ML20217M797

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Radioactive Effluent Release Rept 40,970101-1231, for Peach Bottom Atomic Power Station Units 1 & 2
ML20217M797
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1997
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20217M791 List:
References
40, NUDOCS 9805050137
Download: ML20217M797 (20)
v • d • e


Text

.

PEACH BOTTOM ATOMIC POWER STATION .

~ '

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

RADIOACTIVE EFFLUENT RELEASE REPORT NO. 40 JANUARY 1,1997 TIIROUGH DECEMBER 31,1997 F

Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR-44 and DPR-56 9805050137 900420 PDR ADOCK 05000277 R PDR

TABLE OF CONTENTS SECTION PAGE I. Introduction 1

. II. Tables 1A. Gaseous Effluents - Summation of All Releases 3 4

1B. Gaseous Effluents for Release Point - Main Stack 5 1C. Gaseous Effluents for Release Point -

j Unit 2, Unit 3 Roof Vents and Aux Boiler Stacks 7 2A. Liquid Effluents - Summation of All Releases 9 2B. Liquid Effluents 11 III. Classes of Solid Radioactive Waste Shipments 13 IV. Attachments A. Supplemental Information 14 Technical Concurrences: (for accuracy ofinformation) p -

, 1- in; Y~

16 Mana(er Chemistry Manager I

i

1. INTRODUCTION In accordance with the Reporting Requirements of Technical Specification 5.6.3 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, 1997 through December 31,1997. The notations E and E- are used to denote positive and negative exponents to the base 10, respectively.

The relea:e of radioactive materials during the reporting period was within the Offsite Dose Calculation Manual Specification limits.

The Offsite Dose Calculation Manual (ODCM) was revised during the reporting -

period. ODCM Revision 10 issued January 30,1997 included the following changes:

1. Incineration of contaminated waste oilin the Auxiliary Boilers.
a. ODCMS Figure 3.8.A.1 : Added Auxiliary Boilers as a release point.
b. ODCMS Table 4.8.C.1 : Added Auxiliary Boilers waste oil sampling and analysis requirements.
c. ODCMS 3.8.C.7,4.8.C.7.1 and 2 : New sections to detail control's for waste oil burning.
d. ODCM IV.F.1 and 2 : New sections to define release calculations for waste oil burning.
2. Incorporate REMP ((Radiological Environmental Monitoring Program) changes.

h a. ODCM Table VII.A-1 : Replaced Farm O with Farm R. The annual land use census identified this new farm (R) as yielding a calculated dose commitment greater than the farm (O) being replaced.

b. ODCM Table IVV.A-1 : Changed the 22G1 air particulate / iodine

_.. sampling station designation to 5H2. This station is also used for the Limerick REMP. Changing the PB station designation did not change the physical location.

e

c. ODCM IV.C : New D/Q (annual average relative deposition) value to reflect Farm R as the critical pathway.

d.- ODCM Figures VII.A.1, VII.A.2, and Vil.A.3 : Updated maps to reflect the REMP changes.

e. ODCMS Table 4.8.E.2 : Lower limit of detection (LLD) values replaced minimum detectable level (MDL) values.

1

f. ODCMS 3.10.1.d : Corrected Table reference.
g. ODCMS Bases B 3.8 Radiological Environmental Monitoring: Corrected Table reference and changed MDL to LLD. .
3. Revised 10 CFR 20.
a. ODCM III.A : Specified liquid effluent concentration values and limits by referencing the Table 2 values of revised 10 CFR 20 in place of the Table II values of the previous revision of 10 CFR 20.
b. ODCMS 3.8.B.1 : Defined liquid radwaste effluent concentration limits in terms of the revised 10 CFR 20 values specified in Technical

. Specification 5.5.4.b.

c. ODCMS Bases B 3.8 : Referenced the appropriate sections of Revised 10 CFR 20.
4. Corrected report references.
a. ODCMS Table 4.8.B.1 note (d) : Changed " Annual Effluent Report: to

" Annual Radioactive Effluent Release Report".

b. ODCMS 3.8.E.1 Required Compensatory Measure D.1 : Changed

" Annual Radiological Operating Report" to " Annual Radiological Environmental Operating Report".

The station Process Control Program (PCP) was not revised during the reporting period.

'Ihe noble gas Total Curie and Air Dose values in this report were generated by using

- baseline isotopic noble gas grab sample data in conjunction with the continuous noble gas effluent monitor information.

