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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
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 PDR ADOCK 0500 7
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 -
TABLE OF CONTENTS SECTION PAGE I.
Unit 2 and Unit 3 Roof Vents                             5
Introduction 1
                                                                                                    +
II.
2A, Liquid Effluents - Summation of All Releases               7 2B. Liquid Effluents                                           8           r III. Classes of Solid Radioactive Waste Shipments                   9           ,
Tables 1A. Gaseous Effluents - Summation of All Releases 2
                  ' IV. Attachments 1
IB. Gaseous Effluents for Release Point - Main Stack 3
A. Supplemental Information                                 10 Technical Concurrences: (for accuracy ofinformation)
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
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
Radwaste Manager aQOdd Chemistry Manager


          - ~
- ~
l
1.
: 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.
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.
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 re orting 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).
p 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.
There were two unplanned releases of liquid radioactive material.
l l
1 i
1 i
i
i


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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.
Table 1 A Page 1 of 1 Gaseous Effluents - Summation of All Releases UNITS QUARTER Q'UARTER EST.
3         4       ERROR j             TOTAL %
3 4
ERROR j
TOTAL %
A. Fission & activation gases
A. Fission & activation gases
: 1. Total release                             Ci     5.25E3     2.08E3       18.8
: 1. Total release Ci 5.25E3 2.08E3 18.8
: 2. Average release rate for period         pCi/sec   6.67E2     2.65E2       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
: 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
: 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
: 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
: 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
: 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)
: 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
: 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
: 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
: 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
: 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)
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
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
: 1. Fission gases f           Krypton - 85M                                                             Ci                             1.51 E2           7.40E1           0                           0 l
4 3
Krypton - 87                                                             Ci                             1.85E2           1.25E2           0                           0 l
4
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
: 1. Fission gases f
: 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
Krypton - 85M Ci 1.51 E2 7.40E1 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
0 l
l 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 1.51 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)
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
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
l d
4 3
l l
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 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 d
1 4
1 4
l


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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
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
: 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
4 3
: 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
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
: 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
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)                                 ,
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       ;
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
Yttrium - 91M                   Ci     3.73E-3           6.53E-5           0                   0       :
4 3
Iodine - 133                     Ci       9.17E-4         3.64E-4           0                   0 Copper - 64                     Ci         0                 0             0                   0       ;
4 Zine - 65 Ci 0
            - Rubidium - 88                   Ci         0                 0             0                   0 Manganese - 54                   Ci         0                 0             0                   0 Strontium - 92                   Ci         0                 0             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
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)
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 %
Table 2A Page 1 of 1 Liquid Effluents - Summation of All Releases Quarter Quarter Est. Error Units 3
4 Total %
A. Fission & activation products
A. Fission & activation products
: 1. Total release (not including tritium, gases, alpha)     Ci     2.61E-2 2.75E-2   22.9
: 1. Total release (not including tritium, gases, alpha)
: 2. Average diluted concentration during period           pCi/ml   5.99E-11 7.39E-11   22.9
Ci 2.61E-2 2.75E-2 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
: 2. Average diluted concentration during period pCi/ml 5.99E-11 7.39E-11 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
: 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
: 1. Total release                                           Ci     1.88E0 3.37E-1   15.0
: 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
: 2. Average diluted concentration during period           Ci/ml   4.31Es 9.06E-10   15.0 C. Dissolved and entrained gases
: 1. Total release Ci 1.88E0 3.37E-1 15.0
: 1. Total release                                           Ci     9.67E-3 1.49E-4   22.9
: 2. Average diluted concentration during period Ci/ml 4.31Es 9.06E-10 15.0 C. Dissolved and entrained gases
: 2. Average diluted concentration during period         gCi/ml   2.22E-11 4.01E-13   22.9 D. Gross alpha radioactivity
: 1. Total release Ci 9.67E-3 1.49E-4 22.9
: 1. Total release                                           Ci     3.71E-5 6.24E-6   22.9
: 2. Average diluted concentration during period gCi/ml 2.22E-11 4.01E-13 22.9 D. Gross alpha radioactivity
: 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
: 1. Total release Ci 3.71E-5 6.24E-6 22.9
l i
: 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
I 7
7 I
I


i EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)               I l
i EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
Table 2B Page 1 of 1 Liquid Effluents l
Table 2B Page 1 of 1 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quaner Quarter Quarter 3
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
4 3
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
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


