ML20082P999

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Annual Effluent Release Rept 37 Jan-Dec 1994
ML20082P999
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1994
From: Rainey G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-95-14036, NUDOCS 9504280005
Download: ML20082P999 (22)
v • d • e


Text

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T

o. red c. nwoey CCN 95-14036 Vice Przsident A Peach Bottom Atomic Power station PECO ENERGY - - -

ecco teerov co-o ev RD 1. Box 208 oelta, PA 17314 9739 717 456 7014 April 17,1995 Docket Nos. 50-277 50-278 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Annual Effluent Release Report No. 37 January 1,1994 through December 31,1994 Peach Bottom Atomic Power Station Unit Nos. 2 and 3 Gentlemen:

Enclosed are two copies of the Annual Effluent Release Report No. 37, January 1,1994 through December 31,1994 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.

This report is being submitted in compliance with 10CFR 50.36a (a) (2) and the Technical Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of ,

Regulatory Guide 10.1. i Sincerely,

// %

Gerald R. Rainey / )

Vice President, Peac o m Atomic Power Station GRR/GDE/ ADO /SCB:a0 enclosures i I

cc: R. A. Burricelli, Public Service Electric & Gas Company W. P. Domsife, Commonwealth of Pennsylvania W. L Schmidt, USNRC Senior Resident inspector R.1. McLean, State of Maryland T. T. Martin, Administrator, Region I, USNRC  !

H. C. Schwemm, Atlantic Electric Company  !

A. F. Kirby, Delmarva Power & Light j INPO Records Center  !

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J. A. Bernstein . W/O Attachments 51 A-13, Chesterbrook J. B. Cotton 63B-5, Chesterbrook E. J. Cullen +* * "

S23-1, Main Office A. F. Fulvio SMB-4, Peach Bottom W. G. MacFarland, IV " "

Limerick G. A. Hunger 52A-5, Chesterbrook G. R. Rainey SMB-4, Peach Bottom R. A. Kankus 62C-3, Chesterbrook D. M. Smith 63C-3, Chesterbrook Correspondence Control Desk 61B-3, Chesterbrook Peach Bottom Nuclear Records SMB-1, Peach Bottom J

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- PEACII BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 ANNUAL EFFLUENT RELEASE REPORT NO. 37 JANUARY 1,1994 THROUGH DECEMBER 31,1994 I

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

I' TABLE OF CONTENTS SECTION PAGE I. Introduction 1 1-II. Tables l

1A. Gaseous Effluents - Summation of All Releases 2 -l

I IB. Gaseous Effluents for Release Point - Main Stack 4- ..

' I C. Gaseous Effluents for Release Point -

Unit 2 and Unit 3 Roof Vents 8 2A.- Liquid Effluents - Summation of All Releases 10 l l

2B. Liquid Effluents 12 )

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III. Classes of Solid Radioactive Waste Shipments 14 IV. Attachments A. Supplemental Information 15 l

Technical Concurrences: (for accuracy of information)

Maste M(nager Chemistry Manager i

. ,_ , - . . - . , _ , . _ = . _ . .

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 January 1,1994 through December 31,1994. 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.

l Main Stack vent flow estimations were used to calculate effluent gas releases from January 5,1994 to March 24,1994 when the Main Stack vent flow indication was declared inoperable due to intermittently frozen sensing lines.

There were three unplanned releases of liquid radioactive material.

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

. Table 1 A Page 1 of 2 , ,

Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST.

I 2 ERROR TOTAL %

A. Fission & activation gases

1. Total release Ci 1.81E3 2.16E3 18.8
2. Average release rate for period pCi/sec 2.30E2 2.74E2 18.8  !
3. Gamma Air Dose Millirad 1.10E-1 9.11 E-2 18.8 Percent of Technical Specification  % 1.10E0 9.1 I E-1 18.8
4. Beta Air Dose Millirad 8.54E-2 6.92E-2 18.8 Percent of Technical Specification  % 4.27E-1 3.46E-1 18.8 B. Iodines
1. Total iodine-131 Ci 8.31E-3 6.95E-3 22.9
2. Average release rate for period pCi/sec 1.06E-3 8.84 E-4 22.9
3. Critical Organ dose Millirem 3.52 E-2 3.20E-2 22.9 Percent of Technical Specification  % 2.35E-1 2.13E-1 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 2.36E. 3 1.68E-3 22.9 and Strontium 89-90) _
2. Aserage release rate for period pCi/sec 3.00E-4 2.14 E-4 22.9
3. Average Gross Alpha Radioactivity Ci 5.13E-6 3.58E-6 22.9 I D. ' Tritium
1. Total relean Ci 0 0 23.5 pCi/sec 0 0 23.5
2. Average rieg{ ate for period 2

