ML20138A993

From kanterella
Jump to navigation Jump to search
Annual Effluent Release Rept Number 39,for 960101-1231
ML20138A993
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1996
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20138A985 List:
References
39, NUDOCS 9704290027
Download: ML20138A993 (18)
v • d • e


Text

i x l

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

l 1

ANNUAL EFFLUENT RELEASE REPORT NO. 39 JANUARY 1,1996 TIIROUGII DECEMBER 31,1996

)

t l

Submitted to i The United States Nuclear Regulatory Commission I l Pursuant to )

l Facility Operating Licenses DPR-44 and DPR-56 1 I

i 9704290027 970423 ,

PDR ADOCK 05000277 i R PDR ~

l

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, 1996 through December 31,1996. 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 Offsite ;

Dose Calculation Manual Specification limits. There were no changes made to the Off-Site Dose Calculation Manual (ODCM) during the reporting period.

In accordance with the guidance in NRC Generic Letter 89-01, the PBAPS Technical Specifications were converted to NUREG-1433 (Standard Technical Specifications for '

General Electric Plants, BWR/4) with an effective date of 1-18-96.

l l

j New Sorrento gaseous effluent radiation monitors were installed at all three gaseous i effluent release points (Main Stack, Unit 2 Roof Vent, and Unit 3 Roof Vent). This l l installation was completed 9-5-96. i l

l The station Process Control Program (PCP) was revised on 9/27/96. The incorporated changes were:

1) Revise references to the QA Plan (A-C-930), ,
2) Add description of on-site oil incineration, l
3) Add description of polymer use in condensate resin at Limerick, l
4) Add implementation of 10CFR20.2002 for Limerick, and l
5) Describe the use of condensate demineralizer pre-coat.

l A copy of the revised RW-C-100 Solid Radwaste System Process Control Program j (PCP)is attached to this report.

The 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 i gas effluent monitor information.

There were two unplanned releases of liquid radioactive material.

There were three abnormal gaseous radioactive material release events. Two were l

l unplanned. One was a planned acceptance test for the new effluent monitors.

i 1

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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

I 2 ERROR 1 TOTAL %

A. Fission & activation gases

l. Total release Ci 1.72El 1.29E2 18.8
2. Average release rate for period pCi/sec 2.19E0 1.64El 18.8
3. Gamma Air Dose Millirad 5.37E-4 2.57E-2 18.8

. Percent of Technical Specification  % 5.37E-3 2.57E-1 18.8 1

4. Beta Air Dose Millirad 4.29E-4 1.78 E-2 18.8 l l

Percent of Technical Specification  % 2.15E-3 8.90E-2 18.8 B. Iodines

. 1. Total iodine-131 Ci 1.11 E-3 1.87E-3 22.9

2. Average release rate for period pCi/sec 1.41 E-4 2.38E-4 22.9
3. Critical Organ dose Millirem 6.60E-3 8.42E-3 22.9 Percent of Technical Specification  % 4.40E-2 5.61 E-2 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 5.96E-4 4.65E-4 22.9 and Strontium 89-90)
2. Average release rate for period pCi/sec 7.58E-5 5.91E-5 22.9
3. Average Gross Alpha Radioactivity Ci 4.37E-6 2.09 E-6 22.9 D. Tritium
1. Total release Ci 0 9.36El 23.5
2. Average release rate for period Ci/sec 0 1.19El 23.5 2

. . EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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

1. Total release Ci 2.00E2 1.31E2 18.8
2. Average release rate for period pCi/sec 2.55El 1.63E1 18.8
3. Gamma Air Dose Millirad 3.91 E-2 2.40E-2 18.8 Percent of Technical Specification  % 3.91E-1 2.40E-1 18.8
4. Beta Air Dose Millitad 2.67E-2 1.67E-2 18.8 Percent of Technical Specification  % 1.34E-1 8.35E-2 18.8 B. Iodines
1. Total iodine-131 Ci 3.03E-3 1.55E-3 22.9
2. Average release rate for period pCi/sec 3.85 E-4 1.93 E-4 22.9
3. Critical Organ dose Millirem 1.40E-2 7.72E-3 22.9 Percent of Technical Specification  % 9.33 E-2 5.15E-2 22.9 C. Particulates
1. Particulates with half-lives greater than 8 days (includes Alpha Ci 4.55E-4 5.70E-4 22.9 and Strontium 89-90)
2. Average release rate for period Ci/sec 5.79E-5 7.09E-5 22.9
3. Average Gross Alpha Radioactivity Ci 5.46E-6 5.14E-6 22.9 D. Tritium
1. Total release Ci 5.98E1 0 23.5
2. Average release rate for period '

