ML20107L920
| ML20107L920 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1995 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20107L903 | List: |
| References | |
| NUDOCS 9604300081 | |
| Download: ML20107L920 (21) | |
Text
__-_ - - ___-___ __- ____________________ ___
PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50-278 ANNUAL EFFLUENT RELEASE REPORT NO. 38 JANUARY 1,1995 TIIROUGII DECEMBER 31,1995 l
Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56 9604300081 960422 PDR ADOCK 05000277 PDR R
l' l
j.
TABLE OF CONTENTS SECTION PAGE l
. I.
Introduction 1
II.
Tables I A. Gaseous Effluents - Summation of All Releases 3
IB. Gaseous Effluents for Release Point - Main Stack 5
IC. Gaseous Effluents for Release Point -
Unit 2 and Unit 3 Roof Vents 9
i l
2A. Liquid Effluents - Summation of All Releases 11 2B, Liquid Effluents 13 III.
Classes of Solid Radioactive Waste Shipments 15 IV.
Attachments A.
Supplemental Information 16 l
l Technical Concurrences: (for accuracy of information) d waste Man 6r
~
Chemistry Manager l
1.
INTRODUCTION In accordance with the Unique Reporting Requirements of Technical Specification 6.9.2h(2) applicable during the reporting period, this report summarizes the Effluent Release Data for Peach Bottom Atomic Power Station Units 2 and 3 for the period January 1,1995 through December 31,1995. 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.
The Off-Site Dose Calculation Manual (ODCM) was revised four times during the reporting period. These revisions were:
Revision 6 (issued March 2,1995) 1.
Annotation of a previously incorporated commitment to calculate and report maximum total body and organ doses.
2.
Changes to reflect the current Radiological Environmental Monitoring Program by:
Reducing the number of listed TLD sample stations from 47 to 40.
a.
b.
Replacing the specified air particulate and air iodine sample station 12D with station 22G1 from the LGS REMP.
Revision 7 (issued October 3,1995) 1.
Changes to reflect the installation of new hydrogen analyzers.
2.
Changes to reflect the introduction of new gaseous effluent radiation monitors.
Revision 8 (approved October 23,1995 but delayed pending implementation of Improved Technical Specifications. These changes were incorporated into
. Revision 9.)
Incorporation of the relocated requirements from Technical Specifications consistent with NRC Generic Letter 89-01.
Revision 9 (approved January 3,1996 and issued January 18, 1996) 1.
Changes to reflect the revised implementation schedule for the gaseous effluent radiation monitors upgrade.
2.
Minor non-technical changes to correct two typographical errors on page 26 and a diagram reference on page 30.
A copy of Revision 9 of the ODCM is attached to this report.
1
\\
l The station Process Control Program (PCP) was revised on 12-15-94 with an effcctive date of 1-19-95. The incorporated changes were:
1.
Option to use SEG for dewatering activities, instead of being limited to use of 1
Vectra (previously NuPac).
2.
Distinction between system utilized at PBAPS and LGS regarding the processing of condensate filter /demineralizer waste, i.e. a precoatable and precoatless system, respectively.
3.
Update of procedure sources / references and personnel titles, j
4.
Submittal of NRC Annual Radioactive Effluent Release Report on an annual rather than a semi-annual basis.
l A copy of the revised RW-C-100 Solid Radwaste System Process Control Program (PCP) is attached to this report.
i A review of the Main Stack Gaseous Effluent Monitor calibration data in conjunction with published information on the performance characteristics of these monitors verified that the factor used throughout 1995 to convert monitor net counts per second to gross noble gas activity was unnecessarily conservative.
Accordingly, the 1995 Main Stack noble gas Total Curie and Air Dose values in this report were generated by adjusting the originally determined Main Stack noble gas activity values to reflect the use of a more realistic conversion factor.
2
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table 1 A Page 1 of 2 Gaseous Effluents - Summation of All Releases 1
UNITS QUARTER QUARTER EST.