EFFLUENT & WAh.E DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

Table 1A Page 2 of 2 '

Gaseous Effluents - Summation of All Releases l

UNITS QUARTER QUARTER EST. I 3 4 ERROR l

TOTAL %

A. Fission & activation gases

1. Total release Ci 2.48E3 2.28E3 18.8
2. Average release rate for period pCi/sec 3.15E2 2.90E2 18.8
3. Gamma Air Dose Millirad 7.29E-2 6.89E-2 18.8 Percent of Technical Specincation  % 7.29E-1 6.89E-1 18.8
4. Beta Air Dose Millirad 5.74 E-2 5.68E-2 18.8 i Percent of Technical Specification  % 2.87E-1 2.84E-1 18.8 B. lodmes l l
1. Total iodine-13.' Ci 5.96E-3 5.97E-3 22.9  !

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2. Average release rate for period Ci/sec 7.58E-4 7.59E-4 22.9 j
3. Critical Organ dose Millirem 3.20E-2 2.49E-2 22.9 i 1

Percent of Technical Specification  % 2.13 E-1 1.66E-1 22.9 l l

C. Particulates j

1. Particulates with half-lives  ;

greater than 8 days (includes Alpha Ci 1.76E-3 1.28E-3 22.9 l and Strontium 89-90)

2. Average release rate for period pCi/sec 2.24E-4 1.68E-4 22.9
3. Average Gross Alpha Radioactivity Ci 4.92E-6 6.86E-6 22.9

]

D. Tritium l

1. Total release Ci 5.24E0 0 23.5
2. Average release rate for period pCi/sec 6.67E-1 0 23.5 l l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

Table IB Page 1 of 4 ,

Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2

1. Fission gases Krypton - 85M Ci 1.92El 2.21El 0 0 Krypton - 87 Ci 4.62E1 0 0 0 Krypton - 88 Ci 1.80El 0 0 0 Xenon - 133 Ci 5.28E2 8.23E2 0 0 Xenon - 135 Ci 3.66E2 9.67E2 0 0 Xtnon - 135M Ci 1.28E2 0 0 0 Xenon - 138 Ci 1.97E2 0 0 0 Unidentified Ci 8.62E1 0 0 0 Total for Period Ci 1.39E3 1.81E3 0 0
2. lodines lodine - 131 Ci 4.45 E-3 3.46E-3 0 0 lodine - 133 Ci 1.41E-2 1.21E-2 0 0 lodine - 135 Ci 8.16E-3 1.02E-2 0 0 Total for Period Ci 2.67E-2 2.58E-2 0 0
3. Particulates Strontium - 89 Ci 1.07E-3 9.27E-4 0 0 Strontium - 90 Ci 2.55E-6 9.59E-7 0 0 Strontium - 91 Ci 1.19E-3 4.69E-4 0 0 Cesium - 137 Ci 9.19E-6 1.86E-6 0 0 Cesium - 138 Ci 3.29E-2 3.42E-2 0 0 l l

Barium - 139 Ci 1.16E-2 4.94 E-3 0 0  ;

1 Barium - 140 Ci 7.06E-4 3.04 E-4 0 0 Lanthanum - 140 Ci 4.78E-4 1.92E-4 0 0 4

i EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

Table IB Page 2 of 4 Gaseous Effluents For Release Point - Main Stack Continuous Batch Mode Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 Yttrium - 91M Ci 7.50E4 2.88E-4 0 0 lodine - 133 Ci 1.84 E-6 1.47E-5 0 0 Tellurium - 132 Ci 2.01 E-6 0 0 0 Rubidium - 89 Ci 1.45 E-3 0 0 0 TOTAL FOR PERIOD Ci 5.02E-2 4.13E-2 0 0 5

