ML20067D261

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Semiannual Effluent Release Rept 36 Jul-Dec 1993
ML20067D261
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1993
From: Crosse F, Odell A, Rainey G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-94-14029, NUDOCS 9403080139
Download: ML20067D261 (16)
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  • Gertid R. Rainty Vice President Peach Bottom Atomic Power station JCN 94-14029 - ,

v PECO ENERGY ;gg;gcomm Delta, PA 17314-9739 717 456 7014 February 25,1994 Docket Nos. 50-277 -

'50-278 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Semi-Annual Effluent Release Report No. 36 July 1,1993 through December 31,1993 Peach Bottom Atomic Power Station Unit Nos. 2 and 3 Gentlemen:

Enclosed are two copies of the Semi-Annual Effluent Release Report No. 36, July 1,1993 through December 31,1993 for Peach Bottom Atomic Power Station Unit Nos. 2 and 3.

This report is being submitted in compliance with 10 CFR 50.36a (a) (2) and the Technical Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of Regulatory Guide 10.1.

Sincerely, Yi G. R. Rainey Vice President GRR:aa enclosures 0 D!)0 ?~j cc: R. A. Burricelli, Public Service Electric & Gas W. P. Dornsife, Commonwealth of Pennsylvania W. L Schmidt, USNRC Senior Resident inspector R. l. McLean, State of Maryland T. T. Martin, Administrator, Region I, USNRC H. C. Schwemm, Atlantic Electric C. D. Schaefer, Delmarva Power INPO Records Center

/" ,

9403080139 931231 1 i PDR ADOCK 05000277 i R PDR i

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 TIIROUGII DECEMBER 31,1993 l

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

l TABLE OF CONTENTS SECTION PAGE I. Introduction 1 II. Tables IA. Gasecus 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 III. Classes of Solid Radioactive Waste Shipments 9 IV. Attachments A. Supplemental Information 10 Technical Concurrences: (for accuracy of information)

AdW Radwaste Manager

h. -

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 reporting period.

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

There were two unplanned releases of liquid radioactive material.

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

Tabic 1 A Page 1 of 1

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

3 4 ERROR TOTAL %

A. Fie, ion & activation gases

1. Total release Ci 5.25E3 2.08E3 18.8
2. Average release rate for period Ci/sec 6.67E2 2.65E2 18.8
3. Gamma Air Dose Millirad 1.40E-1 6.63E-2 18.8

- Percent of Technical Specification  % 1.40t0 6.63E-1 18.8

4. Beta Air Dose Millirad 1.39E-1 6.10E-2 18.8 Percent of Technical Specification  % 6.95 E-1 3.05E-1 18.8 B. Iodines
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) i 2. Average releaae 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 27.9 D. Tritium
1. Total release Ci 8.8EE0 4.68E0 23.5
2. Average release rate for period Ci/sec 1.13E0 5.95E-1 23.5 -

t 2

h - _ _ - . _ - - _ _ . _ __-.___________._______.____._.______________________--.___-___.______________m___-_m._______m_--m__________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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

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

1. Fission gaw Krypton - 85M Ci 1.51E2 7.40El 0 0 Krypton - 87 Ci 1.85E2 1.25E2 0 0 Krypten - 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 Unidentified Ci 0 2.51E2 0 0 Total for Period Ci 3.82E3 1.85E3 0 0
2. lodines lodine - 131 Ci 1.93 E-2 2.24E-3 0 0 Iodine - 133 Ci 5.58 E-2 9.48E-4 0 0 hxline - 135 Ci 1.74E-2 0 0 0 l Total for Pericx! Ci 9.25E-2 3.19E-2 0 0 l

l 3. Particu!ates Strontium - 89 Ci 1.35 E-3 1.14E-3 0 0 Stroatium - 90 Ci 1.63E-6 2.32E-6 0 0 Strontium - 91 Ci 5.71E-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 , O Barium - 140 Ci 3.95 E-4 8.44E-4 0 0 Lanthanum - 140 Ci 2.38 E-4 6.31E-4 0 0 Cobalt - 57 Ci 0 0 0 0 Cobah - 58 Ci 0 0 0 0 3