Ci/sec 7.61E0 0 23.5 l

l 3  !

i

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

Table IB Page 1 of 2 Gaseous Efauents for Release Point - Main Stack i

Continuous Mode Batch Mode 1 Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 J

1. Fission gases i l

Krypton - 85M Ci 9.06E-1 1.41EO 0 0 Krypton - 87 Ci 0 0 0 0 Krypton - 88 Ci 0 0 0 0 Xenon - 133 Ci 9.83E0 1.18E1 0 0 Xenon - 135 Ci 3.38E0 3.07E0 0 0 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 1.05E0 0 0 0 Unidentified Ci 0 0 0 0 Total for Period Ci 1.52E1 1.63E1 0 0

2. Todines i 1

Iodine - 131 Ci 6.54 E-4 8.66E-4 0 0 Iodine - 133 Ci 1.94 E-3 5.16E-3 0 0 l

Iodine - 135 Ci 0 4.19E-3 0 0  :

1 Total for Period Ci 2.59E-3 1.02E-2 0 0

3. Particulates i

Strontium - 89 Ci 3.49E-4 2.76E-4 0 0 Strontium - 90 Ci 7.20E-7 3.00E-7 0 0 l

Barium - 140 Ci 1.38E-4 7.10E-5 0 0 TOTAL FOR PERIOD Ci 4.88 E-4 3.47E4 0 0 4

i l

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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

1. Fission gases Krypton - 85M Ci 9.45E0 2.15E0 0 0 Krypton - 87 Ci 1.75E-1 2.65E0 0 0 l

Krypton - 88 Ci 8.97E-1 0 0 0 l

Xenon - 133 Ci 2.13El 2.81 E0 0 0 Xenon - 135 Ci 1.15El 1.70El 0 0 Xenon - 135M Ci 2.05E0 9.83E-1 0 0 Xenon - 138 Ci 2.76E0 5.18E0 0 0 l

Argon - 41 Ci 0 3.19E0 0 0 l l

Kryptori - 85 Ci 0 0 4.84E-1 0 Unidr.stified Ci 0 4.84E0 0 0 I Total for Period Ci 4.81El 3.88El 4.84E-1 0

2. Iodines Iodine - 131 Ci 1.30E-3 4.99E-4 0 0 Iodine - 133 Ci 2.30E-3 1.55E-3 0 0 lodine - 135 Ci 0 0 0 0 Total for Period Ci 3.60E-3 2.05 E-3 0 0
3. Particulates Strontium - 89 Ci 2.39E-4 2.33 E-4 0 0 Strontium - 90 Ci 2.34E-7 3.80E-7 0 0 Cesium - 137 Ci 1.10E-6 0 0 0 Barium - 140 Ci 4.08E-5 1.24E-5 0 0 Cerium - 141 Ci 0 4.50E-7 0 0 TOTAL FOR PERIOD Ci 2.81 E-4 3.58 E-4 0 0 5

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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. Fiaion 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 1.11E1 0 0 Xenon - 135M Ci 0 0 0 0 Xenon - 138 Ci 0 0 0 0 Krypton - 85 Ci 0 0 0 2.29E0 1

Unidentified Ci 2.02E0 9.84El 0 0 Total for Period Ci 2.02E0 1.10E2 0 2.29E0

2. Iodines

, Iodine - 131 Ci 4.58 E-4 1.01E 3 0 0 Iodine - 133 Ci 4.87E-3 9.64E-3 0 0 lodine - 135 Ci 0 0 0 0 Total for Period Ci 5.33 E-3 1.07E-2 0 0 .

3. Particulates Strontium - 89 Ci 1.03 E-4 1.15E-4 0 0 Strontium - 90 Ci 0 8.00E-7 0 0 i TOTAL FOR PERIOD Ci 1.03E-4 1.16 E-4 0 0 f

u 6

\

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/3:/96)

