ML20076K780

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Corrected Copies of Semi-Annual Effluent Release Rept 36 Jul-Dec 1993, for PBAPS Units 2 & 3
ML20076K780
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1993
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20076K765 List:
References
NUDOCS 9411020109
Download: ML20076K780 (30)
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. PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 36 JULY 1,1993 THROUGH DECEMBER 31,1993 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56 9411020109 941020 7 PDR ADOCK 0500 R

TABLE OF CONTENTS SECTION PAGE I. Introduction 1 II. Tables 1A. Gaseous Effluents - Summation of All Releases 2 IB. Gaseous Effluents for Release Point - Main Stack 3 1C. Gaseous Effluents for Release Point -

Unit 2 and Unit 3 Roof Vents 5

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2A, Liquid Effluents - Summation of All Releases 7 2B. Liquid Effluents 8 r III. Classes of Solid Radioactive Waste Shipments 9 ,

' IV. Attachments 1

A. Supplemental Information 10 Technical Concurrences: (for accuracy ofinformation)

Radwaste Manager aQOdd Chemistry Manager

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1. INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2h(2) 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 July 1,1993 through December 31,1993. The notations E and E- are used to denote positive and negative exponents to the base 10, respectively.

The release of radioactive materials during the reporting period was within the Technical Specification limits. There were no changes made to the Off-Site Dose Calculation Manual (ODCM) during the reporting period.

Estimated particulate, iodine, and fission gas releases were determined for a 7-day period when an improperly secured main stack particulate and cartridge filter assembly resulted in diluted sample flow (PBAPS LER 2-93-15).

There were two unplanned releases of liquid radioactive material.

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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

. Table 1 A Page 1 of 1 Gaseous Effluents - Summation of All Releases UNITS QUARTER Q'UARTER EST.

3 4 ERROR j TOTAL %

A. Fission & activation gases

1. Total release Ci 5.25E3 2.08E3 18.8
2. Average release rate for period pCi/sec 6.67E2 2.65E2 18.8
3. Gamma Air Dose Millirad 1.406-1 6.63E-2 18.8 Percent of Technical Specification  % 1.40E0 6.63E-1 18.8
4. Beta Air Dose Millirad 1.39E-1 6.10E-2 18.8 Percent of Technical Specification  % 6.95E-1 3.05E-1 18.8 B. Iodines
1. Total iodine-131 Ci 3.06E-2 4.34E-3 22.9
2. Average release rate for period Ci/sec 3.89E-3 5.52E-4 22.9
3. Critical Organ dose Millirem 1.19E-1 1.87E-2 22.9 Percent of Technical Specification  % 7.93E-1 1.25E-1 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 3.48E-3 2.L'sE-3 22.9 and Strontium 89-90)
2. Average release rate for period Ci/sec 4.43E-4 2.85E-4 22.9
3. Average Gross Alpha Radioactivity Ci 5.68E-6 2.26E-5 22.9 D. Tritium
1. Total release Ci 8.88E0 4.68E0 23.5
2. Average release rate for period pCi/sec 1.13E0 5.95E-1 23.5 2

4 EFFLUENT & WASTE DISPOSAL SEMI-ANNUt.L REPORT (7/01/93 - 12/31/93)

Table IB Page 1 of 2 j- Gaseous Effluents for Reicase Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases f Krypton - 85M Ci 1.51 E2 7.40E1 0 0 l

Krypton - 87 Ci 1.85E2 1.25E2 0 0 l

Krypton - 88 Ci 5.55El 7.49El 0 0 Xenon - 133 Ci 1.16E3 4.93E2 0 0 Xenon - 135 Ci 7.89E2 3.97E2 0 0 Xenon - 135M Ci 7.26E2 1.51 E2 0 0 Xenon - 138 Ci 7.45 E2 2.87E2 0 0 Xenon - 133M Ci 9.61E0 0 0 0 l Unidentified Ci 9.04E2 2.51 E2 0 0 l Total for Period Ci 4.73E3 1.85E3 0 0

2. lodines lodine - 131 Ci 1.93 E-2 2.24E-3 0 0 lodine - 133 Ci 5.58E-2 9.48 E-4 0 0 hxtine - 135 Ci 1.74E-2 0 0 0 Total for Period Ci 9.25 E-2 3.19E-2 0 0
3. Particulates Strontium - 89 Ci 1.35E-3 1.14 E-3 0 0 Strontium - 90 Ci 1.63 E-6 2.32E-6 0 0 Strontium - 91 Ci 5.71 E-4 1.04E-3 0 0 Cesium - 134 Ci 0 1.47E-5 0 0 Cesium - 137 Ci 3.79E-5 3.26E-5 0 0 Cesium - 138 Ci 6.89E-2 2.53E-2 0 0 Barium - 139 Ci 4.22E-3 1.32E-2 0 0 11arium - 140 Ci 3.95 E-4 8.44 E-4 0 0 lamthanum - 140 Ci 2.38E-4 6.31 E-4 0 0 Cobalt - 57 Ci 0 0 0 0 Cobalt - 58 Ci 0 0 0 0 3

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IB Page 2 of 2 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Cobalt - 60 Ci 0 5.57E-6 0 0 l Zinc - 65 Ci 0 0 0 0 Yttrium - 91M Ci 5.73E-3 6.05E-4 0 0 lodine - 133 Ci 9.88E-5 7.18E-6 0 0 Copper - 64 Ci 0 0 0 0 Rubidium - 88 Ci 0 0 0 0 Manganese - 54 Ci 0 0 J 0 Strontium - 92 Ci 0 0 0 0 Iodine - 135 Ci 1.69E-5 0 0 0 Tellurium - 132 Ci 4.27E-6 0 0 0 Molybdenum - 99 Ci 9.94E-7 0 0 0 Technetium - 99m Ci 1.51E-6 0 0 0 TOTAL FOR PERIOD Ci 8.15E-2 4.28E-2 0 0 l

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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IC Page 1 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units 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 2.64E1 0 0 0 Xenon - 135 Ci 4.74E1 0 0 0 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 0 Unidentified Ci 4.39E2 2.25E2 0 0 Total for Period Ci 5.13E2 2.25E2 0 0
2. Jodines lodine - 131 Ci 1.13E-2 2.10E-3 0 0 lodine - 133 Ci 7.14E-2 1.18E-2 0 0 lodine - 135 Ci 1.15E-1 2.50E-2 0 0 Total for Period Ci 1.98E-1 3.89E-2 0 0
3. Particulates i

