ML20137L796

Semiannual Radioactive Effluent Release Rept,Jan-June 1985

ML20137L796
Person / Time
Site:	Callaway
Issue date:	06/30/1985
From:	Schnell D UNION ELECTRIC CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
ULNRC-1163, NUDOCS 8509130042
Download: ML20137L796 (122)

Text

e SEMIANNUAL RADI0 ACTIVE EFFLUENT 2

RELEASE REPORT CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JANUARY - JUNE, 1985 4

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TABLE OF CONTENTS 1.0 DTRODUCTION 2.0 SUPPLEMENTAL INFORMATION 2.'l Regulatory Limits

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2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abaormal Releases 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS 4.0 SL M Y OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTES SHIFMENTS 6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.2 Changes to the Process Control Program 6.3 Changes to the Offsite Dose Calculation Manual 6.4 Major Changes to Radwaste Treatment Systems 6.5 Land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrumentation Table 1A Semiannual Summation of Gaseous Releases Table IB Semiannual Air?,orne Continuous and Batch Releases Tchle 2A Semiannual Summation of Liquid Releases Tchle 2B Semiannual Liquid Continuous and Batch Releases Tcble 3 Solid Waste and Irradiated Fuel Shipments l

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TABLE OF CONTENTS (Continued)

Radioactive Liquid Waste Sampling and Analysis Program Radioactive Gaseous Waste Sampling and Analysis Program offsite Dose calculation Manual Changes Description of Radwaste Treatment Systems Changes Process Control Program Changes d

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1

1.0 INTRODUCTION

This Semiannual Radioactive Effluent Release Report is for Union Electric Company's Callaway Plant and is submitted in accordance with the requirements of Technical Specification 6.9.1.7.

The report covers the period from January 1, 1985 through June 30, 1985.

This report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

The information is presented in accordance with the format outlined in Appendix B of f +gulatory Guide 1.21, Revision 1 June 1974.

All liquid and gaseous effluents discharged during this reporting period were in compliance with the 1.Mts of the Callaway Plant Technical Specifications.

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2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatorv Limits Specified as follows are the technical specification limits applicable to the release of radiocctive material in liquid and gaseous effluents.

2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin.

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.

During any calendar year:

Less than or equal to 10 mrad for g

gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.2 Radiciodine, Tritium, and Particulates The dose rate due to Iodine 131 and

133, tritium and all radionuclides in particulate form with half lives greater than eight (8) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem /yr to any organ.

The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 7.5 mrem to

.any organ and, b.

During any calendar year: Less than or equal to 15 mrem to any organ.

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1 2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix. B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/ml total activity.

The dose or dose commitment to an Individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

I During any calendar quarter to less than or equal to 1.5 mrem a.

l to the total body and less than or equal to 5 mrem to any organ, and i

b.

During any calendar year to less than or equal to 3 mrem to the whole body and to less than.or equal to 10 mrem to any organ.

i 2.1.4 Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from i

uranium fuel cycle sources shall be limited to less than or equal to g

25 area to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

2.2 Max h m Permissible Concentrations 2.2.1 The maximum permissible concentration values specified in 10CFR20, Appendix B, Table II, Column 2 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A valtfe of 2.0E-4 microcuries/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents. The concentration limit used to calculate the percent of limit for mixed fission and activation products in Table 2A is 3.0E-7 microcuries/cc.

A limit of 3.0E-3 microcuries/ml (i.e., H-3 i

MPC value) is utilized in the calculation of the percent of limit for tritium in Table 2A.

2.2.2 For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are stated in terms of dose rate at the unrestricted area boundary.

2.3 Average Energy This is not applicable to the Callaway Plant's radiological effluent I

technical specifications.

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2.4 Maasurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Table 4.11-1 and Table 4.11-2 of the Callaway Plant Technical Specifications (See attachments 1 and 2).

Gamma spectroscopy was the primary analysis technique used to determine the radionuclide composition and concentration of liquid and gaseous effluents.

For Sr-89, Sr-90, and Fe-55 composite samples were collected and analyses performed by a contract laboratory.

For these radionuclides the measured concentrations of the previous composite analyses were used.

Tritium and alpha were measured for both liquid and gaseous effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively.

The measured total radioactivity in effluent releases was determined from the measured concentrations of each radionuclide present and the total volume of effluents discharged.

Gross beta or gamma radioactivity measurement techniques were not utilized to approxi-mate the total radioactivity in effluents.

2.5 s Batch Releases 2.5.1 Liquid 2.5.1.1 Number of batch releases: 453 2.5.1.2 Total time period for batch releases:

55173.0 minutes l

2.5.1.3 Maximum time period for a batch release:

395.0 minutes 2.5.1.4 Average time period for batch releases:

121.8 minutes 2.5.1.5 Minimum time period for a batch release:

3.0 minutes 2.5.1.6 Average stream flow during periods of release of effluent into a flowing stream:

69,000 cfs 2.5.2 Gaseous 2.5.2.1 Number of batch releases: 44 2.5.2.2 Total time period for batch releases:

15803.0 minutes 2.5.2.3 Maximum time period for a batch release:

4182.0 minutes 2.5.2.4 Average time period for batch releases:

359.2 minutes 2.5.2.5 Minimum time period for a batch release:

17.0 minutes 4

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2.6 Abnormal Releases 2.6.1 Liquid 2.6.1.1

' Number of releases:

1 2.6.1.2 Total Activity released: 3.15E-2 Curies 2.6.2 Gaseous 2.6.2.1 Number of releases: 0 2.6.2.2 Total Activity released: 0 3.0

SUMMARY

OF GASEOUS RADIOACTIVE EFFLUENTS 3.1 The quantities of radioactive material released in gasecus effluents are suunnarized in Table 1A and IB.

Note that for this repo-ting period no gaseous effluents were considered as elevated release...

4.0

SUMMARY

OF LIQUID RADIOACTIVE EFFLUENTS 4.1 The quantities of radioactive material released in liquid effluents are summarized in Table 2A and 2B.

5.0 SOLID WASTES 5.1 The quantities of radioactive material released in shipments of solid waste and irradiated fuel transported from the site during the reporting period are summarized in Table 3.

6.0 RELATED INFORMATION 6.1 Unplanned Releases 6.1.1 On February 8, 1985, an unplanned release occurred from Secondary Liquid Waste Monitor Tank B (THF04B) which resulted in the discharge of 170 gallons of waste water without an effluent release permit.

Effluent release permit CAL-85-L109 had been generated for the discharge of Liquid Waste Monitor Tank B (THB07B), however, due to personnel error, release of Secondary Liquid Waste Monitor Tank B was initiated instead of Liquid Waste Monitor Tank B.

This condition was recognized by personnel in the Control Room and the release was immediately terminated.

Samples had been collected from-Secondary Liquid Waste Monitor Tank B prior to the inadvertent release. These samples were analyzed and a radiological assessment of the release was conducted in accordance with the Callaway Plant Offsite Dose Calculation Manual. Results of this evaluation are as follows:

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present in the tank:

Ke-133 7.80E-6 uci/ml Xe-135 5.54E-8 uci/ml Concentrations at unrestricted H-3 3.97E-4 uci/al area boundary:

Xe-133 6.33E-8 uci/ml Xe-135 4.49E-10 uci/ml 1

Percent of MPC (Total):

13.3%

Activity released:

3.15E-2 Curies Total body Offsite Dose: 4.52E-8 mrem 4

Percent of quarterly total body dose limit: 3.0E-6%

No technical specifications or 10CFR20 limits were exceeded as a-result of this. release.

Corrective actions have been taken to prevent recurrence, j

6.2 Changes to the Process Control Program Revision 3, to the Callaway Process Control Program (PCP) was issued March 1, 1985. This revision incorporated revised formulations for the solidification of concentrated wastes (borated), revision to the boric acid binding agent (sodium metasilicate) addition chart, and 4

1 incorporation of a new solidification formulation chart for non-borated concentrated wastes.