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

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 5.14E-3 0 Unidentified Ci 1.52E2 9.25El 0 0 Total for Period Ci 1.52E2 9.25El 5.14E-3 0
2. Iodines Iodine - 131 Ci 1.73E-3 1.05E-3 0 0 lodine - 133 Ci 1.73E-2 7.07E-3 0 0 lodine - 135 Ci 1.61E-2 0 0 0 Total for Period Ci 3.51E-2 8.12E-3 0 0
3. Particulates Strontium - 89 Ci 1.46E-4 1.52E-4 0 0 Strontium - 90 Ci 1.77E-7 1.30E-7 0 0 Barium - 140 Ci 2.23E-$ 0 0 0 Cobalt - 60 Ci 0 2.03E-5 0 9.92E-7 Zinc - 65 Ci 0 3.12E-5 0 2.22 E-6 TOTAL FOR PERIOD Ci 1.68E-4 2.04E-4 0 3.21E-6 7

\

l EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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 1.82E-3 6.64E-5 22.9
2. Average diluted concentration during period pCi/ml 2.67E-11 1.91E-12 22.9 1
3. Total Body Dose ADULT Millirem 1.06E-3 1.47E-4 22.9 Percent of Technical Specification  % 3.53E-2 4.90E-3 22.9
4. Maximally Exposed Organ Dose TEEN LIVER Millirem 1.57E-3 1.85 E-4 22.9 Percent of Technical Specification  % 1.57E-2 1.85E-3 22.9 l B. Tritium
1. Total release Ci 1.32E1 1.44E1 15.0 1

j 2. Average diluted concentration during period Ci/ml 1.94 E-7 4.14E-7 15.0  :

C. Dissolved and entrained gases i 1. Total release Ci 1.73E-3 5.48E-3 22.9

2. Average diluted concentration during period Ci/ml 2.54E-11 1.57E-10 l 22.9

_D. Gross alpha racioactivity I

1. Total release Ci 1.87E-7 0 22.9
2. Average diluted concentration during period pCi/ml 2.74E-15 0 22.9 j E. Volume of waste released (prior to dilution) liters 1.51E6 2.06E6 12.7 F. Volume of dilution water used during period liters 6.82E10 3.48E10 10.9 8

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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 tritium, gases, alpha) Ci 1.53E-5 2.85 E-3 22.9
2. Average diluted concentration during period Ci/ml 5.20E-13 5.40E-12 22.9
3. Total Body Dose ADULT Millirem 8.57E-5 4.02E-4 22.9 Percent of Technical Specification  % 2.86E-3 1.34E-2 22.9
4. Maximally Exposed Organ Dose TEEN LIVER Millirem 1.07E-4 8.16E-4 22.9 Percent of Technical Specification  % 1.07E-3 8.16E-3 22.9 I

B. Tritium

1. Total release Ci 6.96E0 1.16El 15.0
2. Average diluted concentration during period Ci/ml 2.37E-7 2.20E-8 15.0 C. Dissolved and entrained gases
1. Total release Ci 2.34E-3 2.55E-3 22.9
2. Average diluted concentration during period pCi/ml 7.96E-11 4.83E-12 22.9 D. Gross alpha radioactivity
1. Total release Ci 0 0 22.9
2. Average diluted concentration during period Ci/mi 0 0 22.9 E. Volume of waste released (prior to dilution) liters 1.97E6 1.56E6 12.7 F. Volume of dilution water used during period liters 2.94E10 5.28 Ell 10.9 9

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96 - 12/31/96)

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 9.00E-7 0 0 0 Alpha Ci 1.87E-7 0 0 0 Tritium Ci 7.79E-3 0 1.32El 1.44El Phosphorus - 32 Ci 0 0 0 0 l Iron - 55 Ci 4.84E-5 0 0 0 1

l Xenon - 133 Ci 0 0 3.73E-4 1.67E-3 Xenon - 135 Ci 0 0 1.36E-3 3.80E-3 Manganese - 54 Ci 1.62E-4 0 4.60E-5 2.08 E-6 Cesium - 134 Ci 5.36E-5 0 6.03E-7 0 l Cesium - 137 Ci 1.53 E-4 0 5.84 E-5 1.63 E-5 Zine - 65 Ci 3.09E-4 0 3.44E-5 5.39E-6 Cobalt - 58 Ci 6.40E-6 0 0 0 Cobalt - 60 Ci 5.81 E-4 0 2.95E-4 4.26E-5 Iodine - 133 Ci 0 0 9.55E-6 0 Lanthanum - 140 Ci 0 0 6.92E-5 0 TOTAL FOR PERIOD Ci 9.10E-3 0 1.32El 1.44E1 10

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96- 12/31/96)

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 2.23E-7 0 0 Strontium - 90 Ci 0 0 0 0 Alpha Ci 0 0 0 0 Tritium Ci 0 1.65E-2 6.96E0 1.16El Phosphorus - 32 Ci 0 0 0 0 Iron - 55 Ci 0 1.94E-5 0 0 l l