    ~
~
EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (07/01/93 - 12/31/93)
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:
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)
        * -Indicates actual total PECO radwaste shipped from Quadrex, after volume reduction, to the burial site.
Container / Type Volume Volume Total Principal (cubic ft.)
        ** - Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site.
(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.
9
9


    '~
ATTACHMENT A j
  . .                                            ATTACHMENT A                                                j SUPPLEMENT INFORMATION                                               !
'~
Facility:     Peach Bottom Units 2 & 3 Licenses:     DPR-44                                                                                   I DPR-56
SUPPLEMENT INFORMATION Facility:
: 1.     Regulatory Limits (Technical Specification Limits)
Peach Bottom Units 2 & 3 Licenses:
A. Noble Gases:                                                                           1
DPR-44 DPR-56 1.
: 1. s500       mrem /Yr           - total body         -
Regulatory Limits (Technical Specification Limits)
                                                                                    " instantaneous" limits 53000     mrem /Yr           - skin                   Tech. Spec. 3.8.C.l.a
A.
: 2. s 10       mrad               - air gamma         - quarterly air dose limits
Noble Gases:
                              $20       mrad               - air beta               Tech. Spec. 3.8.C.2.a
" instantaneous" limits 1.
: 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:
s500 mrem /Yr
: 1. s1500     mrem /Yr           - any organ         - " instantaneous" limits (inhalation path)                           Tech. Spec. 3.8.C.1.b
- total body 53000 mrem /Yr
: 2.     s 15     mrem               - any organ         - quarterly dose limits Tech. Spec. 3.8.C.3.a
- skin Tech. Spec. 3.8.C.l.a 2.
: 3.     s 30     mrem               - any organ         - yearly dose limits Tech. Spec. 3.8.C.3.b C. Liould Effluents
s 10 mrad
: 1. Concentration s 10 CFR 20,                         - " instantaneous" limits Appendix B, Table II, Col. 2                           Tech. Spec. 3.8.B.1       j I
- air gamma
: 2.     s 3.0     mrem               - total body         - quarterly dose limits     j s 10     mrem               - any organ             Tech. Spec. 3.8.B.2.a   j
- quarterly air dose limits
: 3. s6.0     mrem               - total body         - yearly dose limits         )
$20 mrad
s 20     mrem               - any organ         - Tech. Spec. 3.8.B.2.b
- air beta Tech. Spec. 3.8.C.2.a 3.
: 2.     Maximum Permissible Concentrations:
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
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.
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.
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.
10
10


1
1 ATTACHMEEr A (continued) 3.
    ',''                            ATTACHMEEr A (continued) 1
Average Energy:
,"  3. Average Energy:
Not Applicable 4.
Not Applicable
Measurements and Approximations of Total Radioactivity:
: 4. Measurements and Approximations of Total Radioactivity:
i A.
i A. Fission and Activation Gases:                                                         i The method used is the Nuclear Data 6700 Counting System or the Canberra               !
Fission and Activation Gases:
S95/ Dual Host 3400 Counting System                                                   I
The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System
                - Gas Marinelli -                                                                     .
- 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
1 B.
                - Charcoal Cartridge -
Iodme:
C. Particulates:
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
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) -
- Air Particulate Sample, (47mm and 57mm filters) -
D. Liquid Effluents:
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
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
5.
A. Liquid:
Batch Releases; i
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:
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 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
Not applicable 11


