci 1.93E-3 1.00E-3 0 0 kxtine - 135 Ci 3.82E-6 0 0 0 Total for Period Ci 2.10E-3 1.17E-3 0 0
3. Particulates Strontium - 89 Ci 7.68E-5 7.12E-5 0 0 Strontium - 90 Ci 1.24E-7 2.00E-7 0 0 Barium - 140 Ci 1.62E-5 3.03E-5 0 0 TOTAL FOR PERIOD Ci 9.31E-5 1.02E-4 0 0 1

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

Table IC Page 1 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents & Aux Boiler Stacks Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2

1. Fission gases Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 0 0 0 0 Xenon - 135 Ci 0 0 0 0 Xenon - 135M Ci 0 0 0 0 i Xeinin - 138 Ci 0 0 0 0 1

Unidentified Ci 8.72El 8.77El 0 0 Total for Period Ci 8.72El 8.77El 0 0

2. hxlines Iodine - 131 Ci 0 2.98E-5 0 0 hxtine - 133 Ci 0 1.91E-3 0 0 lodine - 135 Ci 0 0 0 0 Total for Pericxl Ci ,

0 1.94E-3 0 0

3. Particulates Strontiuin - 89 Ci 1.33E-5 1.96E-5 0 0 Strontiurn - 90 Ci 0 0 0 0 Cot, alt - 60 Ci 0 0 3.81E-6 0 TOTAL FOR PERIOD Ci 1.33E-5 1.96E-5 3.81 E-6 0 t l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

. Table IC Page 2 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents & Aux Boiler Stacks Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter {'

3 4 3 4

l. Fission gases Krypton 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 l Krypton - 88 Ci 0 0 0 0 i Xernin - 133 Ci 0 0

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Xcruin - 135 Ci 0 0 0 0 Xenon - 135M Ci 0 0 0 0 {

Xenon - 138 Ci 0 0 0 0 I Unidentified Ci 4.91El 1.47E2 0 0 Total for Period Ci 4.91El 1.47E2 0 0

2. todines lodine - 131 Ci 3.89E-4 5.14E-5 0 0 lodine - 133 Ci 1.18E-2 3.09E-3 0 0 <

1' hxline - 135 Ci 0 0 0 0 Total for Period Ca 1.22E-2 3.14E 3 0 0

3. Particulates Strontium - 89 Ci 3.51 E-5 2.45E-5 0 0 Strontium - 90 Ci 0 0 0 0 Cobalt - 60 Ci 0 3.88E-5 0 0 TOTAL FOR PERIOD Ci 3.51E-5 6.33 E-5 0 0 l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

L Table 2A Page 1 of 2 Liquid Effluents - Summation of All Releases Quarter Quarter Est. Error Units 1 2 Total %

A. Fission & activation products

1. Total release (rxit including tritium, gases, alpha) Ci 8.41E-3 7.24E 5 22.9
2. Average diluted concentration during period pCi/mi 2.06E-10 2.32E-12 22.9
3. Total Body Dose Millitern 1.47E-3 1.21 E-4 22.9 Percent of Technical Specification  % 4.90E-2 4.03E-3 22.9
4. Maximally Exposed Organ Dose Millirem 2.17E-3 1.38E-4 22.9 Percent of Technical Specification  % 2.17E-2 1.38E-3 22.9 B. Tritium
1. Total release Ci 4.76El 1,71El 15.0
2. Average diluted concentration during period uCi/ml 1.16E-6 5.48E-7 15.0 C. Dissolved ami entrained gases
1. Total release Ci 1.87E-3 9.82E-4 22.9
2. Average diluted concentration during period pCi/ml 4.57E-11 3.15E-11 22.9 D. Gross alpha radioactivity
1. Total release Ci 0 0 22.9
2. Average diluted concentration during period pCi/ml 0 0 22.9 E. Volume of waste released (prior to dilution) liters 4.19E6 1.83E6 12.7 F. Volutte of dilution water used during period liters 4.09E10 3.12E10 10.9 i