Strontium - 89 Ci 5.80E-4 1.39E-4 0 0 Strontium - 90 Ci 4.13E-6 3.07E-6 0 0 Strontium - 91 Ci 1.21E-3 9.41E-5 0 0 Cesium - 134 Ci 4.61E-5 0 0 0 Cesium - 137 Ci 1.86E-4 3.12E-5 0 0 Cesium - 138 Ci 4.09E-2 3.68E-3 0 0 Barium - 139 Ci 8.65E-3 1.98E-3 0 0 Barium - 140 Ci 4.96E-4 0 0 0 1mthanum - 140 Ci 6.09E-4 9.39E-5 0 0 Cobalt - 57 Ci 0 0 0 0 Cobalt - 58 Ci 3.41E-6 0 0 0 Cobalt - 60 Ci 5.98E-5 0 0 0 5

f EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) ,

Table IC Page 2 of 2 Gaseous EfHuents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Zine - 65 Ci 0 0 0 0  ;

Yttrium - 91M Ci 3.73E-3 6.53E-5 0 0  :

Iodine - 133 Ci 9.17E-4 3.64E-4 0 0 Copper - 64 Ci 0 0 0 0  ;

- Rubidium - 88 Ci 0 0 0 0 Manganese - 54 Ci 0 0 0 0 Strontium - 92 Ci 0 0 0 0 ,

Cadmium - 109 Ci 1.02E-4 0 0 0 Technetium - 99m Ci 1.74E-5 0 0 0 TOTAL FOR PERIOD Ci 5.75E-2 6.45E-3 0 0 6

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 2A Page 1 of 1 Liquid Effluents - Summation of All Releases Quarter Quarter Est. Error Units 3 4 Total %

A. Fission & activation products

1. Total release (not including tritium, gases, alpha) Ci 2.61E-2 2.75E-2 22.9
2. Average diluted concentration during period pCi/ml 5.99E-11 7.39E-11 22.9
3. Total Body Dose ADULT BODY Millirem 3.10E-3 5.43E-3 22.9 Percent of Technical Specification  % 1.03E-1 1.81E-1 22.9
4. Maximally Exposed Organ Dose TEEN LIVER Millirem 5.47E-3 9.72E-3 22.9 Percent of Technical Specification  % 5.47E-2 9.72E-2 22.9 B. Tritium
1. Total release Ci 1.88E0 3.37E-1 15.0
2. Average diluted concentration during period Ci/ml 4.31Es 9.06E-10 15.0 C. Dissolved and entrained gases
1. Total release Ci 9.67E-3 1.49E-4 22.9
2. Average diluted concentration during period gCi/ml 2.22E-11 4.01E-13 22.9 D. Gross alpha radioactivity
1. Total release Ci 3.71E-5 6.24E-6 22.9
2. Average diluted concentration during period Ci/ml 8.51E-14 1.68E-14 22.9 E. Volume of waste released (prior to dilution) liters 9.61E5 1.73E5 12.7 F. Volume of dilution water used during period liters 4.36E11 3.72E11 10.9 l

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i EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) I l

Table 2B Page 1 of 1 Liquid Effluents l

Continuous Mode Batch Mode Nuclides Released Units Quarter Quaner Quarter Quarter 3 4 3 4 Strontium - 89 Ci 9. I BE-6 9.94E-6 1.08E-4 3.21E4 Strontium - 90 Ci 5.33 E-7 6.51E-7 3.08E-5 6.25E-7 1 l

Alpha Ci 8.68E-7 9.93E-7 3.62E-5 5.25E4 Tritium Ci 4.51E-2 4.99E-2 1.83E0 2.87E-1 Phosphorus - 32 Ci 6.19E-6 6.25E-6 1.64E-4 1.95E-5 Iron - 55 Ci 3.51E-4 3.48E-4 5.53E-4 6.66E-5 Xenon - 13]M Ci 0 0 0 0 Xenon - 133 Ci 0 0 3.41E-3 4.01E-5 Xenon - 133M Ci 0 0 0 0 Xenon - 135 Ci 0 0 6.22E-3 1.09E-4 Xenon - 135M Ci 0 0 3.67E-5 0 Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Manganese - 54 Ci 3.33E-3 3.65E-3 2.72E-7 0 Cesium - 134 Ci 2.27E-4 2.57E-4 4.64E-6 3.38E-6 Cesium - 137 Ci 5.99E-4 6.53E-4 1.71E-5 1.20E-5 Cesium - 138 Ci 0 0 0 0 Zine - 65 Ci 8.88E-3 9.75E-3 0 0 Sodium - 24 Ci 0 0 0 0 Cobalt - 58 Ci 9.18E-4 9.80E-4 0 0 Cobalt - 60 Ci 1.04E-2 1.12E-2 1.82E-5 2.82E-6 Chromium - 51 Ci 5.23E-4 5.07E 4 0 0 TOTAL FOR PERIOD Ci 7.03E-2 7.73E-2 1.84E0 2.87E-1 (ABOVE) 8

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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (07/01/93 - 12/31/93)

PEACH BOTTOM UNITS 2 & 3 JULY 1,1993 TO DECEMBER 31,1993 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS Total # of Waste Description Individual Total Shipments (sourte of waste) Container / Type Volume Volume Total Principal (cubic ft.) (cubic ft.) Curie Radionuclides Class A 19 Dewatered Resin H1C/ Type A Cask 202.1 3839.9 4.30E + 02 Zn-65,Co-60, Cs-137, Cs-134, Cr-51 1 Dewatered Resin HIC / Type A Cask 132.4 132.4 1.78E + 01 Zn45,Co40, Cs-137, Mn-54, Cs-134 13 DAW Metal Drum /STC, variable (*) 207.6 1.13E-01 Co-60,Zn-65, Metal Box /STC Fe-55, Cs-137, Mn-54 71 DAW Metal Drum /STC, variable (") 856.3 1.00E + 00 Co-60, Zn45, Metal Box /STC Fe-55, Cs-137, Mn-54 1 DAW HICffype A Cask 38.3 114.9 3.37E + 00 Co-60, Fe-55, Zn-65, Ni-63 1 DAW HICffype A Cask 205.8 205.8 1.41E + 00 Co40, Cs-137, Zn-65, Fe-55, Mn-54 CLASS B 8 Dewatered Resin HICffype A Cask 202.1 Its16.8 3.06E + 02 Zn-65, Cs-137, C3-60, Cs-134, Fe-55 2 Dewatered Filters HIC / Type A Cask 38.3 229.8 3.20E + 01 Co-60, Fe-55, Zn-65, Ni-63 CLASS C 3 Irradiated H' Ware Steel Liner / 57.8 173.4 6.03E + 04 Fe-55, Co-60, Type B Cask Mn-54, Ni-63, Cr-51 TOTALS 119 7376.9 6.11E + (M NOTES:

  • -Indicates actual total PECO radwaste shipped from Quadrex, after volume reduction, to the burial site.
    • - Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site.

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. . ATTACHMENT A j SUPPLEMENT INFORMATION  !