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

T ble IB Page 3 of 4 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quaner Quarter Quarter Quaner 3 4 3 4

1. Fission gases Krypton - 85M Ci 4.12E2 5.85E2 0 0 Krypton - 87 Ci 0 3.84E1 0 0 6

Krypton - 88 Ci 2.38El 6.39El 0 0 Xenon - 133 Ci 1.44E3 7.40E2 0 0 Xenon - 135 Ci 2.95E2 5.75E2 0 0 Xenon - 135M. Ci 0 2.20El 0 0 Xenon - 138 Ci 0 0 0 0 Unidentified Ci 0 0 0 0 Total for Period Ci 2.17E3 2.02E3 0 0

2. Iodines lodine - 131 Ci 2.47E-3 3,30E-3 0 0 Iodine - 133 Ci 6.30E-3 6.18E-3 0 0 lodine - 135 Ci 4.28E-3 6.53E-3 0 0 Total for Period Ci 1.31E-2 1.60E-2 0 0

)

3. Particulates l Strontium - 89 Ci 8.60E-4 7.55E-4 0 0 )

Strontium - 90 Ci 6.01 E.7 1.03 E-6 0 0 Strontium - 91 Ci 1.48E-4 3.15E-4 0 0 Cesium - 137 Ci 5.53E-6 3.25E-6 0 0 Cesium - 138 Ci 3.40E-2 2.30E-2 0 0 1

Barium - 139 Ci 2.36E-3 3.55E-3 0 0 B:rium - 140 Ci 1.02E-4 2.43E-4 0 0 Lanthanum - 140 Ci 8.70E-5 2.04E-4 0 0 l

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

- Ttble IB Page 4 of 4 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quaner Quaner Quarter 3 4 3 4 Cobalt - 60 Ci 0 2.90E-6 0 0 Yttrium - 91M Ci 1.34 E-4 1.99E-4 0 0 lodine - 133 Ci 2.10E-6 2.24E-6 0 0 Rubidium - 89 Ci 2.28E-4 0 0 0 TOTAL FOR PERIOD - Ci 3.79E-2 2.83E-2 0 0 i

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s EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

. 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 1 2 1 2 1, Fission gases Krypton - R$M Ci 0 0 0 0 Krypton - 87 Ci 1.61El 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 Xc.,on - 138 Ci 0 0 0 0 Unidentified Ci 4.06E2 3.44E2 0 0 Total for Period Ci 4.22E2 3.44E2 0 0

2. Iodines Iodine - 131 Ci 3.86E-3 3.49E 3 0 0 lodine - 133 Ci 2.12E-2 2.76E-2 0 0 lodine - 135 Ci 0 0 0 0 Total for Period Ci 2.51 E-2 3.I1E-2 0 0
3. Particulates Strontium - 89 Ci 3.74 E-4 3.57E-4 0 0 Strontium - 90 Ci 3.17E-6 4.08E-6 0 0  !

Cesium - 137 Ci 3.64 E-5 0 0 0 Cesium - 138 Ci 1.45 E-2 2.28E-2 0 0 i Barium - 139 Ci 3.51E-3 3.32E-3 0 0 Barium - 140 Ci 1.51 E-4 7.95E-5 0 0 Yitrium - 91M Ci 2.17E-4 0 0 0 kxline - 133 Ci 7.63E-4 0 0 0 TOTAL FOR PERIOD Ci 1.96E-2 2.66E-2 0 0 8

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

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

1. Fission gases Krypton 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 F.rypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 1.75E0 1.75E-1 0 0 Xenon - 135 Ci 2.91 El 0 0 0 Xenon 135M Ci 0 0 0 0 Xenon-138 Ci 0 0 0 0 Unidentified Ci 2.72E2 2.54E2 0 0 Total for Period Ci 3.03E2 2.54E2 0 0
2. Iodines lodine - 131 Ci 3.49E-3 2.67E-3 0 0 lodine - 133 Ci 2.22E-2 2.33E-2 0 0 lodine - 135 Ci 0 0 0 0 Total for Period Ci 2.57E-2 2.60E-2 0 0
3. Paniculates Strontium - 89 Ci 3.75E-4 2.63 E-4 0 0 Strontium - 90 Ci 3.99E-6 4.34 E-6 0 0 Cesium - 138 Ci 1.83E-2 8.45E-3 0 0 Barium - 139 Ci 4.47E-3 7.73E-3 0 0 Yitrium - 91M Ci 0 1.85 E-4 0 0 lodine - 133 Ci 0 3.88E-4 0 0 Technetium - 99m Ci 9.78E-5 0 0 0 Chromium - 51 Ci 4.03 E-4 0 0 0 TOTAL FOR PERIOD Ci 2.37E-2 1.70E-2 0 0 9