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98)

Table 2A Page 2 of 2 l Liquid Effluents - Summation of All Releases

( Quarter Quarter Est. Error Units 3 4 Total %

A. Fission & activation products

- 1. Total release (ruit including tritium, gases, alpha) Ci 6.84E-4 4.45E-3 22.9

2. Average diluted concentration during period pCi/ml 1.62E-11 9.23E-11 22.9
3. Total Body Dose Millirem 2.28E-4 1.07E-3 22.9 Percent of Technical Specification  % 7.60E-3 3.57E-2 22.9
4. Maximally Exposed Organ Dose Millirem 2.70E-4 1.32E-3 22.9 Percent of Technical Specification  % 2.70E-3 1.32E-2 22.9 B. Tritium
1. Total release Ci 2.42 0. 5.05El 15.0
2. Average diluted concentration during period pCi/ml 5.73E-7 1.0$E-6 15.0 C. Dissolved azul entrained gases I, Total release Ci 9.28E-4 2.61 E-3 22.9
2. Average diluted concentration during period uCi/mi 2.19E-11 5.41E-11 22.9 D. Gross alpha radioactivity
1. Total release Ci 0 0-  !

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2. Average diluted concentration during period uCi/ml 0 0 22.9 E. Volume of waste released (prior to dilution) liters 2.24E6 3.68E6 12.7 F. Volume of dilution water used during perimi liters 4.22E10 4.82E10 10.9 .

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L. EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98 - 12/31/98) f Table 28 Page 1 of 2 .

Liquid Effluents {

Continuous Male Batch Mmle 1

l Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 Strontium - 89 Ci 0 0 0 0 Strontium - 90 Ci 0 0 0 0 Alpha Ci 0 0 0 0 Tritium Ci 9.63E-2 0 4.75El 1.71El Phosphorus - 32 Ci 0 0 0 0 Iron - 55 Ci 8.13 E-4 0 0 0-Xenon - 133 Ci 0 0 7.88E-4 3.55E-4 Xenon - 135 Ci 0 0 1.08E-3 6.27E-4 Manganese - 54 Ci 1.09E-3 0 3.16E-4 9.61 E-7 Cesium - 137 Ci 5.79E-5 0 2.99E-5 9.06E-6 Zine - 65 Ci 1.55E-3 0 9.72E-4 0 Cobalt - 60 Ci 1.95 E-3 0 1.63E-3 6.24E-5 TOTAL FOR PERIOD Ci 1.02E-1 0 4.75El 1.71El i

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98-12/31/98)

Table 2B Page 2 of 2 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Strontium - 89 Ci 0 0 0 0 Strontium - 90 Ci 0 0 0 0 Alpha Ci 0 0 0 0 Tritium Ci 0 0 2.42E1 5.05El Phosphorus - 32 Ci 0 0 0 1.90E-4 Iron - 55 Ci 0 0 0 0 Xenon - 133 Ci 0 0 1.35E-4 3.16E-4 Xenon - 135 Ci 0 0 7.93E-4 2.29E-3 Manganese - 54 Ci 0 0 5.09E-5 8.52E-4 Manganese - 56 Ci 0 0 0 1.54E-5 Cesium - 137 Ci 0 0 2.65E-5 2.00E-5 Zine - 65 Ci 0 0 0 1.28E-3 Cobalt - 58 Ci 0 0 0 2.37E-4 Cobalt - 60 Ci 0 0 1.38E-4 1.62E-3 Chromium - 51 Ci 0 0 4.68E-4 2.37E-4 TOTAL FOR PERIOD Ci 0 0 2.42El 5.05El l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/98-12/31/98)

PEACH BOTTOM UNITS 2 & 3 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS l Tot:1 # of - Waste Description Container / Type individual Total Total Principal  !