There were three unplanned releases ofliquid radioactive material.

s There were three abnormal gaseous radioactive material release events.

2 l

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

Table 1A Page 1 of 2 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST. ERROR 1 2 TOTAL %

A. Fission & activation gases

1. Total release Ci 1.19E2 1.04E2 18.8
2. Average release rate for period Ci/sec 1.51El 1.32E1 18.8
3. Gamma Air Dose Millirad 2.31E-2 2.14E-2 18.8 Percent of Technical Specification  % 2.31E-1 2.14E-1 18.8

- 4. Beta Air Dose Millirad 1.61E-2 1.49E-2 18.8 Percent of Technical Specification  % 8.05E-2 7.45E-2 18.8 B. Todines

1. Totaliodine-131 Ci 1.63E-3 2.14E-3 22.9
2. Average release rate for period Ci/see 2.07E-4 2.72E 4 22.9
3. Critical Organ dose Milbrem 1.19E-2 1.59E-2 22.9 Percent of Techmcal Specification  % 7.93E-2 1.06E 1 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 4.27E-4 4.16E 4 22.9 and Strontium 89-90)
3. Average release rate for period uCi/sec 5.43E-5 5.29E-5 22.9
3. Average Gross Alpha Radioactivity Ci 4.99E-6 3.21E-6 22.9 D. Tritium
1. Total release Ci 0 0 23.5

, 2. Average release rate for period Ci/sec 0 0 23.5 3

)

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97) l Table 1A Page 2 of 2 Gaseous Effluents - Summation of All Releases UNITS QUARTER QUARTER EST. ERROR 3 4 TOTAL %

A. Fission & activation gases

1. Total release Ci 7.57El 2.12E2 18.8
2. Average release rate for period Ci/sec 9.63E0 2.50E1 18.8
3. Gamma Air Dose Millirad 1.49E-2 4.56E-2 18.8 Percent of Technical Specification  % 1.49E-1 4.56E-1 18.8
4. Beta Air Dose Millirad 1.04E-2 3.17E-2 18.8 Percent of Technical Specification  % 5.20E-2 1.59E-1 18.8 B. Iodines
1. Totaliodine-131 Ci 1.79E-3 1.17E-3 22.9
2. Average release rate for period Ci/sec 2.28E-4 1.38E-4 22.9
3. Critical Organ dose Millirem 1.33E-2 7.53E-3 22.9 Percent of Technical Specificatica  % 8.87E-2 5.02E-2 22.9 C. Particulates

)'

1. Particulates with half-lives

- greater than 8 days (includes Alpha Ci 3.76E-4 1.50E-4 22.9 and Strontium 89-90)

2. Average release rate for period Ci/sec 4.78E-5 1.77E-5 22.9
3. Average Gross Alpha Radioactivity Ci 4.10E-6 6.20E-6 22.9 D. Tritium
1. Total release Ci 0 4.66El 23.5 l

, 2. Average release rate for period uCi/sec 0 5.50E0 23.5 1 4

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

Table IB Page 1 of 2 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 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 1.09El 3.44E0 0 0 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 C Unidentified Ci 1.94E1 1.89El 0 0 Total for Period Ci 3.03E1 2.23El 0 0
2. Iodines Iodine - 131 Ci 4.83E-4 5.66E-4 0 0 lodine - 133 Ci 1.60E-3 1.97E-3 0 0 Iodine - 135 Ci 0 9.16E-4 0 0 Total for Period Ci 2.08E-3 3.45E-3 0 0
3. Particulates Strontium - 89 Ci 1.99E-4 1.87E-4 0 0 Strontium - 90 Ci 3.83E-7 4.17E-7 0 0

. Barium - 140 Ci 1.03E-4 7.37E-5 0 0 TOTAL FOR PERIOD Ci 3.02E-4 2.61E-4 0 0 5

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

Table IB' Page 2 of 2 Gaseous Effluents for Release Point - Main Stack Contmuous Mode Batch Mode .