1 2
ERROR TOTAL %
A. Fission & activation gases 4
- 1. Total release Ci 2.66E3 2.68E3 18.8
- 2. Average release rate for period Ci/sec 3.38E2 3.41E2 18.8
- 3. Gamma Air Dose Millirad 1.29E-1 1.66E-1 18.8 Percent of Technical Specification 1.29E-0 1.66E-0 18.8
- 4. Beta Air Dose Millirad 9.50E-2 1.20E-1 18.8 Percent of Technical Specification 4.75 E-1 6.00E-1 18.8 B. Iodines
- 1. Total iodine-131 Ci 7.40E-3 5.49E-3 22.9
- 2. Average release rate for period Ci/sec 9.41 E-4 6.98E-4 22.9
- 3. Critical Organ dose Millirem 3.30E-2 2.75E-2 22.9 Percent of Technical Specification 2.20E-1 1.83E-1 22.9 C. Pcrticulates i
- 1. Particulates with half-hves greater than 8 days (includes Alpha Ci 1.34E-3 1.61E-3 22.9 and Strontium 89-90)
- 2. Average release rate for period Ci/sec 1.70E-4 2.05E-4 22.9
- 3. Average Gross Alpha Radioactivity Ci 4.83 E-6 2.53E-6 22.9 D. Tritium
- 1. Total release Ci 0
4.10El 23.5
- 2. Average release rate for period Ci/sec 0
5.21E-0 23.5 3
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table 1 A Page 2 of 2 Gaseous Effluents -_ Summation of All Releases UNITS QUARTER QUARTER EST.
3 4
ERROR TOTAL %
A. Fission & activation gases l*
- 1. Total release Ci 2.61E3 9.17E2 18.8-
- 2. Average release rate for period Ci/sec 3.32E2 1.17E2 -
18.8 1
- 3. Gamma Air Dose Millised 1.28E-1 4.51E-2 18.8 Percent of Technical Specification 1.28E-0 4.51E-1 18.8
- 4. Beta Air Dose Millired 9.39E-2 3.45E-2 18.8 l~
- Percent of Technical Specification -
4.70E-1 1.72E-1 18.8 BJ Iodines
- 1. Total iodine-131 Ci 1.02E-2 2.11 E-3 22.9
- 2. Average release rate for period pCi/sec 1.30E-3 2.68E-4 22.9
- 3. Critical Organ dose Millirem 5.08E-2 8.61E-3 22.9 Percent of Technical Specification 3.39E-1 5.74E-2 22.9
)
C. Perticulates
- 1. Particulates with half-lives greater than 8 days (includes Alpha Ci 2.22E-3 1.66E-3 22.9 l
and Strontium 89-90)
- 2. Average release rate for period Ci/sec 2.82E-4
- 2. l lE-4 22.9
- 3. Average Gross Alpha Radioactivity Ci 1.53E-6 2.85E-6 22.9 D.' Tritium
- 1. Total release Ci 4.24El 0
23.5 4
- 2. Average release rate for period pCi/sec 5.40E-0 0
23.5 4
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table IB Page 1 of 4 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1
2 1
2
- 1. Fission gases Krypton - 85M Ci 5.33E2 5.26E2 0
0 Krypton - 87 Ci 3.13El 5.50E0 0
0 Krypton - 88 Ci 4.43E2 4.70E2 0
0 Xenon - 133 Ci 9.48E2 8.04E2 0
0 Xenon - 135 Ci 1.46E2 1.66E2 0
0 Xenon - 135M Ci 3.40El 1.07El 0
0 Xenon - 138 Ci 5.58E1 8.40El 0
0 Unidentified Ci 0
0 0
0 Total for Period Ci 2.19E3 2.07E3 0
0
0 Iodine - 133 Ci 3.63E-3 5.44E-3 0
0 Iodine - 135 Ci 5.44E-3 5.29E-3 0
0 Total for Period Ci 1.25 E-2 1.25E-2 0
0