Minor text wording changes were.

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required due to these changes. Attachment 5 includes documentation of the fact that the change has been reviewed and found ac'ceptable by the On-site Review Committee (ORC).

6.3 Changes to the Offsite Dose Calculation Manual I

Changes incorporated into revision 3 of the Callaway Plant Offsite Dose Calculation Manual include:

1)

Cleanup of typographical errors previously identified by an a'

errata transmitted by letter, ULNRC-803, dated April 17, 1984 from Mr. Donald F.

Schnell, Vice President Nuclear, Union Electric Company to Mr. Harold R.

Denton, Director Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission.

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2)

Incorporation of changes resulting from the 1984 Land Use Census.

3)

Incorporate changes to environmental monitoring station l

locations previously described in the above referenced letter.

! includes copies of the revised pages of the ODCM, a detailed explanation of the changes and documentation of the review l

and approval of the changes by the ORC.

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6.4 Major Changer to Radwaste Treatment Systems During this reporting period, a modification to the liquid radwaste treatment system was completed.

This modification involved the addition of two 100,000 gallon batch waste release tanks.

These tanks were required due to an increase in the volume of secondary liquid waste, specifically waste from condensate demineralizer (polisher) regenerations.

Original design estimates of the volume of secondary liquid wastes from regeneration of the condensate polishers was 17,000 gallons per day.

Plant operational data has shown waste volumes averaging 43,000 gallons per day.

The addition of the two 100,000 gallon tanks was foreseen as a means of providing adequate storage volume for this increase in wastes from regeneration of the condensate 3

polishers as well as to provide required sampling and analysis time 1

i prior to discharge to the environment. On September 11, 1984, this requested modification was approved by the On-site Review Committee.

An application was submitted to NRR on October 3, 1984, requesting a revision to the Technical Specifications to allow the addition of two 100,000 gallon tanks (a copy of this letter is shown as ).

Based upon NRC approval granted on February 4, 1985, (see Attachment 4), work commenced in implementing the subject

=odification with final installation and acceptance of the modification occurring during June 1985.

A detailed dcacription of the subject modification is contained in j

the Safety Ev.duation and Significant Hazards Consideration presented in Attacns nt 4,

ULNRC-937.

As stated therein, the requested modification "does not involve a significant increase in the probability or consequence of an accident or other adverse condition.over previous evaluations; or create the possibility of a new or different kind of accident or condition over previous evaluations; or involve a significant reduction in a margin of safety".

i 6.5 Land Use Census Changes 6.5.1 New critical receptor locations for dose calculations as determined by the most recent land use census are listed as follows:

1 i

Previous Location New Location 4

Nearest Cow 2575 meters W sector 5053 meters NW sector Nearest Goat 3540 meters NNE sector 5053 meters NW sector Nearest Vegetable 2736 meters NNW sector 2865 meters NNW sector i

Garden i

Nearest Residence 2736 meters NNW sector 2865 meters NNW sector 7

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6.6 Inoperability of Effluent Monitoring Instrumentation This section of the report covers the inoperability of the Unit Vent gaseous effluent monitor GT-RE-213 from 5/29/85 to 6/l*/85. Details of this incident are covered in Licensee Event Report 85-028-00.

A sununary of the gaseous radioactive effluents released from the Unic Vent during this time period is provided.

The activity released from the Aux / Fuel Building HVAC System from 5/29/95 to 6/11/85 as determined by performance of the routine gaseous radioactive effluent sampling and analysis program (see Section 2.4) was:

H-3 1.24E-1 Curies Xe-133 1.52E+1 Curies Xe-135 5.20E-1 Curies I-131 6.35E-6 Curies 1-133 1.19E-6 Curies Gross Alpha 1.64E-7 Curies During this period three containment purges were conducted. During each purge redundant particulace, radiciodine and gaseous radioactivity monitors, GT-RE-22 and GT-RE-33, were operable and provided continuous monitoring with alarm and isolation capability.

The total activity released from these three containment purges is presented as follows:

H-3 4.79E-l Curies Kr-85m 4.25E-2 Curies Kr-85 L.50E O Curies Kr-88 2.19E-2 Curies Xe-131m 1.78E 0 Curies Xe-133m 2.43E 0 Curies Xe-133 2.12E+2 Curies Xe-135 1.05E O Curies Ar-41 2.10E-1 Curies The offsite doses resulting from the effluents released from the Unic Vent during this period were only a small fraction of Technical l

Specification limits.

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TABLE LA SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2, 1985 UNIT QUARTER 1 QUARTER 2 EST TOTAL TYPE OF EFFLUENT ERROR %

FISSION AND ACTIVATION GASES TOTAL RELEASE CURIES 3.03E 02 5.73E 02 3.50E 01 AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.90E 01 7.21E 01 PERCENT OF TECH SPEC LIMIT 2.24E-03 4.14E-03 RADIOI0 DINES TOTAL 30 DINE-131 CURIES 5.36E-06 1.86E-05 3.50E 01 AVERAGE RELEASE RATE FC?. PERIOD UCI/SEC 6.89E-07 2.34E-06 PERCENT OF TECH SPEC LIMIT 6.56E-07 2.23E-06 PARTICULATES PARTICULATES (EALF-LIVES > 8 DAYS)

CURIES 6.68E-07 1.40E-05 3.50E 01 AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 8.59E-08 1.76E-06 PERCENT OF TECE SPEC LIMIT 5.58E-09 1.14E-07 GROSS ALPHA RADIOACTIVITY CURIES 5.21E-07 L.70E-06 TRITIUM TOTAL RELEASE CURIES 5.59E-01 1.59E 00 2.50E 01 AVERAGE RELEASE RATE FOR ERIOD UC SEC 7.

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.00E-01 PERCENT OF TECH SPEC LIMIT 4.73E-06 1.32E-05 PAGE 1 of 1 v x.~ ~..?y.y.wmyxs.w.;y&m&_ -

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TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 1 AND 2, 1985 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 FISSION GASES KR-85M CURIES 1.35E 00 3.24E-01 2.68E-01 6.67E-02 KR-85 CURIES 0.00E 00 0.00E 00 0.00E 00 1.57E 00 KR-87 CURIES 1.91E-01 0.00E 00 0.00E 00 0.00E 00 KR-88 CURIES 1.37E 00 4.06E-01 1.56E-01 2.63E-02 XE-131M CURIES 1.73E 00 0.00E 00 8.90E-01 6.97E 00 XE-133M CURIES 2.81E-01 8.99E-02 2.74E 00 3.42E 00 XE-133 CURIES 7.15E 01 9.75E 01 2.10E 02 4.56E 02 XE-135M CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 XE-135 CURIES 5.60E 00 4.38E 00 5.73E 00 1.59E 00 XE-138' CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 AR-41 CURIES 0.00E 00 0.00E 00 7.91E-01 8.67E-01 TOTAL FOR PERIOD CURIES 8.20E 01 1.03E 02 2.21E 02 4.70E 02 10 DINES I-131 CURIES 5.09E-06 1 -,86E-05 2.69E-07 1.53E-08 I-133 CURIES 0.00E 00 1.19E-06 0.00E 00 0.00E 00 I-135 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD CURIES 5.09E-06 1.98E-05 2.69E-07 1.53E-08 PARTICULATES H-3 CURIES 3.71E-01 8.14E-01 1.88E-01 7.71E-01 NA-24 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00

-MN-54 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 FE-59 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 Co-58 CURIES 0.00E 00 1.23E-05 1.46E-07 0.00E 00 CO-60 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZN-65 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-89 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00

% 99 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-134 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 PAGE 1 of 2 t