Xenon - 133 Ci 0 0 6.27E-4 1.03E-3 Xenon - 135 Ci 0 0 1.71 E-3 1.52E-3 Manganese - 54 Ci 0 4.36E-4 0 6.80E-6 Cesium - 134 Ci 0 0 0 0 Cesium - 137 Ci 0 1.74E-5 1.30E-5 1.43E-5 Zine - 65 Ci 0 1.71E-3 0 0 Cobalt - 58 Ci 0 7.38E-5 0 0 Cobalt - 60 Ci 0 5.22E-4 2.34 E-6 4.84E-5 Iron-59 Ci 0 8.79E-6 0 0 TOTAL FOR PERIOD Ci 0 1.93 E-2 6.96E0 1.16El 11

EFFLUENT & WASTE DISPOSAL ANNUAL REPORT (1/01/96- 12/31/96) l PEACH BOTTOM UNITS 2 & 3 '

CLASSES OF SOLID RADIOACTIVE WASTE SHIPMENTS l l

Total # of Waste Description Individual Total '

Shipments (source of waste) Container / Type Volume Volume Total Principal (cubic ft.) (cubic ft.) Curie Radionuclides CLASS A 25 Dewatered Resin HICffype A Cask 195.2 4880.0 1.87E + 02 Zn-65, Co-60, Cs-137 i Mn-54, Ni-63 l 137 DAW (*) Metal Box /STC variable 1486.3 1.38E + 00 Co-60, Cs-137, Zn-65 Cr-51, Mn-54

(**) Dewatered Filters (*) Metal Box /STC variable 197.1 5.08E-01 Zn-65, Co-60, Cs-137, Mn-54, Ni-63

(**) Incinerator Ash (*) Metal Box /STC varisble 63.0 7.12E-01 Co-60, Cs-137, Zn-65 Cr-51, Mn-54 4

(**) Asbe A. (*) Metal Box /STC variable 357.8 8.66E-02 Co-60, Cs-137, Zn-65 Cr-51, Mn-54 CLASS B 1 Dewatered Resin HICfrype A Cask 195.2 195.2 4.34E + 01 Co-60, Cs-137, Zn-65 Ni-63, Ce-144  !

1 Dewatered Revin HIC / Type B Cask 135.8 135.8 6.34E + 02 Zn-65, Co-60, Mn-54, Ni-63, Fe-55 2 DAW /Dewatered HIC / Type A Cask 202.1 404.2 1.62E + 01 Co-60, Ce-144, Zn-65

Filters Fe-55, Mn-54 L

, CLASS C None TOTALS 166 7719.4 S.83 E + 02 i NOTES:

  • -Indicates actual total PECO radwaste shipped from Scientific Ecology Group (SEG), after volume reduction, to the burial site.
    • -Shipment total included with DAW from SEG as these shipments contain commingled waste streams. j i

1 l

l l

12  ;

ATTACHMENT A ,

SUPPLEMEiVF INFORMATION k Facility: Peach Bottom Units 2 & 3 l 1

i Licenses: DP3 e D P.4 4;

1. Regulatory Limm e$fsite Dose Calculation Manual Specification Limits)

A. Noble Gases:

1. s500 mrem /Yr - total body -

" instantaneous" limits

, s3000 mrem /Yr - skin ODCMS 3.8.C.I.a i

2. s 10 mrad - air gamma -

quarterly air dose limits j $20 mP.ad - air beta ODCMS 3.8 C.2.a and b 4

)

4 l

l 3. s 20 mrad - air gamma -

yearly air dose limits i s 40 mrad - air beta ODCMS 3.8.C.2.c and d i~

B. Iodines. Tritium. Particulates with Half Life > 8 days; i

1. s1500 mrem /Yr - any organ -

" instantaneous" limits j 6phalation path) ODCaiS 3.8.C.I.b i

2. s 15 mrem - any organ -

quarterly dose limits j 4

ODCMS 3.8.C.3.a j l

3. s 30 mrem - any organ -

yearly dose limits i ODCMS 3.8.C.3.b i

C. Liould E' cats l

1. Concentration s10 CFR 20, -

" instantaneous" limits l

Appendix B, Table II, Col. 2 ODCMS 3.8.B.1
2. s3.0 mrem - total body -

quarterly dose limits s 10 mrem - any organ ODCMS 3.83.2.a

3. $ 6.0 mrem - toml body -

yearly dose limits

$ 20 mrem - any organ -

ODCMS 3.8.B.2.b

2. Maximum Permissible Concentrations:

MPCs are not used to calculate permissible release rates and concentrations for gaseous releases. i 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 Offsite Dose Calculation Manual Specification 3.8.B.I.