      ',4                             A'ITACHMENT A (continued)
',4 A'ITACHMENT A (continued) 6.
: 6. Abnormal Relcasti:                                                                                   )
Abnormal Relcasti:
l A. Liquid:
l A.
: 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.
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 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.
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.
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.
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.
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
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.
12


i-[,')'*                               A'1TACHMENT A (continued)
i-[,')'*
: 6. Abnormal Releases: (Continued)
A'1TACHMENT A (continued) 6.
B. Gaseous:
Abnormal Releases: (Continued)
PBAPS LER 2-93-15 Event Description - While performing the weekly filter change on December 1,                 ,
B.
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 .
Gaseous:
was not obtained for the 7-day period from November 24 through December 1,                   i 1993.
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.
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.                                                                         ,
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.
f a
f a
1 i
1 i
Line 177: Line 388:
13
13


yb            .' $.
y b r.
r.
PEACH BOTTOM ATOMIC POWER STATION-Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 s
PEACH BOTTOM ATOMIC POWER STATION-                                   -
SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 36 JULY 1,1993 THROUGH DECEMBER 31,1993
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
4 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56


                                                                                          .]
.]
  .,                                                                                        i
i TABLE OF CONTENTS i
.'.    ..                                                                                  l l
SECTION PAGE I.
TABLE OF CONTENTS                             l i
Introduction 1
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 -
II.
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)
Tables 1A. Gaseous Effluents - Summation of All Releases 2
Radwaste Manager
1B. Gaseous Effluents for Release Point - Main Stack 3
: 0.         C Chemistry Manager                                       i
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


      ~
~
: 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.
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.
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).
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).
Line 202: Line 421:
1
1


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.
EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) e Table 1A Page 1 of 1 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST.
3         4         ERROR TOTAL %
3 4
ERROR TOTAL %
A. Fission & activation gases
A. Fission & activation gases
: 1. Total release                             Ci     5.25E3   2.08E3         18.8
: 1. Total release Ci 5.25E3 2.08E3 18.8
: 2. Average release rate for period         pCi/sec   6.67E2   2.65E2         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
: 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
: 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
: 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
: 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
: 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)
: 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
: 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
: 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
: 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
: 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) -
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
Table IB Page 1 of 2 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3
Nuclides Released       Units         Quarter           Quarter Quarter           Quarter 3                 4       3                 4
4 3
: 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
4
: 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
: 1. Fission gases Krypton - 85M Ci 1.51E2 7.40E1 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       ;
0 Krypton - 87 Ci 1.85E2 1.25E2 0
l Cesium - 134                 Ci               0             1.47E-5   0                 0 Cesium - 137                 Ci           3.79E-5           3.26E-5     0                 0       ;
0 Krypton - 88 Ci 5.55El 7.49El 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
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 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)
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
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
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 4


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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
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
: 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
4 3
: 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
4
: 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
: 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)
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 .
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
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
6


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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 %
Table 2A Page 1 or 1 Liquid Efnuents - Summation of All Releases Quarter Quarter Est. Error Units 3
A. Fission & activation products                                                                     l
4 Total %
: 1. Total release (not including tritium, gases, alpha)     Ci     2.61E-2 2.75E-2   22.9
A. Fission & activation products
: 2. Average diluted concentration during period           pCi/ml   5.99E-11 7.39E-11   22.9
: 1. Total release (not including tritium, gases, alpha)
: 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       .
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
I
I
: 4. Maximally Exposed Organ Dose TEEN LIVER              Millirem  5.47E-3  9.72E-3  22.9        ,
'i 7
Percent of Technical Specification                      %    5.47E-2  9.72E-2  22.9 B. Tritium
i A
: 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
I
                                                                                                          'i l
7 i
A


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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
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)
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:
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)
        * -Indicates actual total PECO radwaste shipped from Quadrex, after volume reduction, to the burial site.
Container / Type Volume Volume Total Principal (cubic ft.)
        ** -Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site.
(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
4 9