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l TABLE IB SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, 10 DINES, AND PARTICULATES QUARTERS 1 AND 2, 1985 4

CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 PARTICULATES CONTINUED CS-137 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 BA-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 LA-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CE-141 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CE-144 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-90 CURIES 0.00E 00 0.00E 00 0.00E 00 3.39E-08 G ALPHA CURIES 5.01E-07 1.68E-06 2.00E-08 2.04E-08 UNIDENTJFIED CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD CURIES 3.71E-01 8.15E-01 1.88E-01 7.71E-01 PAGE 2 0F 2

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TABLE 2A SEMIANNUAL SLW!ATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 1 AND 2,1985 UNIT QUARTER l QUARTER 2 EST TOTAL ERROR %

' TYPE OF EFFLUENT FISSION AND ACTIVATION PRODUCTS TOTAL RELEASE (NOT INCLUDING TRIT'IDf, GASES, ALPHA)

CURIES 1.39E-04 9.84E-04 2.50E 01 AVERA;E DILUTED CONCENTRATION DURING PERIOD UCI/ML 1.56E-10 1.87E-09 PERCENT OF APPLICABLE LIMIT 5.20E-02 6.23E-01 TRITIUM TOTAL RELEASE CURIES 1.55E 02 1.63E 02 2.50E 01 f

AVERAGE DILUTED CONCENTRATION l

DURING PERIOD UCI/ML 1.74E-04 3.09E-04 5.80E 00 1.03E 01 f

PERCENT OF APPLICABLE LIMIT I

DISSOLVED AND ENTRAINED GASES l

TOTAL RELEASE CURIES 1.06E-01 1.17E-01 2.50E 01 AVERAGE DILUTED CONCENTRATION l

DURING PERIOD UCI/ML 1.19E-07 2.22E-07 l

PERCENT OF APPLICABLE LIMIT 5.95E-02 1.11E-01 l

GROSS ALPHA RADI0 ACTIVITY TOTAL RELEASE CURIES 4.79E-04 2.87E-04 2.50E 01 l

l WASTE VOL RELEASED (PRE-DILUTION)

GAL 7.38E 06 5.34E 06 L.00E 01 UOLUME OF DILUTION WATER USED GAL.

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TABLE 2B SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTER l AND 2, 1985 CONTINUOUS RELEASES BATCH RELEASES NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 ALL NUCLIDES H-3 CURIES 0.00E 00 3.70E-02 1.55E 02 1.63E 02 NA-24 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CR-51 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 MN-54 CURIES 0.00E 00 0.00E 00 0.00E 00 1.48E-06 FE-55 CURIES 0.00E 00 0.00E 00 0.00E 00 4.34E-04 FE-59 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CO-58 CURIES 0.00E 00 9.98E-06 7.74E-05 3.48E-04 CO-60 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZN-65 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-89 s CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 ZN-95 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 NB-95 CURIES 0.00E 00 0.00E 00 1.35E-06 0.00E 00 MO-99 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TC-99M CURIES 0.00E 00 0.00E 00 6.29E-06 0.00E 00 I-131 CURIES 0.00E 00 0.00E 00 4.94E-05 1.19E-04 I-133 CURIES 0.00E 00 0.00E 00 3.75E-06 5.19E-05 I-135 CURIES 0.00E 00 0.00E 00 0.00E 00 1.44E-05 CS-134 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CS-137 CURIES 0.00E 00 0.00E 00 0.00E 00 1.57E-06 LA-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CE-141 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 CE-144 CURIES 0.00E 00 0.00E 00 0.00E 00 3.86E-06 L'-187 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 KR-85M CURIES 0.00E 00 0.00E 00 2.32E-07 0.00E 00 XE-131M CURIES 0.00E 00 0.00E 00 9.44E-04 7.43E-04 XE-133 CURIES 0.00E 00 0.00E 00 1.03E-01 1.13E-01 XE-133M CURIES 0.00E 00 0.00E 00 7.37E-04 1.11E-03 XE-135 CURIES 0.00E 00 0.00E 00 1.18E-03 1.63E-03 Xs-135M CURIES 0.00E 00 0.00E 00 4.87E-05 L.97E-04 BA-140 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 SR-90 CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 G ALPHA CURIES 0.00E 00 0.00E 00 4.79E-04 2.87E-04 UNIDENTIFIED CURIES 0.00E 00 0.00E 00 0.00E 00 0.00E 00 TOTAL FOR PERIOD CURIES 0.00E 00 3.70E-02 1.55E 02 1.63E 02 PAGE 1 0F 1

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i i TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS QUARTERS I AND 2, 1985 i

A.

SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL 1.

WASTE TYPE SOLIDIFICATION AGENT CUBIC METERS WASTE CLASS TYPE OF CONTAINERS CURIES

% ERROR (CI) q Spent Resins Cement 12.7 A

LSA 3.6E-02

+/- 25%

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Estimates Of Major Nuclides By Waste Type

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t WASTE TYPE NUCLIDE ABUNDANCE CURIES Spent Resins H-3 100%

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Solid Waste Disposition Summary

'e NUMBER OF SHIPMENTS HODE OF TRANSPORTATION DESTINATION 1

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IRRADIATED FUEL SHIPMENTS (DISPOSITION)

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- ATTACIDfENT 1 Amendacnt No. 2 TABLE 4.11-1 RADICACTIVE LIOUID WASTE SAMPLING AND ANALYSIS POOGRAM LOWER LIMIT MINIMUM OFDETECT{0s LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) 'l TYPE FREQUENCY FREQUENCY ANALYSIS (pCf /ml)

1. Baten Wasta P

P

_7 Release Each Batch Eaca 8aten Principal Gamma 5x10 Tanks (2)

C3)

Emitters

~0 I-131 1x10

a. Waste Monitor Tank P

M Dissolved and.

lx10~8 One Satch/M Entrained Gases (Gamma Emittars)

b. Secondary Liquid

-5 Wasta P

M H-3 1x10 C4)

Monitor Each Batch Composita

% Tank Gross Alpha 1x10 '

~0

c. Ofscharge P

Q Sr-89, Sr-90 5x10 Monitor Each Satch Ccaposite(4)

~0 Tank Fe-55 1x10

~7

2. Continucus W

Principal Gamma 5x10 Releases (5)

Daily (6)

Ccaposite(4) Emitters (3)

Grab Sample

~0 I-131 1x10 Steam Generater Blowdown M

M Dissolved and 1x10

• Grab Sample Entrained Gases (Gamma Emitters)

~5 H

H-3 1x10 Daily (6)

Compos'ite( )

7 Grab Sample Gross Alpha 1x10

~0 Q

Sr-89, Sr-90 5x10 Daily (6)

CcmpositeI4)

.g Gran Sample Fe-55 1x10 CALLAWAY - UNIT 1 3/4 11-2 PAGE 1 of 3 7

> - =:.

a. A Y

ASi'~' As %M n "n a

ATTACHMENT 1 REVISION 1

1 AHLI' 4.11-1 (Continued)

TABLE NOTATIONS (1)The LLD is defined, for purposes of these specifications, as the smallest concentration of racioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probacility with only 5% probabil.ity of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 s b E

V 2.22 x 108 Y

exp (-Aat)

Where:

LLD = the "a priori" lower limit of detection (microcuries per unit mass or volume),

g s = the standard deviation of the background counting rate or of b

the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 x 108.= the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield *, when appitcable, A = the radioactive decay constant for the particular radionuclide (s 8), and at = the elapsed time between the midpoint of, samole collection and the time of counting (s).

Typical values of E, V, Y, and at should be used in the calculation, it should be recognized that the LLO is defined as an a_ oriori (before Lhe fact) limit representing the capacility of a measurement system anc not as an a posteriori (after the fact) limit for a particular measurement.