Shipments (source of waste) Volume Volume Curie Radionuclides (cubic ft) (cubic ft) I CLASS A 11 Dewatered Resin HIC / Type A Cask 195.7 2152.7 3.95E+05 Zn-65, Co-60, Cs-137, Mn-54, Ni-63 7 Solidified Resin (1) HIC / Type A Cask variable 44.6 3.83E+04 Co-60, Mn-54, Ni-63, Zn-65, Cs-137 49- DAW (2) Metal Box /STC variable 2458.3 2.91 E-01 Co-60, Zn-65, Cs-137, Mn-54, Fe-55 43 DAW (3) Metal Box /STC variable 364.4 3.99E-01 Co-60, Zn-65, Cs-137, )

Mn-54, Fe-59

(*) Dewatered Metal Box /STC variable 11.5 1.78E-01 Co-60, Zn45, Mn-54, Filters (3) Cs-137, Fe-59

(*) Incinerator Metal Box /STC variable 37.5 5.44E-01 Co-60, Zn-65, Cs-137, Ash (3) Mn-54, Fe-59

(*) Asbestos (3) Metal Box /STC variable 70.5 3.78E-02 Co-60,2n-65, Mn-54, Cs-137, Fe-59 12 DAW (4) Metal Box /STC . variable .14.2 1.53E-02 Co-60, Zn-65, Fe-55, Cs-137, Mn-54  ;

CLASSB 1 Dewatered Resin HIC / Type A Cask 195.7 195.7 1.04E+05 Zn-65, Co-60, Cs-137, j Mn-54, Ni-63  !

l CLASS C 1 Irradiated Hardware Metal Liner / 57.4 57.4 2.34E+07 Co-60, Fe-55, Ni-63, Type B Cask Mn-54, Ni-59

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TOTALS 124 5606.9 2.39E+07 NOTES:

(1)- Indicates actual total PECO waste shipped from Allied Technology Group (ATG) aka Molten Metal Technologies, Inc. (MMT) to burial after processing.

(2)- Indicates actual total PECO waste shipped from Manufacturing Sciences Corp. to burial after processing.

(3)- Indicates actual total PECO waste shipped from GTS Duratek (formerly SEG) to burial after processing.

(4)- Indicates actual total PECO waste shipped from American Ecology Recycle Center (AERC) to burial after processing.

(*) Shipment total included with DAW from GTS Duratek as these shipments contained comingled waste streams.

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g-ATTACHMENT A-SUPPLEMENT INFORM ATION Facility: Peach Bottom Units 2 & 3 Licenses: DPR-44 DPR-56 l

1. Regulatory Limits (Offsite Dose Calculation Manual Soecification Limits)

A. Noble Gases:

~ 1. - s500 mrem /Yr - total body -

" instantaneous" limits s3000 mrem /Yr - - skin ODCMS 3.8.C.1.a

- 2. s10 mrad - air gamma -

quarterly air dose limits s20 mrad - air beta ODCMS 3.8.C.2.a and b

3. s20 mrad - air gamma -

yearly air dose limits s40 mrad - air beta ODCMS 3.8.C.2.c and d B. lodines. Tritium. Particulates with Half Life > 8 days:

1. s1500 mrem /Yr. - any organ -

" instantaneous" limits (inhalation path) ODCMS 3.8.C.l.b

2. s15 mrem - any organ -

quarterly dose limits ODCMS 3.8.C 3.a

3. s30 mrem _ - any organ -

yearly dose limits ODCMS 3.8.C.3.b C. Liauid EfHuents

1. Concentration s 10 times 10 CFR 20, -

" instantaneous" limits l Appendix B, Table 2, Col. 2 ODCMS 3.8.B.1

2. s 3.0 mrem - total body -

quarterly dose limits s10 mrem - any organ ODCMS 3.8.B.2.a l 3. s6.0 mrem - total body -

yearly dose limits s20 mrem - any organ -

ODCMS 3.8.B.2.b i

i l 2. Maximum Permissible Concentrations Effluent Concentrations are not used to calculate permissible release rates and concentrations for gaseous I releases.