Nachdes 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 0 0 0 0 Xenon - 135 Ci 6.88E0 0 0 0 Xenon - 135M- Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 0 Unidentified Ci 1.17El 3.65El 0 0

. Total for Period Ci 1.86El 3.65El 0 0

2. Iodines lodine - 131 - Ci 4.35E-4 6.23E-4 '. 0 0 Iodine - 133 Ci 1.77E-3 8.81E-4 0 0 lodine - 135. - Ci 8.95E-4 0 0 0 Total for Period Ci 3.10E-3 1.50E-3 0 0
3. Partaculates Strontium - 89 Ci 1.87E-4 9.46E-5 0 0

. Strontium - 90 Ci 2.90E-7 2.38E-7 0 0

. Barium - 140 Ci 3.67E-5 2.29E-5 0 0 TOTAL FOR PERIOD Ci - 2.24E 1.18E-4 0 0 I

6 4

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1 EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

Table'1C Page 1 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents & Aux Boiler Stacks ca=*i==an= Mode Batch Mode .

, Nuclides Pais Units Quarter Quarter Quarter Quarter 1 2 1 2

1. Fission gases Krypton - 85M Ci- 'O O O O Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci' O. 0 0 0 Xenon - 135 Ci 0 0 0 0' Xenon - 135M Ci 0 0- 0 0

. Xenon - 138 Ci 0 0 0 0 Unid==tified - Ci 8.87El 8.20E1 0 0 Total for Period Ci 8.87El 8.20E1 0 0

2. Iodines Iodine - 131 Ci 1.15E-3 : 1.57E-3 0 0 Iodine - 133 Ci 7.21E-3 1.23E-2 0 0

- Iodine - 135 Ci -0 0 0 0 Total for Period Ci 8.36E-3 1.39E-2 0 0

3. Particulates

- Strontium - 89 Ci 1.20E-4 1.46E-4 0 0 Strontium - 90 Ci 3.60E-7 7.09E-7 0 0

. Cesium - 137 Ci 0 0 0 2.30E-6 Cobalt - 60 Ci 0 0 0 5.60E-6 TOTAL FOR PERIOD Ci 1.20E-4 1.47E-4 0 7.90E-6 7

EFFLUENT & WASTE DT.SPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

Table IC Page 2 of 2 Gaseous Effluents for Release Point - Unit 2 & Unit 3 Roof Vents & Aux Boiler Stacks 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 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 5.71El 1.75E2 0 0 Total for Period Ci 5.71El 1.75E2 0 0
2. Iodines Iodine - 131 Ci 1.35E-3 5.47E 4 0 0 lodine - 133 Ci 1.26E-2 2.46E-3 0 0 Iodine - 135 Ci 0 0 0 0 Total for Period Ci 1.40E-2 3.01E-3 0 0
3. Particulates Strontium - 89 Ci 1.47E-4 2.55E-5 0 0 Strontium - 90 Ci 5.80E-7 0 0 0 TOTAL FOR PERIOD Ci 1.48E-4 2.55E-5 0 0 O

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORY (1/01/97 - 12/31/97)

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 1.86E-3 1.25E-3 22.9
2. Average diluted concentration during period uCi/ml 5.03E-12 2.01E-12 22.9
3. Total Body Dose Millirem 3.36E-4 2.43E-4 22.9 F

Percent of Technical Specification  % 1.12E-2 8.10E-3 22.9

4. Maximally Exposed Organ Dose Millirem 6.37E-4 3.74E-4 22.9 Percent of Technical Specification  % 6.37E-3 3.74E-3 22.9 B. Tritium
1. Total release Ci 4.77E0 2.27El 15.0
2. Average diluted concentration during period Ci/ml 1.29E-8 3.65E-8 15.0 C. Dissolved and entrained gases
1. Total release Ci 1.19N3 7.20E-3 22.9
2. Average diluted concentation during period uCi/ml 3.22E-12 1.16E-11 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 7.40E5 2.10E6 12.7 F. Volume of dilution water used during period liters 3.70E11 6.22E11 10.9 e

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

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

A. Fission & activation products

1. Total release (not including tr: tium, gases, alpha) Ci 4.07E-4 4.56E-3 22.9
2. Average diluted concentration during period pCi/ml 2.66E-12 1.46E-11 22.9
3. Total Body Dose Millirem 2.82E-4 1.05E-3 22.9 Percent of Technical Specification W 9.40E-3 3.50E-2 22.9
4. Maximally Exposed Organ Dose Millirem 3.11E-4 1.56E-3 22.9 Percent of Technical Specification  % 3.11E-3 1.56E-2 22.9 i B. Tritium
1. Totalrelease Ci 2.94E1 3.07El 15.0
2. Average diluted concentration during period Ci/ml 1.92E-7 9.81E-8 15.0 C. Dissolved and entrained gases
1. Totalrelease Ci 3.48E-3 1.00E-3 22.9
2. Average diluted concentration during period uCi/ml 2.27E-11 3.19E-11 22.9 D. Gross alpha radioactivity
1. Total release Ci 0 0 22.9
2. Average diluted concentration during period pCi/ml 0 0 22.9 E. V:lume of waste released (prior to dilution) liters 2.54E6 3.91E6 12.7 F. Volume of dilution water used during period l liters 1.53E11 3.13E11 10.9 e

e I

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4 EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97 - 12/31/97)