Facility: Peach Bottom Units 2 & 3 Licenses: DPR-44 I DPR-56

1. Regulatory Limits (Technical Specification Limits)

A. Noble Gases: 1

1. s500 mrem /Yr - total body -

" instantaneous" limits 53000 mrem /Yr - skin Tech. Spec. 3.8.C.l.a

2. s 10 mrad - air gamma - quarterly air dose limits

$20 mrad - air beta Tech. Spec. 3.8.C.2.a

3. s 20 mrad - air gamma - yearly air dose limits 5 40 mrad - air beta Tech. Spec. 3.8.C.2.b B. Iodines. Tritium. Particulates with Half Life > 8 days:
1. s1500 mrem /Yr - any organ - " instantaneous" limits (inhalation path) Tech. Spec. 3.8.C.1.b
2. s 15 mrem - any organ - quarterly dose limits Tech. Spec. 3.8.C.3.a
3. s 30 mrem - any organ - yearly dose limits Tech. Spec. 3.8.C.3.b C. Liould Effluents
1. Concentration s 10 CFR 20, - " instantaneous" limits Appendix B, Table II, Col. 2 Tech. Spec. 3.8.B.1 j I
2. s 3.0 mrem - total body - quarterly dose limits j s 10 mrem - any organ Tech. Spec. 3.8.B.2.a j
3. s6.0 mrem - total body - yearly dose limits )

s 20 mrem - any organ - Tech. Spec. 3.8.B.2.b

2. Maximum Permissible Concentrations:

MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.

The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified nuclides are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Technical Specification 3.8.B.l.

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', ATTACHMEEr A (continued) 1

," 3. Average Energy:

Not Applicable

4. Measurements and Approximations of Total Radioactivity:

i A. Fission and Activation Gases: i The method used is the Nuclear Data 6700 Counting System or the Canberra  !

S95/ Dual Host 3400 Counting System I

- Gas Marinelli - .

1 B. Iodme: 1 The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System

- Charcoal Cartridge -

C. Particulates:

The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System

- Air Particulate Sample, (47mm and 57mm filters) -

D. Liquid Effluents:

The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli 1

5. Batch Releases; i 1

A. Liquid:

OTR 3 OTR 4 Number of batch releases: 15 7 Total time for batch releases (minutes): 3506 893 Maximura time period for batch release (minutes): 368 260 l Average time period for batch release (minutes): 234 128 I Minimum time period for batch release (minutes): 43 65 i Dilution volume (liters): 1.37E10 2.28E9 B. Gaseous:

Not applicable 11

',4 A'ITACHMENT A (continued)

6. Abnormal Relcasti: )

l A. Liquid:

1. Event description - On 7/23/93 routine sampling of the high pressure service water (HPSW) effluent to the discharge canal detected low level radioactive i contamination. Subsequent investigation determined that a trace amount of condensate stay full or primary coolant water was leaking past the Unit 2 'B' residual heat removal (RHR) heat exchanger floating head gasket into the 'B' loop of the HPSW system. The gasket was replaced and leak tested satisfactorily.

It was estimated that the contaminated water released 7.65E-3 millirem total body dose to the discharge canal from 7/23/93 to 12/7/93. This dose contribution was well below the limits specified in Technical Specifications.

Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The Dose contributions and Isotope quantities from this continuous release were added to this Semi-Annual Effluent Report for the applicable reporting period.

2. Event description - un 11/10/93 routine sampling of the high pressure service water (HPSW) effluent to the discharge canal detected low level radioactive contamination. Subsequent investigation determined that a trace amount of conden . ate stay full or primary coolant water was leaking past the Unit 2 'A' residual heat removal (RHR) heat exchanger floating head gasket into the 'A' loop of the HPSW system. The gasket was replaced and leak tested satisfactorily.

It was estimated that the contaminated water released 6.41E-4 millirem total boJy dose to the discharge canal from 11/10/93 to 1/9/94. This dose ccntribution was well below the limits specified in Technical Specifications.

Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The Dose contributions and Isotope quantities from this continuous release were added to this Semi-Annual Effluent Report for the applicable reporting period. I 12

i-[,')'* A'1TACHMENT A (continued)

6. Abnormal Releases: (Continued)

B. Gaseous:

PBAPS LER 2-93-15 Event Description - While performing the weekly filter change on December 1, ,

1993 the Main Stack Particulate Filter and Charcoal Cartridge Assembly was found to be improperly secured, resulting in diluted sample flow. Accordingly, representative sampling of Main Stack particulate, iodine, and fission gas releases .

was not obtained for the 7-day period from November 24 through December 1, i 1993.

Analysis of Release hwi on existing radiological controls and current and previous plant experience, it is believed that no abnormal particulate, iodine, or j fission gas releases occurred. Release values during the unmonitored period were j calculated by simply extending the before and after release rates into the unmonitored period. ,

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PEACH BOTTOM ATOMIC POWER STATION- -

Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 s

SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 36 -

JULY 1,1993 THROUGH DECEMBER 31,1993

[

4 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56

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TABLE OF CONTENTS l i

l SECTION PAGE I. Introduction 1 II. Tables 1A. Gaseous Effluents - Summation of All Releases 2 1B. Gaseous Effluents for Release Point - Main Stack 3 1C. Gaseous Effluents for Release Point -

Unit 2 and Unit 3 Roof Vents 5 2A. Liquid Effluents - Summation of All Releases 7 2B. Liquid Effluents 8 III. Classes of Solid Radioactive Waste Shipments 9 IV. Attachments A. Supplemental Information 10 Technical Concurrences: (for accuracy of infonnation)

Radwaste Manager

0. C Chemistry Manager i

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1. INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2h(2) 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 July 1,1993 through December 31,1993. The notations E and E- are used to denote positive and negative exponents to the base 10, respectively.

The release of radioactive materials during the reporting period was within the Technical Specification limits. There were no changes made to the Off-Site Dose Calculation Manual (ODCM) during the reporting period.

Estimated particulate, iodine, and fission gas releases were determined for a 7-day period when an improperly secured main stack particulate and cartridge filter assembly resulted in diluted sample flow (PBAPS LER 2-93-15).

There were two unplanned releases of liquid radioactive material.

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1 EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) e Table 1A Page 1 of 1 l Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST.