- 3. P rticulates Strontium - 89 Ci 6.77E-4 6.84E-4 0
0 Strontium - 90 Ci 1.55E-6 5.75E-7 0
0 Strontium - 91 Ci 3.37E-4 1.10E-4 0
0 Cesium - 137 Ci 1.76E-6 0
0 0
Cesium - 138 Ci 2.56E-2 2.55E-2 0
0 Birium - 139 Ci 3.94E-3 2.59E-3 0
0 Barium - 140 Ci 2.06E-4 1.56 E-4 0
0 Lanthanum - 140 Ci 1.57E-4 1.32E-4 0
0 5
,.n._-.7 EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table IB Page 2 of 4 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1
2 1
2 Yttrium - 91M Ci 2.03E-4 1.16E-4 0
0 Iodine - 133 Ci 3.18E-6 0
0 0
Rubidium - 88 Ci 3.42E-3 0
0 0
Total for Period Ci 3.45E-2 2.93E-2 0
0 S
8 4
l l
l EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table IB Page 3 of 4 Gaseous Effluents for Release Point - Main Stack Continuous Mode Batch Mode
. Nuclides Released Units Quarter Quarter Qaarter Quarter 3
4 3
4
- 1. Fissior. gases Krypton - 85M Ci 5.13E2 2.44E2 0
0 Krypton - 87 Ci 2.17El 0
0 0
Krypton - 88 Ci 5.36E2 0
0 0
Xenon - 133 Ci 8.52E2.
3.75E2 0
0 Xenon - 135 Ci 1.45E2 7.86El 0-0 Xenon - 135M Ci 1.96El 0
0 0
Xtnon - 138 Ci 6.18E1 0
0 0
Unidentified Ci 0
4.42El 0
0 Total for Period Ci 2.15E3 7.42E2 0
0
- 2. Iodines lodine - 131 Ci 3.19E-3 1.34E-3 0
0 lodine - 133 Ci 2.62E-2 3.88E-3 0
0 lodine - 135 Ci 4.36E-2 0
0 0
Total for Period Ci 7.30E-2 5.22E-3 0
0
- 3. Particulates Strontium - 89 Ci 6.38E-4 3.03E-4 0
0 Strontium - 90 Ci 4.50E-7 5.58E-7 0
0 Strontium - 91 Ci 4.27E-5 1.69E-4 0
0 Cesium - 137 Ci 2.29E-6 0
0 0
Cesium - 138 Ci 2.32E-2 8.97E-3 0
0 B:rium - 139 Ci 1.98E-3 2.90E-3 0
0 Barium - 140 Ci 5.38E-5 1.50E-4 0
0 Lanthanum - 140 Ci 5.55E-5 1.14E-4 0
0 7
i
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table IB Page 4 of 4 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1
2 1
2 Yttrium - 91M Ci 6.17E-5 1.17E-4 0
0 Iodine - 133 Ci 3.15E-6 0
0 0
Total for Period Ci 2.60E-2 1.27E-2 0
0 6
e 8
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table IC Page 1 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 1
2 1
2
- 1. Fission gases Krypton - 85M Ci 0
0 0
0 Krypton - 87 Ci 0
0 0
0 Krypton - 88 Ci 0
0 0
0 Xenon - 133 Ci 0
0 0
0 Xenon - 135 Ci 0
0 0
0 Xenon - 135M Ci 0
0 0
0 Xenon - 138 Ci 0
0 0
0 Unidentified Ci 4.67E2 6.13E2 0
0 Total for Period Ci 4.67E2 6.13E2 0
0
0 lodhe - 133 Ci 2.59E-2 4.01E-2 0
0 lodine - 135 Ci 0
0 0
0 Total for Period Ci 2.98 E-2 4.39E-2 0
0
- 3. Particulates Strontium - 89 Ci 4.49E-4 7.66E4 0
0 Strontium - 90 Ci 7.52E-7 1.25 E-6 0
0 Strontium - 91 Ci 0
9.76E-5 0
0 Cesium - 138 Ci 1.25E-2 2.61E-2 0
0 Bcrium 139 Ci 1.13 E-2 1.66E-2 0
0 Lanthanum - 140 Ci 6.28E 5 1.83 E-4 0
0 Yitrium - 91M Ci 3.72E-4 7.11 E-4 0
0 lodine - 133 Ci 9.71 E-4 9.58E-4 0
0 Technetium - 99M Ci 7.15E-5 0
0 0
Rubidium - 89 Ci 0
1.96E-3 0