The EfHuent Concentrations speciHed in 10 CFR 20, Appendix B, Table 2, Column 2 times 10, for identified nuclides, are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Offsite Dose Calculation Manual SpeciGcation 3.8.B.1.  !

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w ATTACHMENT A (continued)

3. Average Energy:

Not Applicable

. 4. : Measurements and Approximations of Total Radioactivity:

A. Fission and Activation Gases:

The method used is the Canberra S95/ Dual Host 3400 Counting System

- Gas Marinelli -

B. Iodine:

The method used is the Canberra S95/ Dual Host 3400 Counting System

- Charcoal Cartridge -

. C. Particulates:

The method used is the Canberra S95/ Dual Host 3400 Counting System

- Air Particulate Sample, (37mm and 47mm) -

D. Liould Effluents:

The method used is the Canberra S95/ Dual Host 3400 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a one liter marinelli or one liter bottle.

5.' Batch Releases:

'A. Liquid:

.QTR1 QRT 2 QTR 3 QTR 4 Number of batch releases: 66 31 39 63 Total Time for batch releases (minutes) 15431 6729 8546 14318 Maximum time period for batch release 290 277 355 300 (minutes):

Average time period for batch release 233.80 '217.% 219.13 227.22 (m'inutes):

i Minimum time period for batch release '55 45 65 65 (minutes):

Dilution volume (liters): 4.09E10 3.12E10 4.22E10 4.82E10 16 L __..

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ATFACHMENT A (Continued) )

B. Gaseous:

QTRI QRT 2 QTR 3 QTR 4 Number of batch releases: 2 0 0 0 Total Time for batch releases (minutes) 38542 0 0 0 Maximum time period for batch release 19925 0 0 0 (minutes):

Average time period for batch release 19271 0 0 0 (minutes): l Minimum time period for batch release 18617 0 0 0 (minutes):

6. Abnormal Releases:

A. Liauid:

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1. Event description - This event was a continuation of the high pressure service water (HPSW) event discovered on 11/1/97 through routine sampling of the effluent to the discharge canal.

Investigation of this event determined that a trace amount of condensate stay-full or primary coolant water was leaking past the Unit 2 " A" residual Heat Removal (RHR) heat exchanger tube to the "A" loop of the HPSW system. One leaking tube was plugged.

It was estimated that the contaminated water released 4.35E-4 mrem total body dose to the discharge canal from 1/1/98 to 3/31/98. This dose was well below the limits specified in the ODCM.

Analysis of Release - A representative sample was analyzed for the parameters of a radioactive effluent release. The dose contributions and isotope quantities from this continuous release were added to this Radioactive Effluent Release Report for the applicable reporting periods.

B. Gaseous:

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1. Event Description - During 1998 several potential unmonitored release paths were discovered in the turbine building and off-gas building. These release points were due, in part, to the aging of caulking at concrete-to-metal interfaces.

l As each release point was discovered, the direction of the air flow was determined. If flow was out of the structure, a continuous air sample was obtained. No detectable activity was measured at any of the release points.

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ATTACHMENT A (Continued) )

. 7. Minimum Detectable Concentrations:

A. Liquid:

If a radionuclide was not detected, zero activity was reported for that isotope. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in Offsite Dose

- Calculation Manual Specification Table 4.8.B.1 Radioactive Liquid Waste Sampling and Analysis. In all cases, these L.LDs were less than the values required by Offsite Dose Calculation Manual Specifications.

B. - Gaseous:

If a radionuclide was not detected, zero activity was reported for that isotope. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in Offsite Dose Calculation Manual Specification Table 4.8.C.1 Radioactive Gaseous Waste Sampling and . Analysis from Main Stack and Vent Stack. In all cases, these LLDs were less than the values required by Offsite Dose Calculation Manual Specifications.

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