(2)A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method cescribed in the 00CM to assure rm resentative sampling.

~

CALLOWAY - UNIT 1 3/4 11-3 PAGE 2 of 3

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REVislON I

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TABLE 4.11-1 (Continued) s g TABLE NOTATIONS (Continued)

(3)The principal gamma emitters for wnich the LLD specification applies I

include the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7, in the format outlined in Regulatory Guide 1.21, Appendix 8, Revision 1, June 1974.

(4)A concosite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.

(5)A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

.(6) Samples shall be taken at the initiation of effluent flow and at least once g per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter while the release is occurring. To be representa-s tive of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of samole volume to effluent riischarge volume shall be maintained constant for all samples taken for the composite sample.

^

I l

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1 i

,CALLAWAY - UNIT 1 3/4 11-4 PAGE 3 of 3 l

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Principal Gamma Emitters ( }

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ATTACHMENT 2 REVISION I

N TABtf 4.11-2 (Continued) 1ABLE NOTATIONS (1)lh* ILD l's defined, for purposes of these specifications, as the smallest

~

concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66 sb E

V 2.22 x 108 Y

• exp (-Aat)

Where:

LLD = the "a priori" lower limit of detection (microCuries per unit mass or volume),

the standard deviation of the background counting rate or of s bthe counting rate of a blank sample as appropriate (counts per minute),

g i

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

7.22 x 10" = the number of disintegrations per minute per microcurie, YT the f ractional radiochemical yield, when applicable.

the radioactive decay constant for the particular radionuclide A=

(3 5), and at

• the elapsed time between the midpoint of sample collection and the time of counting (s).

l Typical values of E V, Y, and at should be used in the calculation.

It snould be recognized that the LLO is defined as an a priori (before the fact) limit representing the Capability of a measurement system and not as an a posteriori (af ter the f act) limit for a particular measurement.

CAllAWAY - UNIT I 3/4 11-10 PAGE 2 of 3

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1 I

ATTACHMENT 2 REVISlay 1-TABLE a.ll-2 (Continued)

TABLE NOTATIONS (Continued)

(2)The principal gamma emitters for which the LLD specification applies include the following radionucildes:

Kr-87. Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, In-65, Mo-99,1-131 Cs-134. Cs-137, Co-141, and Ce-144 in todine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7, in the format outlined in Regulatory Guide 1.21, Appendix B. Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a liiERMAL POWER change exceeding 15% of RATED THERMAL PCWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> p*riod.

(4)fritium grab samoles shall be taken and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling Canal is flooded.

(S) Tritium grab samples shall be taken and analyzed at least once per 7 drys

~

f rom the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. Grab samples need to be taken only wnen spent fuel is in the spent fuel pool.

(6)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation

~

made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(/) Samples shall he changed at least once per 7 days and analyses shall ce completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal frcm sampler.

For unit vent, sampling shall also be performed at least once per 24 nours inr at least / days following eacn shutdown, STARTUP or THERMAL PCWER cnange exceeding 15% of RATED THERMAL POWER within a 1-nour period and analyses sh.111 be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 2a hours are analyzed, the corresponding LL0s may be increaseo by a f actor of 10.

This requirement does not apply if:

(1) analysis shows that the DOSE EQulvALENT I-131 concentration in the reactor coolant has not increased more than a factea of 3, and (2) the nocle gas monitor shows that effluent activity has not increased more than a factor of 3.

(8) Continuous sa.moling of the spent fuel Duilding exhaust needs to Oe performed unly when spent fuel is in the spent fuel pool.

cal lAWAY - UNIT I 3/4 11-11 PAGE 3 of 3

i,

ATTACHMENT 3 0FFSITE DOSE CALCULATION MANUAL CHANGES This Attachment contains the following:

1.

Description of Changes to the ODCM page 1 through 3 2.

Callaway Plant ORC Meeting Minutes

' ),

l page 1 through 2 3.

ODCM Procedure Request Form Package page 1 through 8 4.

ODCM Rev. 3 Page Changes Pages:

title page, list of effective pages, i, 11, iii, iv, y,

s vi, vii, viii, 11, 13, 17, 18, 19, 21, 33, 38, 39, 40, 41, 46, 47, 51, 52, 53, 54, 55, 56, 57, 58, 59, 72, 74, 76, 78, 80, 81,

83. Figure 5.1A, Figure 5.1B, Figure 5.3, 90, 91, 92, 93, 95, 96, 97, 98, 99, 100, 101, 102 i

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)>

J ATTACHMENT 3 j

Dascription of Changes To The ODCM 1

l Th2 following presents justification for the changes to the ODCM. A copy of tha revised pages and documentation of ORC approval is included.

Page 11 Minor typographical error.

i Pcge 13 Changes " Individual" to " Member of the Public".

Removed the term "from each unit" as the Callaway Plant is a single unit site. This is

. consistent with the wording of Callaway Plant Technical specifications.

s Ptge 17 1

The former wo~rdirg, "nuclides which are below the LLD for the analyses are reported as "less than" the nuclides Minimum Detecable Activity (MDA

.," was somewhat confusing and ambiguous.

The revised wording 1

I provides clarification with respect to the use of the MDA for nuclides i

% chat are not detected.

Pages 18 & 19 (Table 1) i Added Ingestion Dose Commitment Factor values for Br-85, Y-93, Tc-101, j

Ba-141, Ba-142, and La-142.

j Page 21 1

l Remove'd;che term "from each unit", as the Callaway Plant is a single unit i

site.

Prge 33 The former definition indicated that Qi was applicable only to radiciodines. The new definition clearly applies to all radionuclides.

1 Prge 38 i

Removed the term "from each unit".

Phges 39 s 40 i.

Revised " Individual" to " Member of the Public". Removed the term "from i

each unit".

Prge 41 Revised to allow application of D/Q values at or beyond the Site l

Boundary, as appropriate, in accordance with Tech Spec 3.11.2.3.

3 PAGE 1 0F 3 1

i.

m _,,u.c.mJ 1 AA.;AiO.jd M h lOfU 1 % % -%

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Page 46 Typographical error. Revised to read Tc-99m instead of Te-99m.

Page 47 Skin dose fsetor Te-131 was revised from 3.45E7 to 3.45E4. The original value was miscalculated due to an apparent typographical error in Reg.

Guide 1.109.

Pages 51, 52, 53, 54, 55, 56, 57, 58 & 59 I

l Typographical errors as identified by ULNRC-803.

Pages 72 Added description to Station #20. Corrected error in stated location for Station #34. No changes to actual station locations.

Page 74 Added stations B-3 and A-9 to Table 6 as identified in ULNRC-803.

Page 76

%Added footnote "g" in accordance with Tech Spec 3.12.1, Table 3.12-1.

Page 78 Replaced stations V-2 and V-4 with new stations V-6 and V-7, as identified by the 1984 Land Use Census.

Pages 80, 81 & 83 Footnotes revised as per Tech Spec 3.12.1, Table 4.12-1, and Table 4.1_-2.

Figures 5.lA, 5. lB, and 5.3 Revised as per revised Table 6.

Page 90 "Rev" changed to "Ref".

Figure 6.1 was deleted an it was originally intended to be a graphical representation of hor ;ae computational procedure works and not intended to be used n ds er=ine the site-specific slope factor. The ODCM har bres (

ised to reference the same figure in NUREG/CR-2929. Typograph.c.. ni. "8700 hours0.101 days <br />2.417 hours <br />0.0144 weeks <br />0.00331 months <br />" corrected to "8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />".

Pages 91, 92, & 93 Corrected typographical errors as identified in ULNEC-803. Changed receptor locations as identified by the 1984 Land Use Census.

PAGE 2 OF 3

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Page 95 & 96 Revised to be consistent with Tech Spec 6.9.1.7.