0 TOTAL FOR PERIOD Ci 2.57E-2 4.74E-2 0
0 f
9 1
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table IC Page 2 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3
4 3
4
- l. Fission gases Krypton - 85M Ci 0
0 0
0 Krypton - 87 Ci 0
0 0
0 Krypton - 88 Ci 0
0 0
0 Xenon - 133 Ci 0
0 0
0 Xenon - 135 Ci 0
5.38E0 0
0 Xenon - 135M Ci 0
0 0
0 Xenon - 138 Ci 0
0 0
0 Unidentified Ci 4.62E2 1.70E2 0
0 Total for Period Ci 4.62E2 1.75E2 0
0
0 Iodine - 133 Ci 5.19E-2 6.51 E-3 0
0 kidine - 135 Ci 3.31 E-2 0
0 0
Total for Period Ci 9.20E-2 7.29E-3 0
0
- 3. Particulates Strontium - 89 Ci
'7.94 E-4 7.31 E-5 0
0 Strontium - 90 Ci 5.25 E-6 0
0 0
Strontium - 91 Ci 1.24E-3 0
0 0
Cesium - 137 Ci 0
5.32E-5 0
0 Cesium - 138 Ci 1.65E-2 0
0 0
Barium 139 Ci 1.90E-2 6.03 E-4 0
0 Barium - 140 Ci 7.30E-4 0
0 0
Lanthanum - 140 Ci 9.88E-4 0
0 0
Cobalt - 60 Ci 0
8.88 E-4 0
0 Yttrium - 91M Ci 1.08E-3 0
0 0
Ic:line - 133 Ci 1.60E-3 2.62E-5 0
0 Manganese - 54 Ci 0
1.86E-4 0
0 Manganese - 56 Ci 1.37E-4 0
0 0
lodine - 135 Ci 3.61 E-4 0
0 0
Rubidium - 89 Ci 5.90E-4 0
0 0
TOTAL FOR PERIOD Ci 4.30E-2 1.83E-3 0
0 10
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table 2A Page 1 of 2 Liquid Effluents - Summation of All Releases Quarter Quarter Est. Error Units 1
2 Total %
. A. Fission & activation products
- 1. Total release (not including tritium, gases, alpha)
Ci 2.05 E-4
- 2. l lE-3 22.9
- 2. Average diluted concentration during period pCi/ml 8.07E-Il 4.16E-10 22.9
- 3. Total Body Dose ADULT Millirem 5.14E-5 1.35 E-5 22.9 Percent of Technical Specification 1.71 E-3 4.50E-4 22.9
- 4. Maximally Exposed Organ Dose ADULT LIVER Millirem 8.97E-5 2.03 E-5 22.9 Percent of Technical Specification 8.97E-4 2.03 E-4 22.9 B. Tritium
- 1. Total release Ci 3.29E-1 6.51 E-1 15.0
- 2. Average diluted concentration during period pCi/ml 1.30E-7 1.28E-7 15.0 C. Dissolved and entrained gases
- 1. Total release Ci 1.17E-3 2.20E-3 22.9
- 2. Average diluted concentration during period pCi/ml 4.61E-10 4.34E-10 22.9 D. Gross alpha radioactivity
- 1. Total release Ci 0
0 22.9
- 2. Average diluted concentration during period Ci/ml 0
0 22.9 E. Volume of waste released (prior to dilution) liters 9.29E4 2.35 E5 12.7 F. Volume of dilution water used during period liters 2.54E9 5.07E9 10.9 I1
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table 2A Page 2 of 2 Liquid Effluents - Summation of All Releases Quarter Quarter Est. Error Units 3
4 Total %
_. A. Fission & activation p oducts
- l. Total release (not including tritium, gases, alpha)
Ci 4.03E-3 9.48E-3 22.9
- 2. Average diluted concentration during period Ci/ml 1.36E-11 1.72E-11 22.9
- 3. Total Body Dose ADULT Millirem 1.28E-3 3.40E-3 22.9 Percent of Technical Specification 4.27E-2 1.13 E-1 22.9
