ML20153G051

From kanterella
Jump to navigation Jump to search
Semiannual Effluent Releases Rept 25 for Jan-June 1988
ML20153G051
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 06/30/1988
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20153G049 List:
References
NUDOCS 8809080023
Download: ML20153G051 (17)
v • d • e


Text

- -

l 2880089940 PEACH BOTTOM ATOMIC PO'n'ER STATION Unit Nos. 2 and 3 Docket Nos. 50-277 & 50-278 SEMI-ANNUAL ETTLUENT RELEASES REPORT NO. 25 JANUARY 1, 1988 THROUGH JUNE 30, 1988 Submitted to The United States Nuclear Regulatory Com:nission Pursuant to racility Operating Licenses DPR-44 & DPR-56 l

h$0 IDO - f7 R

l 2880089940 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION Unit Nos. 2 and 3 Docket Nos. 50-277 & $0-278 SEMI-AtJNUAL EPPLUENT hELEASES REPORT NO. 25 JANUARY 1, 1988 THROUGH JUNE 30, 1988

\

Submitted to

, Tne United States Nuclear Regulator) Corrais sion Pursuant to Pacility Operating Licenses DPR-44 & DPR-56 Preparation Directed By:

D. M. Smith, Vice President Peach Battom Atomic Power Station

TABLE OF CONTENTS ~

94h Pace No.

I. Introduction 11 II. Tables IA. Gaseous Effluents - Summation

  • 1 of A1_1 Releases IB. Gaseous Effluents For Release 2 Point - Main Stack >

6 IC. Gaseous Eff 'or Release 4 Point - U/2 Roof Vents 2A. Liquid Effluents - Summation of 6 i All Releases- l

28. Liquid Effluents 7
3. Classes of Solid Radioactive 9 Waste Shipments III. Attachments A. Supplemental Information 10 B.1 Inoperable Main Stack Sample Flow Moni.v; 12 B.2 Calculations for Critical Organ Dose Using 12 7 eticulates With Half-Lives Greater than 8 Days i

l Technical Concurrences: (for accuracy of information) l bY& W 8 -n # [j f lb (

Director-Radiation Protection / Date

~

All _4th b b rector,Radwagtp 03 Date

$4f

-i.

l

2880099940 SEMI-ANNUAL EPPLUENT RELEASE REPORT JANUARY 1, TO JUNL 30, 1988

1. MTRODUCTION In accordance with the Unique Reporting Requirementa of Technical Specification 6~.9.2.h(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 through June 30, 1988. The notations E and E-are used to denote positive and negative exponents to the base 10.

The release of radioactive materials during che reporting period was within the Technical Specification limits. There were changes made to the Offsite Doce Calculation Manual (ODCM) during the reporting period.

A copy of the Offsite Calculation Manual is attached to this report.

There were no known unplanned releases of liquid radioactive material.

A special report discussing the inoperability of the Main Stack Sample Flow Monitor is included in the ATTACHMENT B section of this report.

Iodine was not present from either the roof vents or main stack in section labeled Gaseous Effluents (Table 1A). Therefore, the Critical Organ Dose for iodines in mRea was zero. In accordance with the current revision of the Offsite Dose Calculation Manual (ODCM) attached to this report, the Critical Organ Dose was calculated using the particulates with half-lives greater than 8 days. These calculations are incorporated into the ATTACHMENT B section of the report.

In section labeled Liquid Effluents (Table 2B) the Phosphorus-32 reported value is less than the lower <

limit of detection. The half-life of Phosphorus-32 has l been exceeded by a factor of eight half-lives, j therefore, Phosphorus-32 is reported as zero for this repcrting period, in general, any isotope with half- I lives greater than eight shall be reported as zero.