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

Table ID Page 2 of 2 Gaseous Effluents For Release Point - Main Stack Continuous Mode Batch Mode Nuclides Released Units Qwter Q w ter Qwter Qwter 3 4 3 4 Cobalt - 60 Ci 0 5.57E-6 0 0 Zinc - 65 Ci 0 0 0 0 Yttrium - 91M Ci 5.73 E-3 6.05 E-4 0 0 lodine - 133 Ci 9.88 E-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 - 132 Ci 4.27E4 0 0 0 Molybdenum - 99 Ci 9.94 E-7 0 0 0 Technetium - 09m Ci 1.51E-6 0 0 0 TOTAL FOR PERIOD Ci 8.15 E-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 Reicam! Units Quarter Quarter Quarter Quarter 3 4 3 4

1. Fission gases i

Krypton - 85M Ci 0 0 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 2.64El 0 0 0 Xenon - 135 Ci 4.74El 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 2.25 E2 0 0

2. Iodines lodme - 131 Ci 1.13 E-2 2.10E-3 0 0 lodine - 133 Ci 7.14 E-2 1.18E-2 0 0 lodine - 135 Ci 1.15 E-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 1.21 E-3 9.41E-5 0 0 l l

Cesium - 134 Ci 4.61 E-5 0 0 0 j Cesium - 137 Ci 1.86E-4 3.12E-5 0 0 Cesium - 138 Ci 4.09E-2 3.68E-3 0 0 l

Barium - 139 Ci 8.65E 3 1.98E-3 0 0 Buium - 140 Ci 4.96E-4 0 0 0 1.anthanum - 140 Ci 6.09E-4 9.39E-5 0 0 l 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 4 1

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

Table IC Page 2 of 2 f Gaseous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quamr 3 4 3 4 7ine - 65 Ci 0 0 0 0 Yttrium 91M Ci 3.73E-3 6.53 E-5 0 0 lodine - 133 Ci 9.17E-4 3.64E4 0 0 Copper - 64 Ci 0 0 0 0 Rubidium - 88 Ci 0 0 0 0 Mansnae - 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 TOTA 1. FOR PERIOD Ci 5.75E-2 6.45E-3 0 0 l

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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. Finion & activation products _

j 1. Total release (not including tritium, gases, alpha) Ci 2.61 E-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  % l.03E 1 1.81 E-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 4.31 E-9 9.06E-10 15.0 C. Diuolved and entrained gases
1. Total release Ci 9.67E-3 1.49E-4 22.9
2. Average diluted concentration during period pCi/mi 2.22E-11 4.01 E-13 22.9 D. Gross alpha radioactivity
1. Total release Ci 3.71 E-5 6.24E-6 22.9
2. Average diluted concentration during period pCi/ml 8.51E-14 1.68E-14 22.9 E. Volume of waste released (prior to dilution) liters 9.61 E5 1.73E5 12.7 F. Volume of dilution water used during period liters 4.36E l l 3.72E11 10.9 e

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EFFLUENT & WASTE DISPOS AL SEMI-ANNUAL REPORT (7/01/93 - 12/31/93) l Table 2B Page 1 of I Liquid Effluents Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 Strontium - 89 Ci 9. I B E-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 4.51 E-2 4.99E-2 1.83E0 2.87E-1 Phosphorus - 32 Ci 6.19E-6 6.25 E-6 1.64 E-4 1.95E-5 Iron - 55 Ci 3.51 E-4 3.4 8E-4 5.53E-4 6.66E-5 Xenon - 131M Ci 0 0 0 0 Xenon - 133 Ci 0 0 3.41 E-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 l 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 1.71 E-5 1.20E-5 l