- 4. Maximally Exposed Organ Dose TEEN LIVER Millirem 1.95E-3 5.06E-3 22.9 Percent of Technical Specification 1.95 E-2 5.06 E-2 22.9 B. Tritium
- 1. Total release Ci 3.90E-1 1.86El 15.0
- 2. Average diluted concentration during period pCi/ml 1.32E-9 3.38E-8 15.0 C. Dissolved and entrained gases
- 1. Total release Ci 5.39E-4 4.60E-3 22.9
- 2. Average diluted concentration during period yCi/ml 1.82E-12 8.36E-12 22.9 D. Gross alpha radioactivity
- 1. Total release Ci 5.65E-7 1.19E-6 22.9
- 2. Average diluted concentration during period gCi/ml 1.91 E-15 2.16E-15 22.9 E. Volume of waste released (prior to dilution) liters 2.25E5 3.94E6 12.7 F. Volume of dilution water used during period liters 2.96El1 5.50El1 10.9 O
a 12
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95 - 12/31/95)
Table 2B Page 1 of 2 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter I
2 1
2 Strontium - 89 Ci 0
0 7.47E-8 0
Strontium - 90 Ci 9.08E-9 0
0 0
Alpha Ci 0
0 0
0 Tritium Ci 9.39E-4 0
3.28E-1 6.51 E-1 Phosphorus - 32 Ci 0
0 0
0 Iron - 55 Ci 1.10E-6 0
0 0
Xenon - 133 Ci 0
0 1.30E-4 2.63E-4 Xenon - 135 Ci 0
0 1.04 E-3 1.94E-3 Menganese - 54 Ci 2.29E-5 0
0 0
Cesium - 134 Ci 1.05E-6 0
0 0
Cesium - 137 Ci 3.65 E-6 0
3.99E-6 2.16E-6 Zine - 65 Ci 8.33 E-5 0
4.13E-6 3.34E-5 Cobalt - 58 Ci 3.70E-6 0
0 2.53 E-5 Cobalt - 60 Ci 7.91E-5 0
2.04E-6 1.91 E-4 Chromium 51 Ci 0
0 0
1.86E-3 TOTAL FOR PERIOD Ci 1.13E-3 0
3.29E-1 6.56E-1 e
e 13
_______---_.-______-M
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95-12/31/95)
Table 2B Page 2 of 2 Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3
4 3
4 Strontium - 89 Ci 0
0 0
0 Strontium - 90 Ci 2.72E-6 5.74E-6 0
0 Alpha Ci 5.65E-7 1.19E4 0
0 Tritium Ci 2.36E-2 4.97E-2 3.66E-1 1.85El Phosphorus - 32 Ci 0
0 0
0 Iron - 55 Ci 1.47E-4 3.09E-4 0
0 Xenon - 133 Ci 0
0 8.55E-5 1.23 E-3 Xenon - 135 Ci 0
0 4.53E-4 3.36E-3 Manganese - 54 Ci 4.90E-4 1.03 E-3 0
1.49E-6 Cesium - 134 Ci 1.62E-4 3.42E-4 3.52E-6 3.24E-6 Cesium - 137 Ci 4.64E-4 9.78E-4 2.44 E-5 2.61 E-5 Cesium - 138 Ci 1.29E-5 0
0 0
Zine - 65 Ci 9.34E-4 1.97E-3 0
2.20E-6 Cobalt - 58 Ci 1.94 E-5 4.08E-5 0
0 Cobalt - 60 Ci 1.76E-3 3.71 E-3
0 0
7.72E-5 lodine - 132 Ci 6.40E-7 0
0 0
lodine - 133 Ci 7.25 E-7 0
0 0
lodine - 134 Ci 1.80E-6 0
0 0
Barium - 139 Ci 3.79E-6 0
0 0
Rubidium - 89 Ci
- 3. I 1 E-6 0
0 0
Lanthanum - 140 Ci 0
0 0
8.02E d TOTAL FOR PERIOD Ci 2.76E-2 5.81 E-2 3.67E-1 1.85El 14
EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/95-12/31/95)
PEArH BOTTOM UNITS 2 & 3 CLASSES OF SO.
t RADIOA7IVE WASTE SHIPMENTS Total # of Waste Description Individual Total Shipments (source of waste)
Containertrype Volume Volume Total Principal (cubic ft.)