I 1

l 1

I

usu a 2880089940 EFFLUENT AND WASTE DISPOSAL 5EM1 ANNUAL REPORT (1988A)

GASE0US EFFLUENTS - SUMMATION Of ALL RELEASES Unit Quarter Quarter Est. Total 2&3 1 2 Error, %

A. Fission & activation gases

1. Total release Ci 3.02 E2 2.93 E2 54.0 E0
2. Average release rate for peric,d uCi/sec 3.84 El 3.46 El
3. Gamma Air Oose Millirad 3.53 E-2 4.44 E-2 Percent of Tech. Spec.  % 3.53 E-1 4.44 E-1
4. Beta Air Dose Millirad 1.77 E-2 1.96 E-2 Percent of Tech. Spec.  % 8.85 E-2 9.80 E-1 B. lodines
1. Total iodine-131 Ci 0 0 61.0 E0
2. Average release rate for period UCi/sec 0 0
3. Critical Organ Oose Hillirem 5.11 E-6 3.57 E-5  !

Percent of Tech. Spec.  % 3.41 E-5 2.38 E-4 l

C. Particulates

)

1. Particulates with half-lives greater than 8 days (includes Alph* Ard Strontium 89-90) Ci 2.65 E-4 3.31 E-4 61.0 E0
2. Aserage release rat period uCi/sec 4.11 E-5 3.91 E-5
3. Gross Alpha Radioact Ci 2.50 E-5 4.11 E-5 D. Tritium
1. Total release Ci 3.41 E0 1.87 E0 94.0 E0
2. Average release rate for period uCi/sec 4.34 E-1 2.21 E-1 (1)

\

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1988A)

GASEOUS iFFLUENTS FOR RELEASE POINT: MAIN STACK 0 ,

CONTINUOUS MODE BATCH MODE Nuclides Released Unit- Quarter Quarter Qua-ter Quarter 2&3 1 2 1 2

1. Fission gases Krypton-85M Ci 0 0 0 0 6 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 2.47 E2 2.22 E2 ~0 0 Total for period C1 2.47 E2 2.22 E2 0 0 l

f. lodines lodine-131 Ci 0 0 0 0 lodine-133 Ci 0 0 0 0 lodine-135 Ci 0 0 0 0 Total for period Ci 0 0 0 0
3. Particulates Strontium-89 Ci 4.90 E-7 3 G0 E-7 0 0 Strontium-90 Ci 2.60 E-7 8.50 E-7 0 0

~

Strontium-91 Ci 0 o 0 0 Cesium-134 Ci 0 0 0 0 (2)

TABLE IB~(Continued) 2ggoog994()- ,,

CONTINUOUS MODE BATCH MODE-Nuclides Released- Unit Quarter Quarter Quarter Quartd i 2&3 1 2 1- 2 j

Cesium-137 Ci 0- -0 0 0 Cesium-138 C1 0 0 0 0 Barium-139 Ci 0 0 0 0 Barium-140 Ci 0 0 0 0 Lan8herium-140 Ci 0 0 0 0 Cobalt-57 Ci 0 0 0 0 Cobalt-58 Ci 0 0 0 0 Cobalt-60 Ci 0 0 0 0 Zinc-65 Ci 0 0 0 0 -

Yttrium-91M Ci 0 0 0 0  ;

lodine-133 Ci 0 0 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

[

io8als Ci 7.50 E-7 1.21 E-6 0 0 I

.t f

(3) l l

l i

1

TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1988A)

GASE0US EFFLUENTS FOR RELEASE POINT: U/2 & U/3 Roof Vents 288008994r>

CONTINU0US MODE 8ATCH MODE Nuclides Released Unit Quarter Quarter Quarttr Quarter 2&3 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 C1 0 0 0 0 Xenon-138 Ci 0 0 0 0 Xenon-133M Ci 0 0 0 0 Unidentified Ci 5.50 El 1.09 El 0 0 Total for period Ci 5.50 El 7.09 El 0 0
2. Iodines Iodine-131 Ci 0 0 0 0 lodine-133 Ci 0 0 0 0 lodine-135 Ci 0 0 0 0 Total for period Ci 0 0 0 0
3. Particulates Strontium-89 Ci 1.65 E-5 3.05 E-5 0 0 Strontium-90 Ci 8.95 E-6 1.50 E-5 0 0 Strontium-91 Ci 0 0 0 0 Cesiuz-134 Ci 0 0 0 0 CesiuJ-137 Ci 0 0 0 0 (4)