3 4 ERROR TOTAL %

A. Fission & activation gases

1. Total release Ci 5.25E3 2.08E3 18.8
2. Average release rate for period pCi/sec 6.67E2 2.65E2 18.8
3. Gamma Air Dose Millirad 1.40E-1 6.63E-2 18.8 Percent of Technical Specification  % 1.40E0 6.63E-1 18.8
4. Beta Air Dose Millirad 1.39E-1 6.10E-2 18.8 Percent of Technical Specification  % 6.95E-1 3.05E-1 18.8 B. lodines
1. Total iodine-131 Ci 3.06E-2 4.34E-3 22.9
2. Average release rate for period pCi/sec 3.89E-3 5.52E-4 22.9
3. Critical Organ dose Millirem 1.19E-1 1.87E-2 22.9 Percent of Technical Specification  % 7.93 E-1 1.25E-1 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 3.48E-3 2.24E-3 22.9 and Strontium 89-90)
2. Average release rate for period pCi/sec 4.43E-4 2.85 E-4 22.9
3. Average Gross Alpha Radioactivity Ci 5.68E-6 2.26E-5 22.9 D. Tritium
1. Total release Ci 8.88E0 4.68E0 23.5
2. Average release rate br period pCi/sec 1.13E0 5.95E-1 23.5 2

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) -

Table IB Page 1 of 2 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode l I

Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Krypton - 85M Ci 1.51E2 7.40E1 0 0 Krypton - 87 Ci 1.85E2 1.25E2 0 0 Krypton - 88 Ci 5.55El 7.49El 0 0 Xenon - 133 Ci 1.16E3 4.93E2 0 0 Xenon - 135 Ci 7.89E2 3.97E2 0 0 Xenon - 135M Ci 7.26E2 1.51E2 0 0 Xenon - 138 Ci 7.45E2 2.87E2 0 0 Xenon - 133M Ci 9.61E0 0 0 0 l Unidentified Ci 9.04E2 2.51E2 0 0 l Total for Period Ci 4.73E3 1.85E3 0 0
2. Iodines Iodine - 131 Ci 1.93E-2 2.24E-3 0 0 lodine - 133 Ci 5.58E-2 9.48E-4 0 0 Iodine - 135 Ci 1.74E-2 0 0 0 Total for Period Ci 9.25E-2 3.19E-2 0 0
3. Particulates Strontium - 89 Ci 1.35E-3 1.14E-3 0 0 Strontium - 90 Ci 1.63E-6 2.32 E-6 0 0 Strontium - 91 Ci 5.71E-4 1.04 E-3 0 0  ;

l Cesium - 134 Ci 0 1.47E-5 0 0 Cesium - 137 Ci 3.79E-5 3.26E-5 0 0  ;

Cesium - 138 Ci 6. 89E-2 2.53E-2 0 0 l Barium - 139 Ci 4.22E-3 1.32 E-2 0 0 Barium - 140 Ci 3.95E-4 8.44E-4 0 0 Lanthanum - 140 Ci 2.38E-4 6.31E-4 0 0 Cobalt - 57 Ci 0 0 0 0 Cobalt - 58 Ci 0 0 0 0 3

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IB Page 2 of 2 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Cobalt - 60 Ci 0 5.57E-6 0 0 Zinc - 65 Ci 0 0 0 0 Yttrium - 91M Ci 5.73E-3 6.05E-4 0 0 Iodine - 133 Ci 9.88E-5 7.18E-6 0 0 Copper - 64 Ci 0 0 0 0 Rubidium - 88 Ci 0 0 0 0 Manganese - 54 Ci 0 0 0 0 Strontium - 92 Ci 0 0 0 0 lodine - 135 Ci 1.69E-5 0 0 0 Tellurium - 1?2 Ci 4.27E-6 0 0 0 Molybdenum - 99 Ci 9.94E-7 0 0 0 Technetium - 99m Ci 1.51 E-6 0 0 0 TOTAL FOR PERIOD Ci 8.15E-2 4.28E-2 0 0 1

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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IC Page 1 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units 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 2.64E1 0 0 0 Xenon - 135 Ci 4.74E1 0 0 0 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 0 Unidentified Ci 4.39E2 2.25E2 0 0 Total for Period Ci 5.13E2 2.25E2 0 0
2. Iodines Iodine - 131 Ci 1.13E-2 2.10E-3 0 0 Iodine - 133 Ci 7.14E-2 1.18E-2 0 0 Iodine - 135 Ci 1.15E-1 2.50E-2 0 0 Total for Period Ci 1.98E-1 3.89E-2 0 0
3. Particulates Strontium - 89 Ci 5.80E-4 1.39E-4 0 0 Strontium - 90 Ci 4.13E-6 3.07E-6 0 0 Strontium - 91 Ci 1.21E-3 9.41E-5 0 0 Cesium - 134 Ci 4.61E-5 0 0 0 Cesium - 137 Ci 1.86E-4 3.12E-5 0 0 Cesium - 138 Ci 4.09E-2 3.68E-3 0 0 Barium - 139 Ci 8.65E-3 1.98E-3 0 0 Barium - 140 Ci 4.96E-4 0 0 0 Lanthanum - 140 Ci 6.09E-4 9.39E-5 0 0' Cobalt - 57 Ci 0 0 0 0 Cobalt - 58 Ci 3.41E-6 0 0 0 Cobalt - 60 Ci 5.98E-5 0 0 0 5

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IC Page 2 of 2 Gaseous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch hiode Nuclides Released Units Quarter Q a ter Quarter Quter .

3 4 3 4 Zine - 65 Ci 0 0 0 0 Yttrium - 91M Ci 3.73E-3 6.53E-5 0 0 Iodine - 133 Ci 9.17E-4 3.64E-4 0 0 Copper - 64 Ci 0 0 0 0 Rubidium - 88 Ci 0 0 0 0 Manganese - 54 Ci 0 0 0 0 Strontium - 92 Ci 0 0 0 0 Cadmium - 109 Ci 1.02E-4 0 0 0 Technetium - 99m Ci 1.74E-5 0 0 0 TOTAL FOR PERIOD Ci 5.75E-2 6.45E-3 0 0 i

6

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 2A Page 1 or 1 Liquid Efnuents - Summation of All Releases Quarter Quarter Est. Error Units 3 4 Total %

A. Fission & activation products l

1. Total release (not including tritium, gases, alpha) Ci 2.61E-2 2.75E-2 22.9
2. Average diluted concentration during period pCi/ml 5.99E-11 7.39E-11 22.9
3. Total Body Dose ADULT BODY Millirem 3.10E-3 5.43E-3 22.9 Percent of Technical Specification  % 1.03E-1 1.81E-1 22.9 .