',- l..                                           A'ITACHMENT A SUPPLEMENT INFORMATION
l..
      . Facility:     Peach Bottora Units 2 & 3 Licenses:       DPR-44 DPR-56
A'ITACHMENT A SUPPLEMENT INFORMATION
: 1.     Reculatory Limits (Technical Specification Limits)
. Facility:
A.     Noble Gases:
Peach Bottora Units 2 & 3 Licenses:
: 1. s500       mrem /Yr           - total body         - " instantaneous" limits s3000     mrem /Yr           - skin                 Tech. Spec. 3.8.C.1.a
DPR-44 DPR-56 1.
: 2. s 10       mrad               - air gamma         - quarterly air dose limits s 20       mrad               - air beta             Tech. Spec. 3.8.C.2.a
Reculatory Limits (Technical Specification Limits)
: 3. s 20       mrad               - air gamma         - yearly air dose limits
A.
                              $40       mrad               - air beta             Tech. Spec. 3.8.C.2.b B.     Iodines. Tritium. Particulates with Half Life > 8 days:
Noble Gases:
: 1.     s1500     mrem /Yr           - any organ         - " instantaneous" limits (inhalation path)                           Tech. Spec. 3.8.C.1.b
1.
: 2.     s 15     mrem               - any organ         - quarterly dose limits Tech. Spec. 3.8.C.3.a
s500 mrem /Yr
: 3.     s 30     mrem               - any organ         - yearly dose limits Tech. Spec. 3.8.C.3.b C.     Liquid Effluents
- total body
: 1. Concentration s 10 CFR 20,                         - " instantaneous" limits Appendix B, Table II, Col. 2                           Tech. Spec. 3.8.B.1
- " instantaneous" limits s3000 mrem /Yr
: 2.     s 3.0     mrem               - total body       - quarterly dose limits s 10     mrem               - any organ             Tech. Spec. 3.8.B.2.a
- skin Tech. Spec. 3.8.C.1.a 2.
: 3.     s 6.0     mrem               - total body         - yearly dose limits s 20     mrem               - any organ         - Tech. Spec. 3.8.B.2.b
s 10 mrad
: 2.     Maximum Permiss" .'e Concentrations:
- 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.
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.
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
10


              '.                                                              ATTACHMENT A (continued)
ATTACHMENT A (continued) 3.
: 3. Average Energy:
Average Energy:
Not Applicable
Not Applicable 4.
: 4. Measurements and Anproximations of Total Radioactivity:
Measurements and Anproximations of Total Radioactivity:
A. Fission and Activation Gases:
A.
Fission and Activation Gases:
The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System
The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System
                          - Gas Marinelli -
- Gas Marinelli -
B. Iodine:
B.
Iodine:
The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System
The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System
                          - Charcoal Cartridge -
- Charcoal Cartridge -
C. Particulates:
C.
Particulates:
The method used is the Nuclear Data 6700 Counting System or the Canberra S95/ Dual Host 3400 Counting System
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) -
- Air Particulate Sample, (47mm and 57mm filters) -
D. Liquid Effluents:
D.
l The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli
Liquid Effluents:
: 5. Eatch Releasca:
l The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli 5.
A. Liquid:
Eatch Releasca:
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:
A.
                                                                                                                                                          ]
Liquid:
1 l
DTR 3 OTR 4 Number of batch releases:
Not applicable 11
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 Not applicable l
11


      ',;                              A'ITACHMENT A (continued)
A'ITACHMENT A (continued) 6.
Abnormal Releases:
Abnormal Releases:
6.
A.
A. Liquid:
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
1.
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.
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' 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.
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     ,
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.
and Isotope quantities from this continuous release were added to this Semi-   l Annual Effluent Report for the applicable reporting period.
2.
: 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.
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.
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.
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
12