1 EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

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 (not including tritium, gases, alpha) Ci 4.50E-2 3.1 IE-3 22.9
2. Average diluted concentration during period pCi/ml 3.71E-10 1.23E-Il 22.9
3. Total Body Dose ADULT BODY Millirem 1.10E-2 9.07 E-4 22.9 Percent of Technical Specification  % 3.65 E-1 3.02E-2 22.9
4. Maximally Exposed Organ Dose TEEN LIVER Millirem 2.22E-2 1.39E-3 22.9 Percent of Tecimical Specification  % 2.22E-1 1.39E-2 22.9 B. Tritium
1. Total release Ci 3.89E-2 2.89E-1 15.0
2. Average diluted concentration during period pCi/ml 3.21E-10 1.15 E-9 15.0 l

C. Dissolved and entrained gases

1. Total release Ci 0 1.10E-3 22.9
2. Average diluted concentration during period pCi/ml 0 3.10E-10 22.9 D. Gross alpha radioactivity l
1. Total release Ci 4.69E-6 5.48E-6 22.9
2. Average diluted concentration during period pCi/ml 3.87E-14 2.17E-14 22.9 l i

E. Volume of waste released (prior to dilution) liters 1.292E5 1.707ES 12.7 F. Volume of dilution water used during period liters 1.212 Ell 2.524El1 10.9 l

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I EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

' Table 2A Page 2 of 2 Liould Effluents - Summation of All Releases i

Quarter Quarter Est. Error Units 3 4 Total %

A. Fission & activation products

1. Total release (not including tritium. gases, alpha) Ci 2.59E-2 3.57E 22.9
2. Average diluted concentration during period pCi/ml 3.73E-Il 5.48E-11 22.9
3. Total Body Dose ADULT BODY Millirem 2.49E-3 3.34E-5 22.9 Percent of Technical Specification  % 8.30E-2 1.11 E-3 22.9
4. Maximally Exposed Organ Dose TEEN LIVER Millirem 4.53E-3 7.81E-5 22.9 Percent of Technical Specification  % 4.53E-2 7.81E-4 22.9 B. Tritium
1. Total release Ci 7.69E-2 8.82E-1 15.0
2. Average diluted concentration during period pCi/ml 1.11E-10 1.35E-7 15.0 C. Dissolved and entrained gases
1. Total release Ci 0 4.89E-3 22.9
2. Average diluted concentration during period Ci/ml 0 7.51 E-10 22.9 D. Gross alpha radioactivity
1. Total release Ci 1.58E-6 1.07E-5 22.9 2 Average diluted concentration during period pCi/ml 2.27E-15 1.64F-12 22.9 E. Volume of waste released (prior to dilution) liters 4.410E4 3.424E5 12.7 F. Vele:nc of dilution water used during period liters 6.949E11 6.515E9 10.9 11

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

Table 2B Page 1 of 2 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 Strontium - 89 Ci 1.72E-5 1.00E-6 5.63E-8 3.93E-6 Strontium - 90 Ci 2.95 E-6 7.23 E-7 1.59E-8 1.05E-6 Alpha Ci 4.58E-6 3.30E-7 1.09E-7 5.15E-6 Tritium Ci 3.84 E-2 1.20E-2 5.31 E-4 2.77E-1 Phosphorus - 32 Ci 2.80E-5 9.33E-7 5.94 E-7 3.09E-5 Iron - 55 Ci 6.54 E-4 5.53E-5 4.06E-6 1.55E-4