Page 97 Revised to incorporate the results of the evaluation of computer codes utilized to calculate offsite deses.

Pages 98 & 99 Added ref erence 9.5..i.

Corrected reference 9.6.14.

Pages 100, 101, & 102 Page numbers have changed due to addition of reference 9.5.5 on page 98 (above). No changes to references.

s PAGE 3 0F 3

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ORC Meeting #433s ORC OPEN ITEMS LIST l

1.

JTG Punchlist items:

1. 351 - At the first refueling outage: Normal exhaust fans, Aux.

Bldg. didn't meet Acceptance Criteria 2.3 in slow speed; need i

CMR 84-0271A prior to work.

2.

Physical Security Plan Change Notice #235 held open pending clarification of documentation on security boundaries.

3.

IR 85-036 held open (status change) pending FM performance (MPE-ZZ-QS005) indicates no problems found. Action assigned Asst.

Manager O&M.

\\ 4.

APA-ZZ-00748 Rev. O, held open pending further review of procedure by Industrial Relations. APN has action. Due date July 19, 1985.

5.

IR 85-0235 held open pending further Operation and Rad Waste discussion to prevent further occurrance. GLR has action. Due date June 28, 1985.

l l

This is page 2 of 2 of the minutes for this meeting i

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U N ION E L.ECT R I C C O M P A N Y 1908 GRATIOT STREET ST. Louls, Missount uneuesa acoseum s.

O'f,..",,"l,",l'"

April 17, 1984

,, so J.,

• ,."o,*,.....

Mr. Harold ~R.

Denton, Director Office of Nuclear Reactor Regulation

.U.S.

Nuclear Regulatory Commission Waehington, D.C.

20555 Daar Mr. Denton:

ULNRC-803 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 OFFSITE DOSE CALCULATION MANUAL, REV. 2 ERRATA

Reference:

ULNRC-760 dated March 8, 1984 The referenced letter transmitted Revision 2 of the Callaway Offsite Dose Calculation Manual (ODCM).

As a result of a phone callsbetween Mr. Ed Branagan (NR) and Mc.

D.

Shafer (UE) on April 16, 1984, the following additional information is submitted:

1)

Errata to Callaway ODCM, Revision 2.

21 Change page 73 and Figure 5.lB indicating monitoring station A-9 is the " community of Reform" and adding station B-3.

3)

" Comparison of Callaway Plant Offsite Dose Calculations for Routine Effluents" performed by Bechtel Power Corporation dated 3/22/84.

The corrections and additions from items 1 and 2 will be made in the initial-Semi-Annual Radioac".ive Effluent Release Report.

f',gy truly yours, Ve

'l

~jk

\\,. 0. 0- z u un J

Dona g Schnell DS/lw cc:

J. Holonich w/a E. Branagan w/a f.b wmmn..

STATE OF MISSOURI )

)

SS CITY OF ST. LOUIS )

Robert J. Schukai, of lawful age, being first duly sworn upon oath says that he is General Manager-Engineering (Nuclear) for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

l\\

n

.J u

k)

/)

h By

(

Robe t J. S hukai Genera ager-Engineering Nuclear SUBSCRIBED and sworn to before me this /M day of

,198g n0 /

BARSARAdNAY #

f40TARY PUGUC, STATE OF 7.!!S20U21 MY COMMIS$10ii EXPIRES APRIL 22, 1533

.SI. LOUIS COUNTX I

p.4 wwa

~.

cc.

Glenn L.

Konster Vice President Operations Kansas Gas & Electric P.O. Box 208 Wichita, Kansas 67201 Donald T.

McPhee Vice President Kansas City Power and Light Company 1330 Baltimore Avenue Kansas City, Missouri 64141 Gerald Charnoff, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M.

S treet, N.W.

Washing ton, D.C.

20036 Nicholas A. Petrick Executive Director SNUPPS 5 Choke Cherry Road Rockville, Maryland 20850 John H. Neisler Callaway Resident Office N

U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 William Forney Division of Projects. and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, M.'ssouri 65077 h 65 www.ew.swemmwww -< = ~- - _

_. ~..

-+~::

i A

l Pcgo 1 Errata to Callaway ODCM Revision 2 PEge Column Line Change

~

51 NUCLIDE 6

Change "Mu" to "Mn" 51 NUCLIDE 7

Change "Mu" to "Mn" 51 NUCLIDE 8

Change "fe" to "Fe" 51 NUCLIDE 9

Change "fe" to "Fe" 51 NUCLIDE 16 Change "Zn-60" to "Zn-69" 51 NUCLIDE 17 Change "BR" to "Br" 51 NUCLIDE 18 Change "BR" to "Br" 51 NUCLIDE 22 Change "RB" to "Rb" 51 NUCLIDE 25 Change "SR" to "Sr" 52 NUCLIDE 13 Change "Rn" to "Ru" r

52 NUCLIDE 14 Change "Rn" to "Ru" l

l 53 NUCLIDE 7

Change "Cs-134" to "Cs-136" l

l 54 LIVER 4

Change "4.37E10" to "4.37E9" l

55 NUCLIDE 13 Change "Rn" to "Ru" 55 NUCLIDE 14 Change "Rn" to "Ru" 56 NUCLIDE 2

Change "I-131" to "I-132" 56 TOTAL BODY 2

Change "6.10El to "6.10E-1" 57 GI-LLI 16 Change "9.'llE4" to "9.11E-4" 58 TOTAL BODY 25 Change "6.38ES" to "6.38E5" 58 GI-LLI 25 Change "5.79ES" to "5.79E5" 59 KIDNEY 5

Change "1.70ES" to "1.70ES" 91 Change units for columns labeled "X/Q -

Decayed /Undepleted" and "X/Q -

Decgyed/ Depleted" from 3

"(m /sec)" to " (sec/m ) ".

92 Same change as on page 91.

pli

.a +..

+

R3v. 2 i

TABLE 6 (Continued) s RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM d

isotopic analysis on those samples for which the gross beta activity is > 10 times the yearly mean of control samples.

Perform I

gamma isotopic analysid on composite samples (by location) at least once per 92 days.

Station Code Sector Site Description Location t-Cu A-1 D

Primary Meteorological Tower 1.3 mi. 9 76 ENE A-8 B

County Road 448, 0.9 mi.

.9 mi. 9 20 NNE South of Highway 0 B-3 A

0.6 mile east of Highway O 1.9 mi. 9 355 N

and CC Junction One sample from the community with the highest D/Q A-9 R

community of Reform 1.7 mi. 9 336 NNW One sample from a control location, as for example 15-30 km distant and in the least prevalent wind direction.

9.5 mi. 9 312 NW A-7 Q

C.

Bartley Farm

~

l AWI - 4 L M) 1)l NNE NE

~ENE N

NW NN 4

REFORM g

7 f

VA A-h46 N

se A-8 R STRICTED AREA BOUNDARY WNW 47 (SITE BOUNDARY FOR GASEOUS EFFLUENTS A-1 45 m

_48 35 -

I g

1

-f

/

4

/1, Rawx I

j WSW l

l e50

/

/

I/ 78 ESE SW COUNTY R D. 4 5 9

.- R AILRO AO

/

SPUR

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1 l

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PORTLAND (STEEOMANf,

')/

l SSW

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8 3

20.00 0

2000 UNION ELECTRIC CO.

FEET SSE C ALL AWAY PL ANT LEGEND:

5 MILE RAOlus AIRBORNK & TLD S AMPLING NETWORK O TLD LOCATION A AIR SAMPLER LOCATION L3 TLD & AIR S AMPLER LOC ATION FIG U R E 8,18 REV 2

w w n n ~

- ~

. _ =.