13

ATTACHMENT A (continued)

3. Average Enerzy:

Not Applicable

4. Measurements and Approximations 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 1

- Charcoal Cartridge -

1 C. Particulates:

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

- Air Particulate Sample, (37mm,47mm, and 57mm filters) -

D. Liquid Effluents: l 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: 28 34 39 32 Total Time for batch releases (minutes 5708 7301 7420 6146 ,

Maximum time period for batch release 260 300 279 300 (minutes):

Average time period for batch release 203.86 214.74 190.26 192.06 (minutes):

Minimum time period for batch release 24 70 45 50 (minutes):

Dilution volume (liters): 1.52E10 3.48E10 2.94E10 2.76E10 B. Gaseous:

Not applicable 14 1

l l

ATTACHMENT A (Continued) '

! 6. Abnormal Releases: ,

I A. Liauid:

~

i l

1. Event description - A continuation of the high pressure service water (HPSW) event, l

discovered on 8/15/95 through routine sampling of the effluent to the discharge canal, was '

terminated on 1/15/96. Investigation of this event determined that a trace amount of i condensate stay-full or primary coolant water was leaking past the Unit 3 'A' Residual Heat j 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 7.16E-4 millirem total body dose to the discharge canal from 1/1/96 to 1/15/96. This dose contribution was well below the limits j specified in the ODCM.

l 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 Annual Effluent Report for the applicable reporting period.

2. Event Description - On 10/7/96 routine sampling of the 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' RHR Heat Exchanger Floating Head Gasket into the 'A' loop of the HPSW.

It was estimated that the contaminated water released 3.05E-4 millirem total body dose to the discharge canal from 10/7/96 to 12/31/96. This dose contribution was well below the limits specified in the ODCM.

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 Annual Effluent Report for the applicable reporting period.

B. Gaseous:

1. Event Description - Prior to placing each of the new Sorrento gaseous effluent radiation monitoring systems in service, their accurate response was verified by releasing a known quantity of Kr-85 gas into each effluent process stream and comparing this known quantity with the value obtained from the monitors.

A total air dose of 8.19E-6 mrad gamma and 7.84E-5 mrad beta was released to the atmosphere. This dose contribution was well below the limits specified in the ODCM.

Analysis of Release - The known quantity of Kr-85 gas released and its dose contribution from these planned batch releases were added to this Annual Effluent Report for the applicable reporting period. .

15 >

Ja a i

l l ATTACHMENT A (Continued) l I

6. Abnormal Releases: (Continued)
2. Event Description - On 7/18/96 during the construction of the Plant Entrance and Radiochemistry Lab, holes were cut into the Unit 3 turbine building outside walls creating a potential radiological release path.

1 It was estimated that 6.32E-7 mrad gamma and 3.26E-7 mrad beta air dose was released to the atmosphere from 7/18/96 to 7/25/96. This dose contribution is well below the limits specified in the ODCM.

l Analysis of Release - A representative sample was analyzed and the radioactive effluent ,

l release calculated based on postulated release conditions. The dose contribution and isotopic '

l quantity from this batch release was added to this Annual Effluent Report for the applicable l reporting period.

1

3. Event Description - On 11/21/96, routine sampling and analysis of the hot shop 'B' train ventilation exhaust detected low level particulate radioactivity. Hot shop work was suspended and the ventilation exhaust was removed from service. Investigation revealed that the HEPA j l filters in the 'B' train exhaust had failed. l l

It was estimated that 1.03E-6 mrem was released to the atmosphere from 11/14/96 to l l

11/21/96. This dose contribution was well below the limits specified in the ODCM. l l Analysis of Release - The representative particulate filter sample was analyzed and the l radioactive effluent release calculated based on actual release conditions. The dose l contribution and isotopic quantities from this batch release were added to this Annual Effluent Report for the applicable reporting period.

l 1

7. Minimum Detectable Concentrations:

A. Liquid:

1

! 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 l 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 activ.ty indicates that no activity was positively detected in any sample when samples were analyzed with techniques which achieved the required IAwcr 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.

16

Retrieved from "https://kanterella.com/w/index.php?title=ML20138A993&oldid=2826409"