(cubic ft.)
Curie Radionuclides CLASS A 21 Dewatered Resin HIC / Type A Cask 202.1 4244.1 2.16E + 02 Zn-65, Co-60,Cs-137, Mn-54, Ni-63 34 Dewatered Resin IllCfrype A Cask 195.2 6636 8 6.55 E + 02 Zn-65, Co-60,Cs-137, Mn-54, Ni-63 1
Dewatered Resin IIIC/ Type A Cask 178.9 178.9 4.23 + 00 Zn-65, Co-60,Cs-137, Mn-54, Ni-63 1
Dewatered Resin IllC/ Type A Cask 135.8 135.8 5.62E + 00 Zn-65, Co-60,Cs-137, Mn-54, Ni-63 1
DAW / Dewatered lilC/ Type A Cask 202.1 202.1 2.36 E + 00 Co-60, Zn-65, Mn-54, Filters Fe-55, Cs-137 7
DAW / Asbestos /
Metal Box /STC 46.0 2944.0 2.16E + 00 Co-60, Cs-137, Fe-55, Ash / Dewatered Metal Drum /STC 12.1 169.4 Zn-65, Ni-63 Filters 83 DAW (*)
Metal Box /STC variable 1521.0 9.41 E-01 Co-60, Cs-137, Zn-65, Cr-51, Fe-55
(**)
Dewatered Filters (*)
Metal Box /STC variable 83.1 1.96E-01 Zn-65, Co-60,Cs-137, Cr-51,11-3
(**)
Incinerator Ash (*)
Metal Box /STC variable 69.2 6.50E-01 Co-60, Cs-137, Zn-65, Fe45, Ag-110m
(**)
Asbestos (*)
Metal Box /STC variable 100.7 5.70E-03 Co-60, Zn-65, Cr-51, Cs-137, Fe-55 2
Dewatered Resin (*)
lilC/ Type A Cask 195.2 390.4 4.60E + 01 Zn-65, Co-60, Cs-137, Cr-51, Ni-63 CLASS B 2
Dewatered Resin lilC/ Type A Cask 202.1 404.2 1.1 I E + 02 Zn-65, Co-60, Cs-137, Ni-63, Cs-134 3
Dewatered Resin lilC/ Type A Cask 195.2 585.6 1.55E + 02 Zn-65, Co-60, Cs-137, Mn-54, Ni-63 1
Dewatered Resin lilCfrype B Cask 132.4 132.4 3.87E + 02 Zn-65, Co-60, Ni-63, Mn-54, Fe-55 CLASS C None TOTALS 156 17797.7 1.59 E + 03 NOTES:
(
- -indicates actual total PECO radwaste shipped from Scientific Ecology Group (SEG), after volume reduction, to the burial site.
l
- -Shipment total included with DAW from SEG as these shipments contain commingled waste streams.
15
ATTACHMENT A SUPPLEMENT INFORMATION Facility:
Peach Bottom Units 2 & 3 Licenses:
DPR-44 DPR-56
- k. Regulatory Limits (Technical Soccification Limits)
A. Noble Gases:
1.
s500 mrem /Yr
- total body
" instantaneous" limits s3000 mrem /Yr
- skin Tech. Spec. 3.8.C.I.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 5 40 mrad
- air beta Tech. Spec. 3.8.C.2.b B. Iodines. Tritium. Particulates with Half Life > 8 days:
1.
s 1500 mrem /Yr
- any organ
" instantaneous" limits (inhalation path)
Tech. Spec. 3.8.C.l.b 2.
s 15 mrem
- any o'gan 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 Permissible Concentrations:
MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.
The MPCs specified in 10CFR20, 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.I.