TABLE IC (Continued) 2880089940 CONTINUOUS MODE BATCH MODE-Y Nuclides Released Unit _ Quarter Quarter Quartar Quarter 2&3 1 2 1 2 -;

Cesium-138 C1 0 0 0 0 j Barium-139 Ci 0 0 0 0 .

l Barium-140 Ci 0 0 0 0  ;

Lanthanum-140 Ci 0 0 0- 0 Cobalt-57 Ci 0 0 0 0 Cobalt-58 Ci 0 0 0 0-Cobalt-60 Ci 1.11 E-4 9.13 E-5 0 U~

Zinc-65 Ci 1.03 E-4 1.62 E-4 0 0 Y8trium-91M Ci 0 -0 0 0 ,

lodine-133 Ci 0 0 0 0 Copper-64 Ci 0 0 0 0 Rubidium-88 Ci 0 0 0 0 Manganese-54 Ci 0 0 0 0 Strontiun -Q2 Ci 0 0 0 0 Totals Ci 2.39 E-4 2.89 E-4 0 0 l

l (5) i l

_ _ ~. -- ,-- ~ +--

i ...

nca 2n EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT (1988A)

LIQUID EFFLUENTS - SUMMAT'ON Of'ALL RELEASES '2880089940 Unit Quarter Quarter Est. Total 2&3 1 2 Error, %

A. fission & activation gases

1. Total release (not including Ci 9.49 E-2 7.69 E-2 32.0 E0 tritium, gases, alpha)
2. Average diluted concentration uC1/ml 6.04 E-9 5.34 E-9 during period

~

3. Whole Body Dose Millirem 4.50 E-1 5.47 E-1 Percent of Technical Specification  % 15.0 E0 18.2 EO
4. Bone Oose M111irem 3.64 E-1 4.57 E-1 Percent of Technical Specification  % 3.64 EO 4.57 E0
8. Tritiu;a
l. Total release Ci 4.40 E0 2.43 E0 39.0 E0
2. Average diluted concentration during period uCi/ml 2.81 E-7 1.69 E-7
s. Dissolved and entrained r'a.es ,

l

1. Total release Ci 0 0 42.0 E0 l
2. Average diluted contentration during period UCi/ml 0 0 D. Gross alpha radioactivity
1. Total release Ci 1.14 E-4 1.06 E-4 39.0 E0
2. Average diluted concentration during period uCi/ml 7.26 E-12 7.36 E-12 E. Volume of waste released (prior to dilution) liters 4.98 E6 4.61 E6 32.0 EO F. Volume of dilution water used during period liters 1.57 E10 1.44 E10 30.0 E0

~

(6)

.60'. 4L EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1988A)

LIQUID EFFLUEhTS 2880089940 CONT]NUOUS MODF BATCH MODE Nuclides Released Unit Quarter Quarter Quarter Quarter 2&3 1 2 1 2 Strontium-89 Ci 0 0 1.87 E-4 8.35 E-5 Strontium-90 Ci 0 0 4.80 E-4 3.99 E-5 Alpha Ci 0 0 1.14 E-4 1.07 E-4 Tritium Ci 0 0 4.40 E0 2.43 E0 Phosphorus-32 Ci 0 0 0 0 Iron-55 Ci 0 0 1.33 E-2 2.56 El Xenon-131M Ci 0 0 0 0 Xenon-133 Ci 0 0 0 0 cenon-133M Ci 0 0 0 0 2enon-135 Ci 0 0 0 0

'tenen-138 Ci 0 0 0 0 trypton-85M Ci 0 0 0 0 Krypton-87 Ci 0 0 0 0 irypton-88

~

Ci 0 0 0 0 xenon-135M Ci 0 0 0 0 Manganese-54 Ci 0 0 1.69 E-5 0

elsium-134 C1 0 0 1.76 E-2 1.99 E-2 Cesium-137 Ci 0 0 2.73 E-2 3.73 E-2 Cesium-138 Ci 0 0 0 0 Zinc-65 Ci 0 0 2.11 E-2 8.94 E-3 Sociu2-24 Ci 0 0 0 0 Cobalt-58 Ci 0 0 0 0 Cobalt-60 Ci 0 0 1.43 E-2 8.09 E-3  ;

locine 131 Ci 0 0 0 0 l l

lodine-133 Ci 0 0 0 0 Kolybdenuhi-99 Ci 0 0 0 0 l

(7)