I

4. Maximally Exposed Organ Dose TEEN LIVER Millirem 5.47E-3 9.72E-3 22.9 ,

Percent of Technical Specification  % 5.47E-2 9.72E-2 22.9 B. Tritium

1. Total release Ci 1.88E0 3.37E-1 15.0
2. Average diluted concentration during period Ci/m! 4.31E-9 9.06E-10 15.0 C. Dissolved and entrained gases
1. Total release Ci 9.67E-3 1.49E-4 22.9
2. Average diluted concentration during period Ci/mi 2.22E-11 4.01E-13 22.9 D. Gross alpha radioactivity
1. Total release Ci 3.71E-5 6.24E-6 22.9
2. Average diluted concentration during period Ci/ml 8.51E-14 1.68E-14 22.9 E. Volume of waste released (prior to dilution) liters 9.61E5 1.73E5 12.7 F. Volume of dilution water used during period liters 4.36E11 3.72E11 10.9 i

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A

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 2B Page 1 of I Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quuter Quarter Quarter Quarter 3 4 3 4 Strontium - 89 Ci 9.18E-6 9.94E-6 1.08E-4 3.21E-6 Strontium - 90 Ci 5.33E-7 6.51E-7 3.08E-5 6.25E-7 Alpha Ci 8.68E-7 9.93E-7 3.62E-5 5.25E-6 Tritium Ci 4.51E-2 4.99E-2 1.83E0 2.87E-1 Phosphorus - 32 Ci 6.19E-6 6.25E-6 1.64E-4 1.95E-5 Iron - 55 Ci 3.51E-4 3.48E-4 5.53E-4 6.66E-5 Xenon - 131M Ci 0 0 0 0 Xenon - 133 Ci 0 0 3.41E-3 4.01E-5 Xenon - 133M Ci 0 0 0 0 Xenon - 135 Ci 0 0 6.22E-3 1.09E-4 Xenon - 135M Ci 0 0 3.67E-5 0 Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Manganese - 54 Ci 3.33E-3 3.65E-3 2.72E-7 0 Cesium - 134 Ci 2.27E-4 2.57E-4 4.64E-6 3.38E-6 Cesium - 137 Ci 5.99E-4 6.53E-4 1.71E-5 1.20E-5 Cesium - 138 Ci 0 0 0 0 Zine - 65 Ci 8.88E-3 9.75E-3 0 0 Sodium - 24 Ci 0 0 0 0 Cobalt - 58 Ci 9.18E-4 9.80E-4 0 0 Cobalt - 60 Ci 1.04E-2 1.12E-2 1.82E-5 2.82E-6 Chromium - 51 Ci 5.23E-4 5.07E-4 0 0 TOTAL FOR PERIOD Ci 7.03 E.2 7.73E-2 1.84E0 2.87E-1 (ABOVE) 8

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (07/01/93 - 12/31/93)

PEACH BOTTOM UNITS 2 & 3 JULY 1,1993 TO DECEMBER 31,1993 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS Total # of Waste Description Individual Total Shipments (source of waste) Container / Type Volume Volume Total Principal (cubic ft.) (cubic ft.) Curie Radionuclides Cliss A 19 Dewatered Resin HIC / Type A Cask 202.1 3839.9 4.30E + 02 Zn-65,Co-60, Cs-137, Cs-134, Cr-51 1 Dewatered Resin HIC / Type A Cask 132.4 132.4 1.78E + 01 Zn45,Co-60, Cs-137, Mn-54, Cs-134 13 DAW Metal Drum /STC, variable (*) 207.6 1.13E-01 Co-60,Zn-65, Metal Box /STC Fe-55, Cs-137, Mn-54 71 DAW Metal Drum /STC, variable (**) 836.3 1.00E + 00 Co-60, Zn-65, M ' ' Box /STC Fe-55, Cs-137, Mn-54 1 DAW HlC/ Type A Cask 38.3 114.9 3.37E + 00 Co-60, Fe-55, 2n-65 Ni-63 1 DAW HIC / Type A Cask 205.8 205.8 1.41E + 00 Co-60, Cs-137, Zn-65, Fe-55, Mn-54 CLASS B 8 Dewatered Resin HIC / Type A Cask 202.1 1616.8 3.06E + 02 Zn-65, Cs-137, Co-60, Cs-134, Fe-55 2 Dewatered Filters HIC / Type A Cask 38.3 229.8 3.20E +01 Co-60, Fe-55, 2n-65, Ni-63 CLASS C 3 Irradiated H' Ware Steel Liner / 57.8 173.4 6.03E + 04 Fe-55, Co-60, Type B Cask Mn-54, Ni-63, Cr-51 TOTALS 119 7376.9 6.11E + 04 NOTES:

  • -Indicates actual total PECO radwaste shipped from Quadrex, after volume reduction, to the burial site.
    • -Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site.

4 9

',- l.. A'ITACHMENT A SUPPLEMENT INFORMATION

. Facility: Peach Bottora Units 2 & 3 Licenses: DPR-44 DPR-56

1. Reculatory Limits (Technical Specification Limits)

A. Noble Gases:

1. s500 mrem /Yr - total body - " instantaneous" limits s3000 mrem /Yr - skin Tech. Spec. 3.8.C.1.a
2. s 10 mrad - air gamma - quarterly air dose limits s 20 mrad - air beta Tech. Spec. 3.8.C.2.a
3. s 20 mrad - air gamma - yearly air dose limits

$40 mrad - air beta Tech. Spec. 3.8.C.2.b B. Iodines. Tritium. Particulates with Half Life > 8 days:

1. s1500 mrem /Yr - any organ - " instantaneous" limits (inhalation path) Tech. Spec. 3.8.C.1.b
2. s 15 mrem - any organ - quarterly dose limits Tech. Spec. 3.8.C.3.a
3. s 30 mrem - any organ - yearly dose limits Tech. Spec. 3.8.C.3.b C. Liquid Effluents
1. Concentration s 10 CFR 20, - " instantaneous" limits Appendix B, Table II, Col. 2 Tech. Spec. 3.8.B.1
2. s 3.0 mrem - total body - quarterly dose limits s 10 mrem - any organ Tech. Spec. 3.8.B.2.a
3. s 6.0 mrem - total body - yearly dose limits s 20 mrem - any organ - Tech. Spec. 3.8.B.2.b
2. Maximum Permiss" .'e Concentrations:

MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.

The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified nuclides are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Technical Specification 3.8.B.1.

10

'. ATTACHMENT A (continued)

3. Average Energy:

Not Applicable

4. Measurements and Anproximations of Total Radioactivity:

A. Fission and Activation Gases:

The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System

- Gas Marinelli -

B. Iodine:

The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System

- Charcoal Cartridge -

C. Particulates:

The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System

- Air Particulate Sample, (47mm and 57mm filters) -

D. Liquid Effluents:

l The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli

5. Eatch Releasca:

A. Liquid:

DTR 3 OTR 4 Number of batch releases: 15 7 Total time for batch releases (minutes): 3506 893 Maximum time period for batch release (minutes): 368 260 Average time period for batch release (minutes): 234 128 Minimum time period for batch release (minutes): 43 65 Dilution volume (liters): 1.37E10 2.28E9 B. Gaseous:

]

1 l

Not applicable 11

',; A'ITACHMENT A (continued)

Abnormal Releases:

6.