Table 2B Page 1 of 2 Liquid Effluents Continuous Mode Batch Mode

} Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 Strontium - 89 Ci 0 0. 0 0 Strontium - 90 Ci 0 0 0 0 Alpha Ci -0 0 0 0 q Tritium Ci 2.72E-2 2.50E-2 4.74 2.27El Phosphoms - 32 Ci 0 0 0 0 Iron - 55 Ci 1.38E-4 1.79E-5 0 0 Xenon - 133 Ci 0 0 1.97E-4 1.69E-3 Xenon - 135 Ci 0 0 9.89E-4 5.51E-3 Manganese - 54 Ci 3.16E-4 1.88E-4 0 1.67E-6 Cesium - 134 Ci 0 0 0 0 Cesium - 137 Ci - 1.98E-5 1.65E-5 5.95E-6 1.47E-5 Zinc - 65 Ci 9.59E-4 6.19E-4 0 5.01E-5 Cobalt - 58 Ci 2.51E-5 9.57E4 0 0 Cobalt - 60 Ci 3.94E-4 2.%E-4 6.35E-6 3.97E TOTAL FOR PERIOD Ci 2.90E-2 2.62E-2 4.74E0 2.27E + 1 o

.g I 11

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97-12/31/97)

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 1.50E-12 0 0 Strontium - 90 Ci 0 2.16E-13 0 0 Alpha Ci 0 0 0 0 Tritium Ci 9.82E-3 2.75E-2 2.94E1 3.07El Phosphorus - 32 Ci 6.75E-8 1.32E-11 0 4.06E-4 Iron - 55 Ci 4.94E-5 6.73E-5 0 (r

.n-- w Xenon - 133 Ci 0 0 1.34E-3 i S5E-4 Xenon - 135 Ci 0 0 2.14E-3 7.17E-4 Meganese - 54 Ci 5.01E-5 8.78E-5 2.65E-5 1.22E-4 Cesium - 134 Ci 0 2.57E-10 0 0 Cesium - 137 Ci 4.19E-6 1.05E-5 6.94E-6 3.58E-5 Zine - 65 Ci 1.13E-4 2.44E-4 8.89E4 1.86E-3 Cobalt - 58 Ci 0 3.45E-10 0 1.30E-5 Cobalt - 60 Ci B.60E-5 2.06E-4 5.81E-5 1.50E-3 Iron-59 Ci 0 5.28E-10 0 0 Barium-140 Ci 0 0 3.74E-6 0 Iodine - 131 Ci 0 3.01E-10 0 0 Iodine - 133 Ci 0 1.01E-9 0 0 0 TOTAL FOR PERIOD Ci 1.01E-2 2.81E-2 2.94E1 3.07El J

)

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EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/97-12/31/97)

PEACH BOTTOM UNITS 2 & 3 CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS Total # of Waste Description Container / Type Individual Total Total Principal Shipments (source of waste) Volume Volume Curie Radionuclides (cubic ft) (cubic ft)

CLASS A 5 Dewatered Rosin HIC / Type A Cask 195.2 976.0 1.16E+02 Zn-65, Co40, Mn-54, Cs-137, Ni-63 1 DAW HIC / Type A Cask 202.1 202.1 3.45E+00 Co40, Co-144, Zn-65, Dewatered Filters l Fe-55, Mn-54

_ Calib. Sources l V

5 Solidified Rosin (1) HIC / Type A Cask variable 33.4 3.55E+01 Co40, Mn-54, Zn-65, Ni-63, Cs-137 10 DAW (2) Metal Box /STC variable 111.3 1.45E-02 Co40, Cs-137, Zn45, Mn-54, Fe-55 49 DAW (3) Metal Box /STC variable 725.2 5.51E-01 Co40, Cs-137, Zn-65, Mn-54, Fe-55

(*) Dewatered Metal Box /STC variable 126.6 1.51E-01 Zn45, Co40, Cs-137, Fitters (3) Fe-55, Ni-63