Rnv. 3 1

i UNION ELECTRIC COMPANY CALLAWAY PLANT OFFSITE DOSE CALCULATION MMsUAL i

Approved:

N'* [ /IL6 Q4

/NY /- 8 4 4/ I3 G U

v Chairman, CRC

/ /

Date ORC meeting number Reviewed:

\\M2

? [1[#

m Superintgeht, Hhalth Physics D'ats

[1 k~

7/dG5 Reviewed:

Supergipdr,H.P. Tech. Support Udte Prepared By:

M4""*

7fIlOf Date

... i t 3,,

v w_ ; -- o.._ %.

..._...,...,_..,.,.1...,,...,,,,,.,%.

1 R v. 3 i

This document contains the following:

Pages

'l through 102 Tables 1

through 12 Figures 4.1, 5.1A, 5.1B, 5.2A, 5.2B, 5.3 r

Sbd l ' d

..'h a.-

Rev. 3 Table of Contents Page 1.0 PURPOSE AND SCOPE 1

2.0 LIQUID EFFLUENTS 2

2.1 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION 3.3.3.10 2

2.2 LIQUID EFFLUENT MONITORS 2

2.2.1 Continuous Liquid Effluent Monitors 4

2.2.2 Radioactive Liquid Batch Release Effluent Monitors 5

2.3 ODCM METHODOLOGY FOR THE DETERMIN-ATION OF LIQUID EFFLUENT MONITOR SETPOINTS 6

2.3.1 Development of ODCM Methodology for the Determination of Liquid Effluent Monitor Setpoints 6

2.3.2 Summary, Setpoint Determination Methodology for Liquid Effluent Monitors 12 2.4 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS 12 2.4.1 Radiological Effluent Technical Specification 3.11.1.1 12 2.4.2 Liquid Effluent Concentration Measurements 12 2.5 INDIVIDUAL DOSE DUE TO LIQUID EFFLUENTS 13 2.5.1 Radiological Effluent Technical Specification 3.11.1.2 13 2.5.2 The Maximum Exposed Individual 13 2.5.3 ODCM Methodology for Determining Dose contributions from Liquid Effluents 13

-i-A1 a

Rnv. 3 Tabln of Contentn (continued)

Page 2.5.3.1 Calculation of Dose Contributions 13 2.5.3.2 Dose Factor Related to Liquid Effluents 15 2.5.4 Summary, Determination of Individ-ual Dose Due to Liquid Effluents 17 2.6 LIQUID RADWASTE TREATMENT SYSTEM 21 2.6.1 Radiological Effluent Technical Specification 3.11.1.3 21 2.6.2 Description of the Liquid Radwaste Treatment System 21 2.6.3 Operability of the Liquid Radwaste Treatment System 21 3.0 GASEOUS EFFLUENTS 22 3.1 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION 3.3.3.11 22 3.2 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION 3.11.2.1 22 3.3 GASEOUS EFFLUENT MONITORS 22 3.3.1 Continuous Release Gaseous Effluent Monitors 23 3.3.2 Batch Release Gaseous Monitors 25 3.4 ODCM METHODOLOGY FOR THE DETERMIN-ATION OF GASEOUS EFFLUENT MONITOR SETPOINTS 26 3.4.1 Development of ODCM Methodology for the Determination of Gaseous Effluent Monitor Setpoints 26 3.4.1.1 Total Body Dose Rate Setpoint Calculations 26 3.4.1.2 Skin Dose Rate Setpoint Calculation 28 3.4.1.3 Gaseous Effluent Monitors Setpoint Determination 29 <

R7v. 3 Tablo of Contents (continund)

Page 3.4.2 Summary, Gaseous Effluent Monitors Setpoint Determination 31 3.5 ODCM METHODOLOGY FOR DETERMINING DOSE CONTRIBUTIONS FROM GASEOUS EFFLUENTS 31 3.5.1 Determination of Dose Rate 31 3.5.1.1 Noble Gases 31 3.5.1.2

. Radionuclides Other Than Noble Gases 32 3.5.2 Individual Dose Due to Noble Gases 38 3.5.2.1 Radiological Effluent Technical Specification 3.11.2.2 38 3.5.2.1.1 Noble Gases 38 3.5.2.2 Radiological Effluent Technical 5

Specification 3.11.2.3 39 3.5.2.2.1 Radionuclides Other Than Noble Gases 40 3.6 GASEOUS RADWASTE TREATMENT SYSTEM 61 3.6.1 Radiological Effluent Technical Specification 3.11.2.4 61 3.6.2 Description of the Gaseous Radwaste Treatment System 61 3.6.3 Operability of the Gaseous Radwaste Treatment System 61 4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 62 4.1 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION 3.11.4 62 4.2 CDCM METHODOLOGY FOR DETERMINING DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 62 4.2.1 Identification of the MEMBER 63 OF THE PUBLIC r

-lii-

..,m

.,...,......,1

Rcv. 3 Tablo of Contents (continund)

Page 4.2.1.1 Utilization of Areas Within the SITE BOUNDARY 63 4.2.2 Total Dose From Gaseous Effluents 64 4.2.3 Total Dose From Direct Radiation 64 4.2.3.1 Direct Radiation From outside Storage Tanks 64 4.2.3.2 Direct Radiation From the Reactor 67 5.O RADIOLOGICAL ENVIRONMENTAL 68 MONITORING l

l 5.1 RADIOLOGICAL EFFLUENT TECENICAL SPECIFICATION 3.12.1 68

5.2 DESCRIPTION

OF THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 68 6.0 DETERMINATION OF ANNUAL AVERAGE

\\

AND SHORT TERM ATMOSPHERE DISPERSION PARAMETERS 84 6.1 ATMOSPHERE DISPERSION PARAMETERS 84 6.1.1 Long Term Dispersion Estimates 84 6.1.1.1 The PUFF Model 84 6.1.1.2 The Straight-Line Gaussian Diffusion Model 85 6.1.1.2.1 Mixed Mode and Elevated Release Model 86 6.1.1.2.2 Gound-Level Release Model 86 6.1.1.2.3 Decay, Depletion, and Deposition Methodology 87 1

6.1.2 Short Term Dispersion Estimates 88 6.1.2.1 The Determination of the Slope Factor (S) 90 i

7.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 94

-iv-w g,..,,

.,_.y-,..,

...,...... s,3

RT,v. 3 Tablo of Contsnts (continusd)

Page 8.0 IMPLEMENTATION OF ODCM METHODOLOGY 96

9.0 REFERENCES

97

-V-a; ' ' ' '

Rnv. 3 List of Figures Figure 4.1 Site Area Closed to Public Use Figure 5.1A Airborne & TLD Sampling Network Figure 5.1B Airborne & TLD Sampling Network Figure 5.2A Location of Aquatic Sampling Stations Figure 5.2B Location of Aquatic Sampling Stations Figure 5.3 Food Products Sampling Locations i

1 i

l l

-vi-

>:l_

R2v. 3 List of Tables Page Table 1 Ingestion Dose Commitment Factor (Ag) for Adult Age Group 18 Table 2 Bioaccumulation Factor (BF.) Used in the Absence of Site-Spedific Data 20 Table 3 Dose Factors for Exposure to A Semi-Infinite Cloud of Noble Gases 30 Table 4 Dose Parameter (P4) for Radio-nuclides Other Than Noble Gases 35 Table 5 Pathway Dose Factors (R.) for Radionuclides Other Thah Noble Gases 43 Table 6 Radiological Environmental Monitoring Program 69 Table 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples 80 Table 8 Maximum Values for the Lower Limits of Detection 81 Table 9 Highest Annual Average Atmospheric Dispersion Parameters - Radwaste Building Vent 90 Table 10 Highest Annual Average Atmospheric Dispersion Parameters - Unit Vent 91 l

Table 11 Short Term Dispersion Parameters 92 Table 12 Application of Atmospheric Dispersion Parameters 93 i

-vii-

R7v. 3 Record of Revisions Revision Number Date Reason for Revision Rev. O March 1983 Rev. 1 November 1983 Revised to support the current RETS submittal and to incorporate NRC Staff comments Rev. 2-March 1984 Revised to incorporate NRC Staff comments

! Rev. 3 June 1985 Revised to incorporate errata identified by ULNRC-803 and changes to the Environmental Monitoring Program.