A. Liquid:

1. Event description - On 7/23/93 rcutine sampling of the high pressure service water (HPSW) effluent to the discharge canal detected low level radioactive l

contamination. Subsequent investigation determined that a trace amount of condensate stay full or primary coolant water was leaking past the Unit 2 'B' i residual heat removal (RHR) heat exchanger floating head gasket into the 'B' l loop of the HPSW system. The gasket was replaced and leak tested satisfactorily.

It was estimated that the contaminated water released 7.65E-3 millirem total body dose to the discharge canal from 7/23/93 to 12/7/93. This dose contribution was well below the limits specified in Technical Specifications.

Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The Dose contributions ,

and Isotope quantities from this continuous release were added to this Semi- l Annual Effluent Report for the applicable reporting period.

2. Event description - On 11/10/93 routine sampling of the high pressure service water (HPSW) effluent to the discharge canal detected low level radioactive contamination. Subsequent investigation 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 Doating head gasket into the 'A' loop of the HPSW system. The gasket was replaced and leak tested satisfactorily.

i It was estimated that the contaminated water released 6.41E-4 millirem total body dose to the discharge canal from 11/10/93 to 1/9/94. This dose contribution was well below the limits specified in Technical Specifications.

Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The Dose contributions and Isotope quantities from this continuous release were added to this Semi-Annual EfDuent Report for the applicable reporting period.

12

ATTACHMENT A (continued)

,' 6. Abnormal Releases: (Continued)

B. Gaseous:

PBAPS LER 2-93-15 Event Description - While performing the weekly filter change on December 1, 1993 the Main Stack Particulate Filter and Charcoal Cartridge Assembly was found to be improperly secured, resulting in diluted sample flow. Accordingly, representative sampling of Main Stack particulate, iodine, and fission gas releases was not obtained for the 7-day period from November 24 through December 1, 1993.

Analysis of Release - Based on existing radiological controls and current and previous plant experience, it is believed that no abnormal particulate, iodine, or fission gas releases occurred. Release values during the unmonitored period were calculated by simply extending the before and after release rates into the unmonitored period.

13

l

. \

.' PEACH BOTTOM ATOMIC POWER STATION I Unit Numbers 2 and 3  !

Docket Numbers 50-277 and 50-278 l

SENU-ANNUAL EFFLUENT RELEASE REPORT NO. 36 JULY 1,1993 THROUGH DECEMBER 31,1993 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56 l

l

.' . . l TABLE OF CONTENTS l SECTION PAGE I. Introduction 1 I

II. Tables )

1A. Gaseous Effluents - Summation of All Releases 2 IB. Gascous Effluents for Release Point - Main Stack 3 1C. Gaseous Effluents for Release Point -

Unit 2 and Unit 3 Roof Vents 5 2A. Liquid Effluents - Summation of All Releases 7 2B. Liquid Effluents 8 III. Classes of Solid Radioactive Waste Shipments 9 IV. Attachments A. Supplemental Information 10 Technical Concurrences: (for accuracy of information)

Radwaste Manager

0. C Chemistry Manager l l

1 l

l l

y.

~

1. INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2h(2) 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 July 1,1993 though December 31,1993. The notations E and E- are used to denote positive and negative exponents to the base 10, respectively.

The release of radioactive materials during the reporting period was within the Technical Specification limits. There were no changes made to the Off-Site Dose Calculation Manual (ODCM) during the reporting period.  !

Estimated particulate, iodine, and fission gas releases were determined for a 74ay period whers an improperly secured main stack particulate and cartridge filter assembly resulted in diluted sample flow (PBAPS LER 2-93-15).

There were two unplanned releases of liquid radioactive material.

i i

s

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 1A Page 1 of 1 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST.

3 4 ERROR TOTAL %

A. Fission & activation gases

1. Total release Ci 5.25E3 2.08E3 18.8
2. Average release rate for period pCi/sec 6.67E2 2.65E2 18.8
3. Gamma Air Dose Millirad 1.40E-1 6.63E-2 18.8 Percent of Technical Specification  % 1.40E0 6.63E-1 18.8
4. Beta Air Doe.e Millirad 1.39E-1 6.10E-2 18.8 Percent of Technical Specification  % 6.95E-1 3.05E-1 18.8 B. hx!ines
1. Total icxline-131 Ci 3.06E-2 4.34E-3 22.9
2. Average release rate for period pCi/sec 3.89E-3 5.52E-4 22.9
3. Critical Organ dose Millirem 1.19E-1 1.87E-2 22.9 Percent of Technical Specification  % 7.93E-1 1.25E-1 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 3.48E-3 2.24E-3 22.9 and Strontium 89-90)
2. Average release rate for period pCi/sec 4.43E-4 2. 85E-4 22.9
3. Average Gross Alpha Radioactivity Ci 5.68E-6 2.26E-5 22.9 D. Tritium
1. Total release Ci 8.88E0 4.68E0 23.5
2. Average release rate for period pCi/sec 1.13E0 5.95E-1 23.5 2

I 1

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 1B Page 1 of 2 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases Krypton - 85M Ci 1.51E2 7.40El 0 0 Krypton - 87 Ci 1.85E2 1.25E2 0 0 i

Krypton - 88 Ci 5.55El 7.49El 0 0 Xenon - 133 Ci 1.16E3 4.93E2 0 0 -

Xenon - 135 Ci 7.89E2 3.97E2 0 0 Xenon - 135M Ci 7.26E2 1.51E2 0 0 Xenon - 138 Ci 7.45E2 2.87E2 0 0 Xenon - 133M Ci 9.61E0 0 0 0 l Unidentified Ci 9.04E2 2.51E2 0 0 l Total for Period Ci 4.73E3 1.85E3 0 0 -

2. Iodines i

Iodine - 131 Ci 1.93E-2 2.24E-3 0 0 lodine - 133 Ci 5.5 SE-2 9.48E-4 0 0 Iodine - 135 Ci 1.74E-2 0 0 0 Total for Period Ci 9.25E-2 3.19E-2 0 0

3. Particulates Strontium - 89 Ci 1.35E-3 1.14 E-3 0 0 Strontium - 90 Ci 1.63 E-6 2.32E-6 0 0 Strontium - 91 Ci 5.71E-4 1.04 E-3 0 0 Cesium - 134 Ci 0 1.47E-5 0 0 Cesium - 137 Ci 3.79E-5 3.26E-5 0 0 Cesium - 138 Ci 6. 89E-2 2.53E-2 0 0 ,

Barium - 139 Ci 4.22E-3 1.32E-2 0 0 Barium - 140 Ci 3.95E-4 8.44E-4 0 0 Lanthanum - 140 Ci 2.3 8E-4 6.31E-4 0 0 Cobalt - 57 Ci 0 0 0 0  !