(*) Incinerator Metal Box /STC variable 24.6 1.34E-01 Co-60, Cs-137, Ash (3) Ce-144, Mn-54, Zn-65

(*) Asbestos (3) Metal Box /STC variable 35.4 6.53E-03 Co-60, Zn-65, Cs-137, Mn-54, Fe-59 CLASS B 1 Dewatered Resin HIC / Type A Cask 195.2 195.2 4.96E+01 Co40, Cs-137, Zn-65, Ni43, Ce-144 1 DAW HIC / Type A Cask 202.1 202.1 3.70E+00 Co40, Zn-65, Mn-54, Dewatered Filters Cs-137, Fe-55 ,

_ CLASS C 1 Dewatered Resin HIC / Type B Cask 135.8 135.8 1.04 E+03 Zn-65, Co40, Mn-54, Cr-51, Ag-110m TOTALS 73 2767.7 1.25E+03 NOTES:

(1)-Indicates actual total PECO weste shipped from Molten Metal Technologies, Inc to burial after processing.

(2)-Indicates actual total PECO waste shipped from Manufacturing Sciences Corp. to burial after processing.

(3)-Indicates actual total PECO waste shipped from GTS Duratek (formerly SEG) to burial after processing.

(*)- Shipment total included with DAW from GTS Duratek as these shipments contained comingled waste streams.

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

l. Regulatorv Limits (Offsite Dose Calculation Manual Specification Limits)

A. Noble Gases:

1. s500 mrem /Yr - total body -

" instantaneous" limits s3000 mrem /Yr - skin ODCMS 3.8.C.l.a y 2. s10 mrad - air gamma -

quarterly air dose limits s20 mrad - air beta ODCMS 3.8.C.2.a and b

3. s20 mrad - air gamma -

yearly air dose limits s40 mrad - air beta ODCMS 3.8.C.2.c and d B. Iodines. Tritium. Particulates with Half Life > 8 days:

1. s1500 mrem /Yr - any organ -

" instantaneous" limits (inhalation path) ODCMS 3.8.C.I.b

2. sl5 mrem - any organ -

quarterly dose limits ODCMS 3.8.C.3.a

3. s30 mrem - any organ -

yearly dose limits ODCMS 3.8.C.3.b C. Liquid Effluents

1. Concentration s 10 times 10 CFR 20, -

" instantaneous" limits Appendix B, Table 2, Col. 2 ODCMS 3.8.B.1

2. s3.0 mrem - total body -

quarterly dose limits s10 mrem - any organ ODCMS 3.8.B.2.a Q 3. s6.0 mrem - total body -

yearly dose limits s20 mrem - any organ -

ODCMS 3.8.B.2.b

2. Maximum Permissible Concentrations:

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

'Ihe Effluent Concentrations specified in 10 CFR 20, Appendix F, Table 2, Column 2 times 10, for identified nuclides, are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Offsite Dose Calculation Manual Specification 3.8.B.I.

14

ATTACHMENT A (continued)

3. 'Averare Energy:

Not Applicable ,

4. - Measurements and Anoroximations of Total Radioactivity:

A. Fission and Activation Gases:

The method used is the Canberra S95/ Dual Host 3400 Counting System

- Gas Marinelli -

B. Iodine: ,

Y The method used is the Canberra S95/ Dual Host 3400 Counting System

- Charcoal Cartridge -

C. Particulates:

1 The method used is the Canberra S95/ Dual Host 3400 Counting System

- Air Particulate Sample, (37mm and 47mm) -

D. Liould Effluents:

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

5. Batch Releases: i A. Liquid:

l QTR1 QRT 2 QTR 3 QTR4 Number of batch releases: 15 38 39 71 Total Time for batch releases (minutes) 2970 7534 8865 15316 Maximum time period for batch release 280 274 345 325 (minutes):

Average time period for batch release 198.00 198.26 227.31 215.72 (minutes):

Minimum time period for batch release 68 15 65 37 (minutes):

Dilution volume (liters): 9.31E9 3.47E10 4.47E10 5.30E10 15

+

A'ITACHMENT A (Continued)

B. Gaseous:

QTR1 QRT 2 QTR 3 QTR 4 Number of batch releases: 0 1 0 0 Total Time for batch releases (minutes)- 0 1.73E4 0 0 Maximum time period for batch release 0 1.73E4 0 0

, (minutes):

Average time period for batch release 0 1.73E4 0 0

.g (minutes):

Minimum time period for batch release 0 1.73E4 0 0 (minutes):

6. Abnormal Releases:

A. Iinuid:

1. Event description - This event was a continuation of the high pressure service water (HPSW) event discovered on 10/7s96 through routine sampling of the effluent to the discharge canal.