TABLE 28 (Continued')

8800H940 CONTINUOUS MODE BATCH MODE lNuclides Released Unit Quarter Quarter Quarter Quarter 2&3 1 2 1 2 I

lodine-135 Ci 0 0 0 0

Barium-140 Ci 0 0 0 0 Neptunium-239 Ci 0 0 0 0

,Cnromium-51 Ci 0 0 0 0 Yttrium-91M Ci 0 0 0 0

-Strontium-91 C1 0 0 0 0 Antimony-122 Ci 0 0 0 0 Te11urium-132 Ci 0 0 0 0 Niobium-95 Ci 0 0 0 0 Lanthanum-140 Ci 0 0 0 0 I Cadmium-109 Ci 0 0 0 0

~

Cesium-136 Ci 0 0 0 0 l Silver-110M Ci 0 0 8.53 E-5 8.51 E-5 f Cesium-144 Ci 0 0 0 0 Antimony-124 Ci 0 0 0 0 Iron-59 Ci 0 0 0 Tellurium-129M Ci 0 0 0 0

'gilurium-131M Ci 0 0 0 0 Zirconium-95 Ci 0 0 0 0 1

~

Cerium-141 Ci 0 0 0 0 Total for Period (above) Ci 0 0 4.495 E0 2.507 EO (8)

2 PEACH BOTTOM UNITS 2 & 3 JANUARY l TO JUNE 30, 1988 CLASSES OF SOLID RADI0 ACTIVE WASTC SHIPMENTS Individual Total Total # Waste Description Volume Volume Total Principal of Shipments (Source of Waste) Container / Type (cubic feet) (cubic feet) Curie Radionuclides CLASS A )

20 Dewatered Resin HIC / 174.3 2963.1 231.5665 Fe-55, Co-60, 2n-65, l Type A Cask 120.3 240.6 Cs-134 Cs-137 l 83.4 83.4 I 16 DAW Metal Drum / 7.5 6045.0 63.3197 Fc.55, Co-60, Zn-65 STC 11.3 113.0 Cs-234, Cs-137 1 DAW Poly Drum / 38.3 76.6 . 9037 Fe-55, 00-60, 2n-65 STC Cs-134, Cs-137 39 DAW B-25 Box / 96.0 5157.2 4.7414 Fe-55, 00-60, 2n-65, SIC Cs-134, Cs-137 1 Filters HIC / 170.8 170.8 17.6857 Fe-55. Co-60, 2n-65 Type A Cask Cs-134. Cs-137 1 Dewatered Resin / HIC,STC/ 7.5 105.0 5.8574 Fe-55, Co-60, Zn-65 DAW Type A Cask Cs-134, Cs-137 CLASS B 7 Dewatered Resin HIC / 174.3 1220.1 176.6622 Fe-55, Co-60, Zn-65 Type A Cask Cs-134 Cs-137-1 DAW HIC / 120.3 120.3 0.8271 Fe-55. Co-60, Zn-65 Type A Cask Cs-134, Cs-137 1 Dewatered Pesin HIC / 120.3 120.3 158.9576 Fe-55, Co-60, Zn-65 Type B Cask Cs-134, Cs-137 CLASS C 1 Filters, DAW HIC / 120.3 120.3 16.9322 Fe-55 Co-60, Zn-65 Type B Cask Cs-134, Cs-137 TOTALS 68 16535.7 678.4535 i

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

fo

ATTACHMENT A SUPPLEMENTAL INFORMATION B.cil3;y: PeSch Bottom Units 2 & 3 288008994o L.ctases: DPR-44 DPR-56