Cesium - 138 Ci 0 0 0 0 Zine - 65 Ci 8.88E-3 9.75 E-3 0 0 l Sodium - 24 Ci 0 0 0 0 Cobalt - 58 Ci 9. I BE-4 9.80E-4 0 0 Cobalt - 60 Ci 1.04E-2 1.12E-2 1.82E-5 2.82E-6 Chromium - 51 C 5.23E 4 5.07E-4 0 0 TOTAL FOR PERIOD Ci 7.03 E-2 7.73 E-2 1.84E0 2.87E-1 (ABOVE) l 8

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

PEACII BOTTOM UNITS 2 & 3 JULY 1,1993 TO DECEMBER 31,1993 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS 1

Total # of Waste Description Individual Total Shipments (source of waste) Containerrrype Volume Volume Total Principal (cubic ft.) (cubic ft.) Curie Radionuclides Class A 19 Dewatered Resin lilC/ Type A Ca.sk 202.1 3839.9 4.30E + 02 Zn45,Co40, Cs-137, Cs-134, Cr-51 1 Dewatered Resin IllC/ 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 Co40,Zn45, Metal Box /STC Fe 55, Cs-137, Mn-54 71 DAW Metal Drum /STC, variable (") 856.3 1.00E + 00 Co40, Zn45, Metal Box /STC Fe-55, Cs-137, Mn-54 1 DAW lilCfrype A Cask 38.3 114.9 3.37E + 00 Co-60, Fe-55, Zn 65, Ni-63 1 DAW lilCfrype A Cask 205.8 205.8 1.41E + 00 Co40, Cs-137, Zn45, Fe-55, Mn-54 CLASS B 8 Dewatered Reain IllC/ Type A Cask 202.1 1616.8 3.06E + 02 Zn-65, Cs-137, Co40, Cs-134, Fe-55 2 Dewatered Filters IIICffype A Cask 38.3 229.8 3.20E4 01 Co40, Fe-55, Zn-65, Ni43 CLASS C 3 Irradiated li' Ware Steel Liner / 57.8 173.4 6.03 E + 04 Fe-55, Co40, Type B Cask Mn 54, Ni43, Cr-51 TOTALS 119 7376.9 6. l l E + N NOTES:

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

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

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

1. Ilegulatory Limits (TechnicaLSpecification Limits)

A. Hoble Gasen

1. s500 mrem /Yr - total body -

" instantaneous" limits

$3000 mrem /Yr - skin Tech. Spec. 3.8.C.1.a

2. $ 10 mrad - air gamma - quarterly air dose limits s 20 mrad - air beta Tech. Spec. 3.8.C.2.a l
3. s 20 mrad - air gamma - yearly air dose limits s 40 mrad - air beta Tech. Spec. 3.8.C.2.b B. lodines, Tritium. Particulates with Half Life > 8 dayE
1. s;1500 mrem /Yr - any organ - " instantaneous" limits (inhalation path) Tech. Spec. 3.8.C.l .b
2. $; 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.ifflucats I
1. Concentration s 10 CFR 20, - " instantaneous" limits Appendix B, Table 11, 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. Maxi)DuHLEcDDissible ConcenlIatiQnn MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.

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

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A'ITACHMENT A (continued)

3. ArcragelacIgy:

Not Applicable

4. Measurements and Approximations of Total Radioactivity:

A. Fission and_ Activation Gases:

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

- Gas Marinelli -

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

- Charcoal Cartridge -

C. DIliculaics:

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

5. LlaldLEclcalcS:

A. Liquid:

QTR_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. 031ccus:

Not applicable 11

ATTACHMENT A (continucd)

6. Abnormal Releases:

A. Liqitid:

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 Reicase - 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.

-1

2. Event description - On 11/10/93 routine sampling of the high pressure service water (HPSW) effluent to the discharge canal detected low level ,

l radioactive contamination. Subsequent investigation determined that a trace l amount of condensate stay full or primary coolant water was leaking past the H 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, l

it was estimated that the contaminated water released 6.41E-4 millirem total i 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 Report for the applicable reporting period.

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12 L

L.. .

+ . .

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.

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