Incorporate results of 1984 I

Land use Census.

-viii-

. m.

- ~J~.&

A bis O~

m z, _ - _- a i.

R".v.

3 I

c = A {(C9)g pCi (Refer to Note (2.9)

"1 Following)

Where:

A=

Adjustment factor which will allow the set-point to be established in a practical manner for convenience and to prevent spurious alarms.

A=Imax (Refer to Note (2.10) f Following) p If A > 1: Calculate c and' determine the maximum value g

for the actual monitor setpoint (pci/ml).

If A i 1:No release may be made.

This condition must be flagged and the operator instructed to re-evaluate F and F (i.e., reduce effluent flow rate hE retur$ffadwaste for reprocessing).

NOTE If Fa < 1, no further dilution is required and the releIse may be made without regard to available dilu-tion or to other releases made simultaneously.

How-ever, it is necessary to establish a monitor setpoint which will provide alarm should the release concentra-tion inadvertently exceed Radiological Effluent Techni-cal Specification 3.11.1.1 limits.

This can be accom-plished by establishing the adjustment factor as follows:

i i

I 1

l A=7 (2,11) d i

i l '

T: ~A

- ~__

Rev. 3 Dose contributions from liquids discharged as conti-nuous releases are determined by utilizing the last measured values of samples required in accordance with Radiological Effluent Technical Specifications Table 4.11-1.

2.5 Individual Dose Due to Liquid Effluents 2.5.1 Radiological Effluent Technical Specification 3.11.1.2 I The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents

! released, to UNRESTRICTED AREAS shall be limited:

During any calendar quarter to less than or equal a.

I to 1.5 mrem to the whole body and less than or equal to 5 mrem to any organ, and b.

During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

2.5.2 The Maximum Exposed Individual The cumulative dose determination considers the dose contributions from the maximum exposed individual's consumption of fish and potable water, as appropriate.

Normally, the adult is considered to be the maximum ex-posed individual.

(Ref. 9.8.3, 9.8.4)

The Callaway Plant's liquid effluents are discharged to the Missouri River.

As there are no potable water in-takes within 50 miles of the discharge point (Ref.

9.7.1, 9.6.6), this pathway does not require routine evaluation.

There fore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dose from discharges to the Missouri River.

Dose from recreational activities is expected i

to contribute the additional 5%, which is considered to be negligible.

(Ref. 9.6.7)

Thus, the maximum exposed individual is an adult, receiving 95% of the total dose from eating fish and 5%

of the total dose.from recreational activities.

2.5.3 ODCM Methodology for Determining Dose Contributions From Liquid Effluents i

2.5.3.1 Calculation of Dose contributions 1

The dose contributions for the total time period.L L

Rnv. 3 Inserting the appropriate usage factors from Regulatory Guide 1.109 into Equation (2.14) yields the following expression:

A

= 1.14E05 (21BF )DF (2.15) g g

g or Agz = 2.39E06 x BF4 f

(2.16) x DF 2.5.4 Summary, Determination of Individual Dose Due to Liquid Effluents The dose contribution for the total time period m

Iatg t=1 is determined by calculation at least once per 31 days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter.

The projected dose contribution from batch releases for which radionuclide concentrations are determined by periodic composite and grab sample analysis, as stated in Table 4.11-1 of the Radiological Effluent Technical Specifications, may be approximated by using the last measured value.

However, for reporting purposes, the calculated dose contribution from those radionuclides is based on actual composite / grab sample analysis.

Dose contributions are determined for all radionuclides identified in liquid effluents released to UNRESTRICTED

! AREAS.

Nuclides which are not detected in the analyses are reported as "less than" the nuclide's Minimum Detectable Activity (MDA) and are not reported as being present at the LLD level for that nuclide.

The "less than" values are not used in the required dose calculations.

i i

17 -

4

AW e cM *.Daaf

'4

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• * "

• I

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N 8 '% t* O89889 M'

Rcv. 3 TABLE 1 INGESTION DOSE COMMITMENT FACTOR (Ag) FOR ADULT AGE GROUP (mrem-hr per pci-ml)

! Total

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

! H-3

!No Data 12.26E-01 12.26E-01!2.26E-01 !2.26E-01!2.26E-Ol!2.26E-Ol!

! C-14

!3.13E+04!6.26E+03 !6.26E+03!6.26E+03 !6.26E+03!6.26E+03!6.26E+03!

! Nc-24 14.07E+02!4.07E+02 !4.07E+02!4.07E+02 14.07E+02!4.07E+02!4.07E+02!

! P-32 14.62E+07!2.87E+06 11.78E+06tNo Data

!No Data !No Data 15.19E+06!

! Cr-51 !No D6ta !No Data

!1.27E+00!7.62E-01 12.81-01 II.69E+00!3.2-E+02!

! Mn-54 !No Data !4.38E+03 18.35E+02fNo Data

!1.30E+03!No Data ll.34E+04!

! Mn-56 !No Data ll.10E+02 !1.95E+0l!No Data ll.40E+02!No Data !3.52E+03!

! Fc-55 16.57E+02!4.54E+02 !1.06E+02!No Data

!No Data !2.53E+02!2.61E+02!

! Fo-59 11.04E+03!2.44E+03 19.34E+02tNo Data

!No Data !6.81E+02!8.13E+03!

! Co-58 !No Data !8.94E+01 12.00E+02!No Data

!No Data !No Data !1.81E+03!

! Co-60 INo Data 12.57E+02 15.66E+02tNo Data

!No Data !No Data 14.82E+03!

! Ni-63 !3.11E+04!2.15E+03 11.04E+03!No Data

!No Data INo Data 14.49E+02!

! Ni-65 !1.26E+02!1.64E+01 17.48E+00!No Data

!No Data !No Data 14.16E+02!

! Cu-64 INO Data fl.00E+01 !4.69E+00!No Data

!2.52E+01!No Data !8.52E+02!

! Zn-@S 12.32E+04!7.38E+04 !3.33E+04tNo Data 14.93E+04!No Data !4.65E+04!

! Zn-69 14.93E+0l!9.44E+01 16.56E+00!No Data 16.13E+0l!No Data fl.42E+01!

! Br-83 !No Data !No Data

!4.04E+0l!No Data

!No Data !No Data 15.81E+01!

! Br-84 INo Data !No Data 15.26E+01tNo Data

!No Data !No Data 14.13E-04!

! ! Br-85 !No Data !No Data 12.15E+00!No Data

!No Data !No Data !

0

! Rb-86 !No Data fl.01E+05 14.71E+04!No Data

!No Data !No Data ll.99E+04!

! Rb-88 !No Data !2.90E+02 !1.54E+02!No Data

!No Data !No Data !4.00E-09?

! Rb-89 !No Data fl.92E+02 !1.35E+02tNo Data

!No Data !No Data 11.12E-l*!

! Sr-89 !2.21E+04tNo Data

!6.35E+02!No Data

!No Data !No Data !3.55E+03!

Sr-90 !5.44E+05fNo Data 11.34E+05tNo Data

!No Data !No Data !1.57E+04!

! Sr-91 14.07E+02!No Data fl.64E+01!No Data

!No Data !No Data !1.94E+03!

! Sr-92 !1.54E+02!No Data

!6.68E+00!No Data

!No Data !No Data !3.06E+03'

! Y-90 f5.75E-Ol!No Data 11.54E-02!No Data

!No Data !No Data 16.10E+03!