The event was terminated on 'l/21/97. Investigation of this event 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 floating head flange was seal welded to the tube sheet and leak tested satisfactorily.

It was estimated that the contaminated water released 1.09E-4 mrem total body dose to the discharge canal from 1/1/97 to 7/21/97. This dose was well below the limits specified in the

-ODCM.

Analysis of Release - A representative sample was analyzed for all the parameters of a

.)

radioactive effluent release. The dose contributions and isotope quantities from this continuous release were added to this Radioactive Effluent Release Report for the applicable reporting periods.

2. Event Description - On 11/1/97 routine sampling of the HPSW cffluent 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 through a Unit 2 "A" RHR heat exchanger tube.

It was estimated that the contaminated water released 6.52E-5 mrem total body dose to the

- discharge canal from 11/1/97 to 12/31/97. This dose was well below the limits specified in the ODCM.

16

ATTACHMENT A (Continued)

Analysis of Release - A representative sample was analyzed for all the parameters of a radioactive effluent release. The dose contributions and isotope quantities from this continuous release were added to this Radioactive Effluent Release Report for the applicable 1eporting periods.

3. Event Description - On 11/10/97 approximately 6 ml of Unit 3 reactor water was poured down a non-radioactive sink. The sink drains to the sewage plant which discharges to the discharge canal. Investigation determined that the release was due to personnel error.

It was estimated that the contaminated water released 2.24E-9 mrem total body dose to the discharge canal on 11/10/97. This dose was well below the limits specified in the ODCM.

g Analysis of Release - The representative sample obtained was analyzed for all the parameters of a radioactive effluent release. The dose contributions and isotope quantities from this continuous release were added to this Rsdioactive Effluent Release Report for the applicable reporting period.

4. Event Description - On 5/26/97 a floor drain sample tank was released to the discharge canal without an activity analysis as required by ODCMS Table 4.8.B.1. The tank was released with a quantitative analysis of the identifiable gamma emitters that did not meet the minimum detectable level requirements.

The cause of the event was determined to be lack of attention to detail. Software changes were made to add an additional barrier to prevent future occurrences.

Analysis of Release - After the tank was released, a sample of the tank was analyzed with the required detection levels. This analysis verified that no release limits were exceeded.

B. Gaseous:

1. Event Description - The Main Stack flow monitor was declared inoperable on 1/12/97 due to erratic response. Investigation verified that the low ambient air temperatures were causing

, moisturc to freeze in the pitot tubes.

Flows were estimated at least once every four hours in accordance with ODCMS 3.8.C.4.C.

O The Main Stack flow monitor was declared operable on 4/21/97 when a new type flow monitor was put in service. The new flow monitors are thermal mass flow sensors that are not susceptible to low ambient temperatures.

2. Event Description - On 8/13/97 a possible non-compliance with the methodology described in the ODCM was discovered. When the Isotopic Analysis Method was used for determining dose rate and dose from iodine -131, iodine-133, tritium and radioactive materials in particulate form with half-lives greater than eight days the dose contribution for strontium-89 and strontium-90 was not being included in the dose calculations.

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ATTACHMENT A (Continued)

The iodine and particulate releases were examined for the last three years to determine if the reported doses were accurate. In all cases the reported doses were limiting. The Iodine-131 Method was used for all releases. Procedures will be revised to include strontium-89 and '

strontium-90 in dose rate and dose calculations.

3. Event Description - During 1997 several potential unmonitored release paths were discovered in the turbine building and off-gas building. These release points were due, in part, to the aging of caulking at concrete-to-metal interfaces.

As each release point was discovered, the direction of the air flow as determined. If flow was out of the structure, a continuous air sample was obtained. No detectable activity was measured at any of the release points.

N

7. Minimum Detectable Concentrations-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 'Offsite Dose Calculation Manual Specification Table 4.8.B.1 Radioactive Liquid Waste Sampling and Analysis. In all cases, these LLDs were less than the values required by Offsite Dose Calculation Manual 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 Offsite Dose Calculation Manual Specification Table 4.8.C.1 Radioactive Gaseous Waste Sampling and Analysis from Main Stack and Vent Stack. In all cases, these LLDs were less than the values required by Offsite Dose Calculation Manual Specifications.

Ch i

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