1. Regulatory Limits (Technical Specification Limits)

A. Noble Gases: .

1. 5 500 mrem /Yr - total body "instantaneous" limits per 5 3000 mrem /Yr - skin Tech. Spec. 3.8.C.l.a
2. 5 10 mrad - gamma air - quarterly air dose limits per 5 20 mrad - beta air Tech. Spec. 3.8.C.2.a
3. 5 20 mrad gamma air - yearly air dose limits per 5 40 mrad - beta air Tech. Spec. 3.8.C.2.b B. Iodines, Tritium, Particulates with Half Life > 8 days:
1. $ 1500 mrem /Yr - any organ "instantaneous" limits per (inhalation path) Tech. Spec. 3.8.C'.l.b
2. $15 mrem - any organ - quarterly dose limits per Tech. Spec. 3.8.C.3.a
3. 5 30 mrem - any organ - yearly dose limits per Tech. Spec. 3.8.C.3.b
_ C. Licuid Effluents
1. Concentration < 10 CFR 20, "instantaneous" limits per Appendix B, Ta51e II, Col. 2 Tech. Spec. 3.8.B.1
2. 1 3.0 mrem - total body - quarterly dose limits per 5 10 mrem - any organ Tech. Spec. 3.8.B.2.a
3. $ 6.0 mrem - total body - yearly dose limits per 5 20 mrem - any organ Tech. Spec. 3.8.B.2.b '

l

2. Maximum Permisttible Concentrations MPCs are not used to calculate pertaissible 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 releases per Peach Bottom Technical Specification 3.8.B.l.

1 (10)

ATTACHMENT A (Continued)

3. Average Energy 2880089940 Not applicable.
4. Msasurements and Approximations of Total Radioactivity A. Pission and Activation Gases The method used is the Nuclear Data 6600/6700 Counting System

- Gas Marinelli B. Iodine t

The method used in the Nuclear Data 6600/6700 Counting System *

- Charcoal Cartridge C. Particulate: '

1 The method used is the Nuclear Data 6600/6700 Counting System

- Air Particulate Sample, 47 mm filter D. Liquid Effluents:

The method used is the Nuclear Data 6600/6700 Counting System and the Radwaste Liquid Discharga Pre-Release Method with a  ;

liter bottle.

i

15. Batch Releases A. Liquid 01 02
  1. of Batch Releases: 66 69 Total Time for batch releases, minutes 18396 16871 Maximum time period for a batch release, minutes 340 340  :

Average time period for batch release, minutes 279 245 Minimum time period for a batch release, minutes 38 23 l Dilution flow (Liters) 1.57 E10 1.44 E10 l

B Gaseous: N/A '

i

6. Abnormal Releases A. Liquid: See Attachment B B. Gaseous *:ene i

l i

(11) 1

1 ATTACHMENT B ,

2880089940  !

SUMMARY

OF UNPLANNED RELEASES i l

1. Inoperable Main Stack Sample Flow Monitor On February 9, 1988, the Main Stack sample flow rate monitor (PT-7341) could not be calibrated during a surveillance test, thus the monitor was determined to be inoperable. Technical Specification 4.8.C.4.e requires that if inoperable radiation monitors cannot be corrected within 30 days, an explanation of why the inoperability was not corrected will be reported in the next Semi-annual Radioactive Effluent Releases Report A replacement monitor was ordered; however, the manufacturer could not supply the same model. In addition, the manufacturer could not deliver a replacement until late May, 1988. On March 18, 1988, a calibration check was successfully performed on a redundant in-line Flow Indicating Transmitter (FIT-6509), which is being used to temporari)y perform the same function as FT-7341. Meanwhile a site modification is currently being designed to install the new monitor, This modification is expected to be installed by October 10, 1988.
2. Calculations For Critical Oroan Dose Usino Particulates With Half-Lives Greater Than 8 Days The following doses were calculated using particulates identified during the first and second quarter reporting period of 1988; PARTICULATE CRITICAL ORGAN DOSE, LIVER, (MREM)

Quarter 1 Quarter 2 Sr-89 6.40 E-8 1.18 E-7 Sr-90 2.97 E-6 5.03 E-6 Co-60 1.03 E-8 8.50 E-8 Zn-65 2.07 E-6 3.05 E-5 Total 5.11 E-6 3.57 E-5 The percentage of Technical Specification for the Critical Organ (liver) for the first quarter is 3.41 E-5, second quarter is 2.38 E-4.

(12)

_

Retrieved from "https://kanterella.com/w/index.php?title=ML20153G051&oldid=2958339"