16
ATTACHMENT A (continued)
- 3. ' Average Enernv:
Not Applicable
- 4. Measurements and Anproximations of Total Radioactivity:
A. Fission and Activation Gases:
The method used is the Canberra S95/ Dual Host 3400 Counting System
- Gas Marinelli -
B. Iodine:
The method used is the Canberra S95/ Dual Host 3400 Counting System
- Charcoal Cartridge -
C. Particulates:
The method used is the Canberra S95/ Dual Host 3400 Counting System
- Air Particulate Sample, (47mm and 57mm filters) -
D. Liauid Effluents:
The method used is the Canberra S95/ Dual Host 3400 Counting System and the Radwaste Liquid Discharge Pre-Release Method with a liter marinelli.
- 5. Batch Releases:
A. Liquid:
QTR1 QRT 2 QTR 3 QTR 4 Number of batch releases:
9 5
6 64 Total Time for batch releases (minutes):
933 1092 1168 16059 Maximum time period for batch release 310 280 320 330 (minutes):
Average time period for batch release 103.67 218.40 194.67 250.92 (minutes):
Minimum time period for batch release 62 84 60 60 (minutes):
Dilution volume (liters):
2.54E9 5.07E9 3.93E9 5.54E10 B. Gaseous:
Not applicable 17
ATTACHMENT A (Continued)
- 6. Abnormal Releases:
A. Liould:
- 1. Event description - On 3/8/95 the temporary mispositioning of the Unit 2 'D' residual heat removal (RHR) heat exchanger differential pressure transmitter equalization valves resulted in the leakage of approximately 100 gallons of contaminated condensate stay-full or primary coolant water into the 'D' loop of the high pressure service water (HPSW) system. This contaminated water was then released to the discharge canal when the HPSW pumps were run.
It was estimated that the contaminated water released 3 57E-5 millirem total body dose to the discharge canal on 3/8/95. 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 efnuent release. The results were then calculated based on the actual release conditions. The dose contributions and isotope quantities from this continuous release were added to this Annual Effluent Report for the applicable reporting period.
- 2. Event description - On 7/28/95 it was discovered that a contaminated air conditioner condensate drain line had been routed through a clean drain to the river. The drain line was immediately re-routed to Radwaste.
It was estimated that the contaminated water released 5.15E-5 millirem total body dose to the discharge canal from 7/25/95 to 7/28/95. 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 efnuent release. The results were then calculated based on the actual release conditions. The dose contributions and isotope quantities from this continuous release were added to this Annual Effluent Report for the applicable reporting period.
- 3. Event description - On 8/18/95 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 3 'A' residual heat removal (RHR) heat exchanger Goating head gasket into the 'A' loop of the HPSW system. The Coating head flange was seal welded to the tube sheet and leak tested satisfactorily.
It was estimated that the contaminated water released 4.32E-3 millirem total body dose to the discharge canal from 8/18/95 to 12/31/95. This dose contribution was well below the limits specified in Technical Specifications.
Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The results were then calculated based on the actual release conditions. The dose contributions and isotope quantities from this continuous release were added to this Annual Effluent Report for the applicable reporting period.
I8
ATTACHMENT A (Continued)
- 6. Abnormal Releases: (Continued)
B. Gaseous:
None
- 7. Minimum Detectable Concentrationn A. Liquid:
If a radionuclide was not detected, zero activity was reported for that isotope. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required Lower Limits of Detection (LLD) as specified in Technical Specification Table 4.8.1 Radioactive Liquid Waste Sampling and Analysis. In all cases, these LLDs were less than the values required by Technical Specifications.
B. Gaseous:
If a radionuclide was not detected, zero activity was reported for that isotope. A zero activity indicates that no activity was positively detected in any sample when samples were analyzed with
. techniques which achieved the required Lower Limits of Detection (LLD) as specified in Technical Specification Table 4.8.2 Radioactive Gaseous Waste Sampling and Analysis from Main Off-Gas Stack and Reactor Building Vent Exhaust Stack. In all cases, these LLDs were less than the values required by Technical Specifications.
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