ATTACHMENT A (continued)
ATTACHMENT A (continued) 6.
,'          6. Abnormal Releases: (Continued)
Abnormal Releases: (Continued)
B. Gaseous:
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.
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.
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
13


\\
PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 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
TABLE OF CONTENTS SECTION PAGE I.
Introduction 1
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 1
l
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.
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
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
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.                                 !
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).
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.
There were two unplanned releases of liquid radioactive material.
Line 361: Line 787:


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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.
Table 1A Page 1 of 1 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST.
3         4         ERROR TOTAL %
3 4
ERROR TOTAL %
A. Fission & activation gases
A. Fission & activation gases
: 1. Total release                             Ci     5.25E3   2.08E3         18.8
: 1. Total release Ci 5.25E3 2.08E3 18.8
: 2. Average release rate for period         pCi/sec   6.67E2   2.65E2         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
: 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
: 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
: 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
: 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
: 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)
: 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
: 2. Average release rate for period pCi/sec 4.43E-4
: 3. Average Gross Alpha Radioactivity         Ci     5.68E-6   2.26E-5       22.9 D. Tritium
: 2. 85E-4 22.9
: 1. Total release                             Ci     8.88E0   4.68E0       23.5
: 3. Average Gross Alpha Radioactivity Ci 5.68E-6 2.26E-5 22.9 D. Tritium
: 2. Average release rate for period         pCi/sec   1.13E0   5.95E-1       23.5 2
: 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
I 1
EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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
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
: 1. Fission gases Krypton - 85M               Ci             1.51E2             7.40El   0                 0 Krypton - 87                 Ci             1.85E2             1.25E2   0                 0 i
4 3
Krypton - 88                 Ci           5.55El             7.49El   0                 0 Xenon - 133                 Ci             1.16E3             4.93E2   0                 0     -
4
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     -
: 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
: 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
Iodine - 131 Ci 1.93E-2 2.24E-3 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     ,
0 lodine - 133 Ci 5.5 SE-2 9.48E-4 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     !
0 Iodine - 135 Ci 1.74E-2 0
Cobalt - S S                 Ci               0                   0     0                 0     l l
0 0
1 3                                               !
Total for Period Ci 9.25E-2 3.19E-2 0
a 1
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 1
3 a
1


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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
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
l 1
4 3
1 I
4 Cobalt - 60 Ci 0
l l
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 1
1 4
1 4
1 i
1 i
                                                                                                        ^
^


EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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
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
: 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
4 3
: 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
4
: 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
: 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)
EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) s Table IC Page 2 of 2 Gaseous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode i
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
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
4 3
l I
4 Zinc - 65 Ci 0
l l
0 0
1 l
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 I
6
6


9 EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93)
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 %
Table 2A Page 1 of 1 Liquid Efnuents - Summation of All Releases Quarter Quarter Est. Error Units 3
4 Total %
A. Fission & activation products
A. Fission & activation products
: 1. Total release (not including tritium, gases, alpha)     Ci     2.61E-2 2.75E-2     22.9
: 1. Total release (not including tritium, gases, alpha)
: 2. Average diluted concentration during period           pCi/ml   5.99E-11 7.39E-11   22.9
Ci 2.61E-2 2.75E-2 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
: 2. Average diluted concentration during period pCi/ml 5.99E-11 7.39E-11 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
: 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
: 1. Total release                                           Ci     1.88E0 3.37E-1     15.0
: 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
: 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 1.88E0 3.37E-1 15.0
: 1. Total release                                           Ci     9.67E-3 1.49E-4   22.9
: 2. Average diluted concentration during period pCi/ml 4.31E-9 9.06E-10 15.0 C. Dissolved and entrained gases
: 2. Average diluted concentration during period             Ci/ml 2.22E-11 4.01E-13     22.9 D. Gross alpha radioactivity
: 1. Total release Ci 9.67E-3 1.49E-4 22.9
: 1. Total release                                           Ci     3.71E-5 6.24 E-6   22.9
: 2. Average diluted concentration during period Ci/ml 2.22E-11 4.01E-13 22.9 D. Gross alpha radioactivity
: 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
: 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)
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
Table 2B Page 1 of 1 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3
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
4 3
          . 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
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)
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, ,
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)
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             ,
. ContainerfType Volume Volume Total Principal (cubic ft.)
l TOTALS 119                                                                               7376.9   6.11E + 04 NOTES:
(cubic ft.)
      * - Indicates actual total PECO radwaste shipped from Quadrex, after volume reduction, to the burial site.
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
l
Dewatered Resin HIC / Type A Cask 132.4 132.4 1.78E +01 Zn-65,Co-60,,
      " - Indicates actual total PECO radwaste shipped from SEG, after volume reduction, to the burial site.
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 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.
9
9