Cobalt - S S Ci 0 0 0 0 l l

1 3  !

a 1

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IB Page 2 of 2 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Cobalt - 60 Ci 0 5.57E-6 0 0 Zine - 65 Ci 0 0 0 0 Yttrium - 91M Ci 5.73E-3 6.05E-4 0 0 Iodine - 133 Ci 9.88E-5 7.18E-6 0 0 Copper - 64 Ci 0 0 0 0 Rubidium - 88 Ci 0 0 0 0 Manganese - 54 Ci 0 0 0 0 Strontium - 92 Ci 0 0 0 0 Iodine - 135 Ci 1.69E-5 0 0 0 Tellurium - 132 Ci 4.27E-6 0 0 0 Molybdenum - 99 Ci 9.94E-7 0 0 0 Technetium - 99m Ci 1.51E-6 0 0 0 TOTAL FOR PERIOD Ci 8.15E-2 4.28E-2 0 0 l

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EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IC Page 1 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quaner Quarter 3 4 3 4

1. Fission Fa8e8 Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 2.64E1 0 0 0 Xenon - 135 Ci 4.74E1 0 0 0 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 0 Unidentified Ci 4.39E2 2.25E2 0 0 Total for Period Ci 5.13E2 2.25E2 0 0
2. Iodines lodine - 131 Ci 1.13E-2 2.10E-3 0 0 Iodine - 133 Ci 7.14E-2 1.18E-2 0 0 lodine - 135 Ci 1.15E-1 2.50E-2 0 0 Total for Period Ci 1.98E-1 3.89E-2 0 0
3. Particulates Strontium - 89 Ci 5.80E-4 1.39E-4 0 0 Strontium - 90 Ci 4.13E-6 3.07E-6 0 0 Strontium - 91 Ci 1.21E-3 9.41E-5 0 0 Cesium - 134 Ci 4.61E-5 0 0 0 Cesium - 137 Ci 1.86E-4 3.12E-5 0 0 Cesium - 138 Ci 4.09E-2 3.68E-3 0 0 Barium - 139 Ci 8.65E-3 1.98E-3 0 0 Barium - 140 Ci 4.96E-4 0 0 0 Lanthanum - 140 Ci 6.09E-4 9.39E-5 0 0 Cobalt - 57 Ci 0 0 0 0 Cobalt - 58 Ci 3.41E-6 0 0 0 Cobalt - 60 Ci 5.98E-5 l 0 0 0 5

s EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table IC Page 2 of 2 Gaseous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode i

Nuclides Relemed Units Quarter Quarter Quarter Quarter 3 4 3 4 l Zinc - 65 Ci 0 0 0 0 Yttrium - 91M Ci 3.73E-3 6.53E-5 0 0 Iodine - 133 Ci 9.17E-4 3.64E-4 0 0 Copper - 64 Ci 0 0 0 0 Rubidium - 88 Ci 0 0 0 0 Manganese - 54 Ci 0 0 0 0 S* e atium - 92 Ci 0 0 0 0 Cadmium - 109 Ci 1.02E-4 0 0 0 Technetium - 99m Ci 1.74E-5 0 0 0 TOTAL FOR PERIOD Ci 5.75E-2 6.45E-3 0 0 l

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6

9 EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 2A Page 1 of 1 Liquid Efnuents - Summation of All Releases Quarter Quarter Est. Error Units 3 4 Total %

A. Fission & activation products

1. Total release (not including tritium, gases, alpha) Ci 2.61E-2 2.75E-2 22.9
2. Average diluted concentration during period pCi/ml 5.99E-11 7.39E-11 22.9
3. Total Body Dose ADULT BODY Millirem 3.10E-3 5.43E-3 22.9 Percent of Technical Specification  % 1.03E-1 1.81E-1 22.9
4. Maximally Exposed Organ Dose TEEN LIVER Millirem 5.47E-3 9.72E-3 22.9 Percent of Technical Specification  % 5.47E-2 9.72E-2 22.9 B. Tritium
1. Total release Ci 1.88E0 3.37E-1 15.0
2. Average diluted concentration during period pCi/ml 4.31E-9 9.06E-10 15.0 C. Dissolved and entrained gases
1. Total release Ci 9.67E-3 1.49E-4 22.9
2. Average diluted concentration during period Ci/ml 2.22E-11 4.01E-13 22.9 D. Gross alpha radioactivity
1. Total release Ci 3.71E-5 6.24 E-6 22.9
2. Average diluted concentration during period Ci/ml 8.51E-14 1.68E-14 22.9 E. Volume of waste released (prior to dilution) liters 9.61E5 1.73E5 12.7 F. Volume of dilution water used during period liters 4.36E11 3.72E11 10.9 7

+ EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)

Table 2B Page 1 of 1 Liquid Effluents  !

1 Continuous Mode Batch Mode l

Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Strontium - 89 Ci 9.1SE4 9.94E-6 1.0SE-4 3.21E-6 Strontiurn - 90 Ci 5.33 E-7 6.51E-7 3.08E-5 6.25E-7 Alpha Ci 8.68E-7 9.93E-7 3.62E-5 5.25E-6 Tritium Ci 4.51E-2 4.99E-2 1.83E0 2.87E-1 Phosphorus - 32 Ci 6.19E-6 6.25E-6 1.64E-4 1.95E-5 Iron - 55 Ci 3.51E-4 3.48E-4 5.53E-4 6.66E-5

. Xenon - 131M Ci 0 0 0 0 Xenon - 133 Ci 0 0 3.41E-3 4.01E-5 Xenon - 133M Ci 0 0 0 0 Xenon - 135 Ci 0 0 6.22E-3 1.09E-4 Xenon - 135M Ci 0 0 3.67E-5 0 Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Manganese - 54 Ci 3.33E-3 3.65E-3 2.72E-7 0 Cesium - 134 Ci 2.27E-4 2.57E-4 4.64E-6 3.38E-6 Cesium - 137 Ci 5.99E-4 6.53E-4 1.71E-5 1.20E-5 Cesium - 138 Ci 0 0 0 0 Zinc - 65 Ci 8.tSE-3 9.75E-3 0 0 Sodium - 24 Ci 0 0 0 0 Cobalt - 58 Ci 9.18E-4 9.80E-4 0 0 Cobalt - 60 Ci 1.04 E-2 1.12E-2 1.82E-5 2.82E-6 Chromium - 51 Ci 5.23 E-4 5.07E-4 0 0 TOTAL FOR PERIOD Ci 7.03E-2 7.73 E-2 1.84E0 2.87E-1 (ABOVE) 8

. EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (07/01/93 - 12/31/93)