  • Xenon - 133 Ci 0 0 0 3.48E-4 Xenon - 135 Ci 0 0 0 7.53 E-4 Manganese - 54 Ci 3.45E-3 3.23E-4 0 0 Cesium - 134 Ci 2.83E-4 1.12E-4 4.94E-6 2.08E-6 Cesium - 137 Ci 5.18E-4 2.21 E-4 1.28E-5 5.90E-6 Zinc - 65 Ci 3.40E-2 8.11 E-4 0 0 Cobalt - 58 Ci 1.04 E-3 5.72E-5 0 0 Cobalt - 60 Ci 4.72E-3 1.33E-3 1.21 E-6 0 Chromium - 51 Ci 3.02E-4 0 0 0 TOTAL FOR PERIOD Ci 8.34 E-2 1.49E-2 5.55E-4 2.78E-1 12

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/94 - 12/31/94)

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 7.16E-6 0 1.83E-7 8.23 E-6 Strontium - 90 Ci 1.32E-6 0 3.31 E-8 2.25E-6 Alpha Ci 1.36E-6 0 2.22E-7 1.07E-5 Tritium Ci 7.54 E-2 0 1.54 E-3 8.82E-1 Phosphorus - 32 Ci 7.54 E-6 0 5.50E-7 3.26E-5 fron - 55 Ci 6.78E-4 0 4.68 E-6 2.61 E-4 Xenon - 133 Ci 0 0 0 6.01 E-4 Xenon - 135 Ci 0 0 0 4.25E-3 Xenon - 135M Ci 0 0 0 3.54E-5 Manganese - 54 Ci 4.14 E-3 0 0 0 Cesium - 134 Ci 2.0$ E-4 0 7.78E-7 8.57E-7 Cesium - 137 Ci 6.03E-4 0 4.86E-6 6.79E-6 Zinc - 65 Ci 9.55E-3 0 0 0 Cobalt - 58 Ci 5.98E-4 0 0 0 Cobalt - 60 Ci 1.01 E-2 0 0 4.55E-5 l TOTAL FOR PERIOD Ci 1.01 E-1 0 1.55E-3 8.87E-1 i

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (01/01/94 - 12/31/94)

PEACH BOTTOM UNITS 2 & 3 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS l

Total # of Waste Description Individual Total Shipments (source of waste) Contsiner/ Type Volume Volume Total Principal (cubic ft.) (cubic ft.) Curie Radionuclides Class A 28 Dewatered Resin IllC/ Type A Cask 202.1 5658.8 2.75E+02 Zn-65, Cs-137, Co-60 I-131, Cs-134 1 DAW /Dewatered HIC / Type A Cask 135.8 135.8  !.53E +01 Co-60, Fe-55, Zn-65, Filters Ni-63, Cs-137 .

t 2 DAW /Dewatered lilC/ Type A Cask 114.9 229.8 8.35E+00 Co-60 Fe-55, Zn-65, Filters Cr-51, Mn-54 1 DAW /Dewatered lilC/ Type A Cask 205.8 205.8 4.97E-01 Co-60, Cs-137, Zn-65, Filters Fe-55, Ag-110m 2 DAW lilC/ Type A Cask 120.3 240.6 3.00E +00 Co-60, Cs-137, Zn-65, Fe-55, Ag-110m 98 DAW (*) Metal Box /STC variable 2352.8 1.54E+00 Co-60, Cs-137, Zn-65, Fe-55, Mn-54 185 DAW (**) Metal Box /STC variable 6603.9 3.47E+00 Co-60, Cs-137, Zn-65 Fe-55, H-3 CLASS B 2 Dewatered Resin lilC/ Type A Cask 202.1 404.2 2.81E +01 Cs-137, Cs-3 34, Co-60, Zn-65, Cr-51 1 Dewatered Resin lilC/ Type B Cask 132.4 132.4 4.04E +02 Zn-65, Cr-51, Co-60, Mn-54, Co-58 2 Dewatered Filters lilC/ Type A Cask 114.9 229.8 3.25E+01 Co-60, Fe-55, Zn-65, Ni-63, Pu-241 1 Irrad. II' ware / lilC/ Type A Cask 132.4 132.4 2.72E+02 Fe-55, Co-60, Mn-54, Dewa'ered Filters Ni-63 H-3 CLASS C 3 Irradiated II' Ware Steel Liner / Type B 22.4 67.2 4.37E+04 Co-60, Fe-55, Ni-63, Cask Mn-54, Ni-59 3 Irradiated it' Ware Steel Liner / Type B 57.8 173.4 3.42E+04 Co-60, Fe-55, Ni-63, Cask Mn-54, Sb-125 TOTALS 329 16566.9 7.89E +04 NOTES:

Indicates actual total PECO radwaste shipped from American Ecology (Quadrex), after volume reduction, to the burial site.

    • - Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site, j 14 L .

l ATTACHMENT A SUPPLEMENT INFORMATION Facility: - Peach Bottom Units 2 & 3 j Licenses: DPR-44 l DPR-56

1. Regulatory Limits (Technical Snecification Limits)

A. Noble Gases:

1. s500 mrem /Yr - total body - " instantaneous" limits i 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. Liauid Ef0uents
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

3. s 6.0 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.1.

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1 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 Nuclear Data 6700 Counting System or the Canberra S95/ Dual Hest 3400 Counting System

- Gas Marinelli -

B. Iodine:

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

- Charcoal Cartridge -

C. Particulates:

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

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

D. Liquid Ef0uents:

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

5. Batch Releases:

A. Liouid:

OTR 1 ORT 2 OTR3 OTR4 Number of batch releases: 1 4 2 9 Total time for batch releases (minutes): 64 770 310 1721 Maximum time period for ba*ch release (minutes): 64 310 245 300 Average time period for batch release (minutes): 64 192.5 155 191 Minimum time period for batch release (minutes): 64 80 65 40 Dilution volume (liters): 1.635E8 3.543E9 1.584E9 6.515E9 B. Gaseous:

Not applicable 16

A'ITACHMENT A (continued)  ;

6; Abnormal Releases: '

A. Liquid:

1. Event description - On 3/3/94 routine sampling of the high pressure service water ]

'(HPSW) effluent to the discharge canal detected low level radioactive

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contamination. Subsequent investigation determined that a trace amount of j condensate stay full or primary coolant water was leaking past the Unit 3 'C' I 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 1.22E-2 millirem total body _ j dose to the discharge canal from 3/3/94 to 4/10/94. 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 Annual Effluent Report ,

for the applicable reporting period. I

2. Event description - On 5/2/94 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 j condensate stay full or primary coolant water was leaking past the Unit 2 'A' l 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 1.92 E-4 millirem total body dose to the discharge canal from 5/2/94 to 5/31/94. 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 Annual Effluent Report -

for the applicable reporting period.

3. Event description - On 7/8/94 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 'C' 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.

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l ATTACHMENT A (continued) )

.I

-6. Abnormal Releases: (Continued)

A. Liquid: (Continued)

3. (Continued)

It was estimated that the contaminated water released 2.48E-3 millirem total body dose to the discharge canal from 7/8/941o .9/13/94. 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 ased on the actual release conditions. The dose contributions and isotope quantities from this continuous release were added to this Annual Effluent Report . l for the applicable reporting period. <

4. An investigation of these continuing RHR heat exchanger leak problems determined that cross leakage could be prevented by seal . welding the floating head flange to the floating tube sheet. This seal weld fix has been implemented on one RHR heat exchanger and is scheduled for the other seven.

B. Gaseous:

~

The Main Stack vent flow indication was declared inoperable on January 5,1994 due to erratic response. Investigation verified that the outside dilution air being drawn into the eductor was at times cold enough to freeze entrained moisture and restrict the flow in the sensing lines.

It was determined that the only effective corrective action would be to eliminate the components in which the freezing and moisture problems occurred by installing a thermal mass element flow sensor in place of the current pitot tube design. Since this modification of the Main Stack vent flow indication could not be quickly performed, the Main Stack vent flow estimations continued until March 24,1994 when warmer weather eliminated the freezing problem.

The new Main Stack radiation monitors scheduled for installation late in 1995 use thermal mass el:: ment flow sensors to provide vent flow information. Ultimately, these flow sensors will be used to provide input for the Main Stack vent flow indication. Mr awhile, temporary thermal mass element flow sensors were successfully installed on February 24,1995.

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