        .                                        ATTACHMENT A
ATTACHMENT A SUPPLEMENT INFORMATION Facility:
  ;*                                    SUPPLEMENT INFORMATION Facility:     Peach Bottom Units 2 & 3 Licenses:     DPR-44 DPR-56
Peach Bottom Units 2 & 3 Licenses:
: 1.     Regulatory Limits (Technical Specification Limits)
DPR-44 DPR-56 1.
A. Noble Gases:
Regulatory Limits (Technical Specification Limits)
: 1. s500       mrem /Yr           - total body         - " instantaneous" limits s 3000     mrem /Yr           - skin                   Tech. Spec. 3.8.C.1.a
A.
: 2. s 10       mrad               - air gamma         - quarterly air dose limits s 20       mrad               - air beta               Tech. Spec. 3.8.C.2.a
Noble Gases:
: 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.
: 1. s1500     mrem /Yr           - any organ         - " instantaneous" limits (inhalation path)                           Tech. Spec. 3.8.C.1.b
s500 mrem /Yr
: 2.     s 15     mrem               - any organ         - quarterly dose limits Tech. Spec. 3.8.C.3.a
- total body
: 3.     5 30     mrem               - any organ         - yearly dose limits Tech. Spec. 3.8.C.3.b     j C. Liauid Effluents
- " instantaneous" limits s 3000 mrem /Yr
: 1. Concentration s10 CFR 20,                           - " instantaneous" limits Appendix B, Table II, Col. 2                           Tech. Spec. 3.8.B.1
- skin Tech. Spec. 3.8.C.1.a 2.
: 2.     s 3.0     mrem               - total body         - quarterly dose limits s 10     mrem               - any organ             Tech. Spec. 3.8.B.2.a     i l
s 10 mrad
: 3. s 6.0     mrem               - total body         - yearly dose limits         l s 20     mrem               - any organ         - Tech. Spec. 3.8.B.2.b     I
- air gamma
: 2.     Maximum Permissible _C'oncentrations:
- quarterly air dose limits s 20 mrad
I 1
- air beta Tech. Spec. 3.8.C.2.a 3.
MPCs are not used to calculate permissible release rates and concentrations for gaseous       {
s 20 mrad
releases.
- air gamma
                                                                                                              )
- yearly air dose limits s 40 mrad
The MPCs specified in 10 CFR 20, Appendix B, Table II, Column 2, for identified               ;
- air beta Tech. Spec. 3.8.C.2.b B.
nuclides are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Technical Specification 3.8.B.1.
Iodines. Tritium. Particulates with Half Life > 8 days 1.
10 l
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 s 20 mrem
- any organ
- Tech. Spec. 3.8.B.2.b 2.
Maximum Permissible _C'oncentrations:
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