PEACH BOTTOM UNITS 2 & 3 JULY 1,1993 TO DECEMBER 31,1993 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS Total # of Waste Description Individual Total Shiprnents (source of waste) . ContainerfType Volume Volume Total Principal (cubic ft.) (cubic ft.) Curie Radionuclides Class A 19 Dewatered Resin HIC / Type A Cask 202.1 3839.9 4.30E + 02 Zn-65,Co-60, Cs-137, Cs-134, Cr-51 1 Dewatered Resin HIC / Type A Cask 132.4 132.4 1.78E +01 Zn-65,Co-60, ,

Cs-137, Mn-54, Cs-134 13 DAW Metal Drum /STC, variable (*) 207.6 1.13E-01 Co-60,Zn-65, Metal Box /STC Fe-55, Cs-137, Mn-54 71 DAW Metal Drum /STC, variable (") 856.3 1.00E + 00 Co-60, Zn-65, Metal Box /STC Fe-55, Cs-137, Mn-54 1 DAW HICfrype A Cask 38.3 114.9 3.37E + 00 Co-60, Fe-55, Zn45, Ni-63 1 DAW HIC / Type A Cask 205.8 205.8 1.41E + 00 Co40, Cs-137, Zn-65, Fe-55, Mn-54 CLASS B 8 Dewatened Resin HICfrype A Cask 202.1 1616.8 3.06E + 02 Zn-65, Cs-137, Co-60, Cs-134, Fe-55 2 Dewatered Filters HICfrype A Cask 38.3 229.8 3.20E + 01 Co-60, Fe-55, Zn-65, Ni43 CLASS C 3 Irradiated H' Ware Steel Liner / 57.8 173.4 6.03E + 04 Fe-55, Co-60, Type B Cask Mn-54, Ni-63, Cr-51 ,

l TOTALS 119 7376.9 6.11E + 04 NOTES:

  • - Indicates actual total PECO radwaste shipped from Quadrex, after volume reduction, to the burial site.

l

" - Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site.

9

. ATTACHMENT A

SUPPLEMENT INFORMATION Facility
  • Peach Bottom Units 2 & 3 Licenses: DPR-44 DPR-56
1. Regulatory Limits (Technical Specification Limits)

A. Noble Gases:

1. s500 mrem /Yr - total body - " instantaneous" limits s 3000 mrem /Yr - skin Tech. Spec. 3.8.C.1.a
2. s 10 mrad - air gamma - quarterly air dose limits s 20 mrad - air beta Tech. Spec. 3.8.C.2.a
3. s 20 mrad - air gamma - yearly air dose limits s 40 mrad - air beta Tech. Spec. 3.8.C.2.b B. Iodines. Tritium. Particulates with Half Life > 8 days
1. s1500 mrem /Yr - any organ - " instantaneous" limits (inhalation path) Tech. Spec. 3.8.C.1.b
2. s 15 mrem - any organ - quarterly dose limits Tech. Spec. 3.8.C.3.a
3. 5 30 mrem - any organ - yearly dose limits Tech. Spec. 3.8.C.3.b j C. Liauid Effluents
1. Concentration s10 CFR 20, - " instantaneous" limits Appendix B, Table II, Col. 2 Tech. Spec. 3.8.B.1
2. s 3.0 mrem - total body - quarterly dose limits s 10 mrem - any organ Tech. Spec. 3.8.B.2.a i l
3. s 6.0 mrem - total body - yearly dose limits l s 20 mrem - any organ - Tech. Spec. 3.8.B.2.b I
2. Maximum Permissible _C'oncentrations:

I 1

MPCs are not used to calculate permissible release rates and concentrations for gaseous {

releases.

)

The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified  ;

nuclides are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Technical Specification 3.8.B.1.

10 l

'i,;'- ATTACHMENT A (contmued)

.a

,' 3. Average Energy:

Not Applicable

4. Measurements and Approximations of Total Radioactivity:

A. Fission and Activation Gases:

l The method used is the Nuclear Data 6700 Counting System or the Canberra l

S95/ Dual Host 3400 Counting System l - Gas Marinelli -

B. Joding:

The method used is the Nuclear Data 6700 Counting System or the Canberra ,

S95/ Dual Host 3400 Counting System  ;

- Charcoal Cartridge - l l

C. Particulates: l l

The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System

- Air Particulate Sample, (47mm and 57mm filters) -

I D. Liquid Effluents:

The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli

5. Itatch Releases:

A. liquid:

_O T R 3 OTR 4 Number of batch releases: 15 7 Total time for batch releases (minutes): 3506 893 Maximum time period for batch release (minutes): 368 260 Average time period for batch release (minutes): 234 128 Minimum time period for batch release (minutes): 43 65 Dilution volume (liters): 1.37E10 2.28E9 B. Gaseous:

Not applicable 11 l

- _- _A

. ATTACHMENT A (continued) l

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6. Abnormal Releases: I A. Liquid:
1. Event description - On 7/23/93 routine sampling of the high pressure service l water (HPSW) efDuent to the discharge canal detected low level radioactive contamination. Subsequent investigation determined that a trace amount of condensate stay full or primary coolant water was leaking past the Unit 2 'B' residual heat removal (RHR) heat exchanger floating head gasket into the 'B' loop of the HPSW system. The gasket was replaced and leak tested satisfactorily.

It was estimated that the contaminated water released 7.65E-3 millirem total body dose to the discharge canal from 7/23/93 to 12/7/93. This dose contribution was well below the limits specified in Technical Specifications.

Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The Dose contributions and Isotope quantities from this continuous release were added to this Semi-Annual Effluent Report for the applicable reporting period.

2. Event description - On 11/10/93 routine sampling of the high pressure service water (HPSW) effluent to the discharge canal detected low level radioactive contamination. Subsequent investigation 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 floating head gasket into the 'A' loop of the HPSW system. The gasket was replaced and leak tested satisfactorily.

It was estimated that the contaminated water re. leased 6.41E-4 millirem total body dose to the discharge canal from 11/10/93 to 1/9/94. This dose contribution was well below the limits specified in Technical Specifications.

Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The Dose contributions and Isotope quantities from this continuous release were added to this Semi-Annual Effluent Repon for the applicable reporting period.

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p *,: ' . t ? _

ATTACHMENT A (continued).

'4

' '~ 6. . Abnormal Releases: (Continued)-

B. Gaseous:

PBAPS LER 2-93-15 Event Description While performing' the weekly filter change on December'1, 1993 the Main Sbck Particulate Filter and Charcoal Cartridge Assembly was fouad to be improperly secured, resulting in diluted sample flow. - Accordingly, representative sampling of Main Stack particulate, iodine, and fission gas releases was not obtained for the 7-day period from November 24 through December 1, 1993.

Analysis of Release - Based on existing radiological controls and current and -

previous plant experience, it is believed that no abnormal particulate, iodine, or fission gas releases occurred. Release values during the unmonitored period were calculated by simply extending the before and after release rates into the unmonitored period.

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