  'i,;'-                               ATTACHMENT A (contmued)
'i,;'-
      .a
ATTACHMENT A (contmued)
  ,'    3. Average Energy:
.a 3.
Not Applicable
Average Energy:
: 4. Measurements and Approximations of Total Radioactivity:
Not Applicable 4.
A.     Fission and Activation Gases:
Measurements and Approximations of Total Radioactivity:
l The method used is the Nuclear Data 6700 Counting System or the Canberra l
A.
S95/ Dual Host 3400 Counting System l                  - Gas Marinelli -
Fission and Activation Gases:
:          B.     Joding:
l l
The method used is the Nuclear Data 6700 Counting System or the Canberra     ,
The method used is the Nuclear Data 6700 Counting System or the Canberra l
S95/ Dual Host 3400 Counting System                                           ;
S95/ Dual Host 3400 Counting System
                    - Charcoal Cartridge -                                                       l l
- Gas Marinelli -
C.     Particulates:                                                                 l l
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
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) -
- Air Particulate Sample, (47mm and 57mm filters) -
I D.     Liquid Effluents:
I D.
The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli
Liquid Effluents:
: 5. Itatch Releases:
The method used is the Nuclear Data 6700 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli 5.
A.     liquid:
Itatch Releases:
_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:
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
Not applicable 11 l
                                                                        -          _-        _A
_A


              .                            ATTACHMENT A (continued)                                         l
ATTACHMENT A (continued)
        /                                                                                                     i 1
/
: 6. Abnormal Releases:                                                                           I A. Liquid:
i 1
: 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.
6.
Abnormal Releases:
A.
Liquid:
1.
Event description - On 7/23/93 routine sampling of the high pressure service 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.
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.
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.
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.
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.
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.
l l
i 12 i
l i
12 i
I I
I I


p *,: ' . t ? _
p *,: '. t ? _
ATTACHMENT A (continued).
ATTACHMENT A (continued).
      '4
'4
' '~         6. . Abnormal Releases: (Continued)-
' '~
B. Gaseous:
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.
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 -
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.
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.
l l
l
                                                                                                            )
)
l i
l i
13}}
13
-}}

Latest revision as of 02:20, 15 December 2024

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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Text

,

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 PDR ADOCK 0500 7

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

+

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

- ~

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 re orting period.

p 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.

1 i

i

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

l 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 1.51 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 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 d

1 4

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 i

7 I

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

Table 2B Page 1 of 1 Liquid Effluents 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

~

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.

9

ATTACHMENT A j

'~

SUPPLEMENT INFORMATION Facility:

Peach Bottom Units 2 & 3 Licenses:

DPR-44 DPR-56 1.

Regulatory Limits (Technical Specification Limits)

A.

Noble Gases:

" instantaneous" limits 1.

s500 mrem /Yr

- total body 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

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.

10

1 ATTACHMEEr A (continued) 3.

Average Energy:

Not Applicable 4.

Measurements and Approximations of Total Radioactivity:

i 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 -

1 B.

Iodme:

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 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

',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 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.

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.

f a

1 i

y 1

13

y b r.

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

.]

i TABLE OF CONTENTS i

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

~

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.

1

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) e 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 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 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 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 4

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

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

I

'i 7

i 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 Not applicable l

11

A'ITACHMENT A (continued) 6.

Abnormal Releases:

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' 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 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

\\

PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 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

TABLE OF CONTENTS SECTION PAGE I.

Introduction 1

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 1

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 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 1

1 4

1 i

^

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

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

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 Continuous Mode Batch Mode 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 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.

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 s 20 mrem

- any organ

- Tech. Spec. 3.8.B.2.b 2.

Maximum Permissible _C'oncentrations:

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

'i,;'-

ATTACHMENT A (contmued)

.a 3.

Average Energy:

Not Applicable 4.

Measurements and Approximations of Total Radioactivity:

A.

Fission and Activation Gases:

l l

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

S95/ Dual Host 3400 Counting System

- 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)

/

i 1

6.

Abnormal Releases:

A.

Liquid:

1.

Event description - On 7/23/93 routine sampling of the high pressure service 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.

i 12 i

I I

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.

l

)

l i

13

-

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