! Y-91M !5.44E-03!No Data 12.10E-04!No Data

!No Data !No Data !1.60E-02!

! Y-91

!8.43E+00!No Data 12.25E-01!No Data INo Data !No Data !4.64E+03!

! Y-92

!5.05E-02!No Data 11.48E-03tNo Data

!No Data !No Data 18.85E+02 !

it ! Y-93

!1.60E-Ol!No Data

!4.42E-03tNo Data INo Data INo Data 15.08E+03!

! Zr-95 !2.40E-01!7.70E-02 !5.21E-02tNo Data ll.21E-Ol!No Data !2.44E+02!

! Zr-97 !1.33E-02!2.68E-03 11.22E-03tNo Data 14.04E-03!No Data 18.30E+02!

! Nb-95 14.47E+02!2.48E+02 11.34E+02tNo Data 12.46E+02tNo Data 11.51E+06!

! Mo-99 INo Data !1.03E+02 11.96E+01!No Data 12.33E+02tNo Data !2.39E+0;!

! Tc-99Mf8.87E-03!2.51E-02 13.19E-Ol!No Data

13. 81E-01 ! 1. 23 E-02 ! 1. 48E+0 * !

! ! Tc-10l!9.11E-03!1.31E-02 11.29E-Ol!No Data 12.36E-01!6.70E-03!

0

! Ru-103!4.42E+00!No Data fl.90E+00!No Data ll.69E+0l!No Data !5.17E+01!

! Ru-105!3.68E-01tNo Data ll.45E-01tNo Data 14.76E+00!No Data !2.2SE+02!

! Ru-106!6.57E+01!No Data 18.32E+00!No Data 11.27E+02tNo Data 14.25E*03! l l

6_ _ -

,;.w

...mm

Rcv. 3 j

TABLE 1 (Continued)

INGESTION DOSE COMMITMENT FACTOR (Ag) FOR ADULT AGE GROUP i

l (mrem-hr per pei-ml)

! Total i

!Nuclide! Bone Liver Body

! Thyroid ! Kidney !

Luno

! GI-LLI !

}

}

!To-125M!2.57E+03!9.30E+02 13.44E+02!7.72E+02 !1.04E+04tNo Data 11.02E+04!

l

!Ta-127M!6.47E+03!2.32E+03 !7.90E+02!1.66E+03 !2.63E+04!No Data !2.17E+04!

i t

!Te-127 11.05E+02!3.78E+01 12.28E+01!7.80E+01 !4.29E+02tNo Data 18.30E+03!

!To-129M!1.10E+04!4.11E+03 11.74E+03!3.78E+03 14.60E+04!No Data 15.54E+04!

!Te-129 13.01E+01!1.13E+01 17.33E+00!2.31E+01 11.26E+02tNo Data 12.27E+01!

!Te-131M!1.66E+03!8.09E+02 16.75E+02!1.28E+03 18.21E+03tNo Data 18.03E+04!

}

!Te-131 11.89E+01!7.88E+00 15.96E+00!1.55E+01 !8.25E+011No Data 12.67E+00!

i ITo-132 !2.41E+03!1.56E+03 11.47E+03!1.72E+03 11.50E+04tNo Data 17.38E+04!

l 1

11-130

!2.71E+01!8.01E+01 !3.16E+01!6.79E+03 11.2SE+02tNo Data !6.89E+01!

II-131

!1.49E+02!2.14E*02 11.22E+02!7.00E+04 13.66E+02tNo Data 15.64E+01!

1 11-132 17.29E+00!1.95E+01 16.82E+00!6.82E+02 13.11E+0i!No Data 13.66E+00!

!I-133

!5.10E+01!8.87E+01 12.70E+01!1.30E+04 11.55E+02fNo Data !7.97E+01!

!I-134 13.81E+00!1.03E+01 !3.70E+00!1.79E+02 !1.64E+01tNo Data 19.01E-03!

l i

II-135 11.59E+01!4.16E+01 11.54E+01!2.75E+03 !6.68E+01!No Data !4.70E+01!

i

!Cs-134 12.98E+05!7.09E+05 !5.80E+05!No Data 12.29E+05!7.62E+04!1.24E+04!

l

!Cs-136 13.12E+04!1.23E+05 18.86E+04!No Data 16.85E+04!9.39E+03!1.40E+04!

!Cs-137 !3.82E+05!5.22E+05 !3.42E+05!No Data

11. 77E+05 ! 5. 89E +04 ! 1. 01E+04 !

!Co-138 !2.64E+02!5.22E+02 12.59E+02tNo Data

13. 84E+02 ! 3. 79E+01'! 2. 2 3E-03 !

IBa-139 19.29E-01!6.62E-04 !2.72E-02!No Data

!6.19E-04!3.76E-04!1.65E+0C!

!Ba-140 !1.94E+02!2.44E-01 !1.27E+01!No Data

! 8. 31E-02 !1. 40E-01! 4. 00E+02 !

!! !Ba-141 14.50E-01!3.40E-04 11.52E-02tNo Data 13.16E-04 ! 1. 93 E-04 ! 2.12E-10 !

!! IBa-142 12.04E-01!2.09E-04 11.28E-02tNo Data 11.77E-04!1.19E-04!

0 l

j

!La-140 !1.50E-01!7.53E-02 11.99E-02tNo Data

!No Data !No Data 15.53E+02!

i

'l

!La-142 17.65E-03!3.48E-03 !8.66E-04!No Data INo Data !No Data 12. 54E+01'

!Co-141 12.24E-02!1.51E-02 11.72E-03!No Data 17.03E-03!No Data 15.78E+0*!

t ICc-143 13.94E-03!2.92E+00 13.23E-04tNo Data 11.28E-03fNo Data 11.09E+01!

!Co-144 11.17E+00!4.88E-01 16.26E-02!No Data 12.89E-01!No Data 13.94E+02 !

!Pr-143 15.50E-01!2.21E-01 12.73E-02fNo Data 11.27E-011No Data 12.41E+02!

+

!Nd-147 !3.76E-01!4.35E-01 !2.60E-02tNo Data

!2.54E-01!No Data !2. 09E+03 '

[

!W-187

!2.96E+02!2.47E+02 18,64E+01tNo Data

!No Data !No Data 18.09E+04 !

l 1

{

INp-239 12.84E-02!2.80E-03 !1.34E-03!No Data 18.72E-03tNo Data !$.74E+01!

(

1 I

l i !

,w ~ -.

A..cs R ' M - n n=u m.a a

_ _v. v, -

R^.v. 3 2.6 LIQUID RADWASTE TREATMENT SYSTEM 2.6.1 Radiological Effluent Technical Specification 3.11.1.3 The LIQUID RADWASTE TREATMENT SYSTEM Shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivty when the projected I doses due to the liquid effluent, to UNRESTRICTED AREAS, would exceed 0.06 mrem to the total body or 0.2 mrem tg any organ in a 31 day period.

2.6.2 Description Of The LIQUID RADWASTE TREATMENT SYSTEM 2.6.3 OPERABILITY Of The LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is capable of varying treatment, depending on waste type and product desired.

It is capable of concentrating, gas strip-ping, and distillation of liquid wastes through the use of the evaporator system.

The demineralization system is capable of removing radioactive ions from solutions to be reused as makeup water.

Filtration is performed on certain liquid wastes and it may, in some cases, be the only required treatment prior to release.

The sys-tem has the ability to absorb halides through the use of charcoal filters prior to their release.

The design and operation requirements of the LIQUID RADWASTE TREATMENT SYSTEM provide assurance that releases 'of radioactive materials in liquid effluents will be kept "As Low As Reasonably Achievable" (ALARA).

The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensuren this system will be available for use when liquids require treatment prior to their release to the environment.

OPERABILITY is demonstrated through com-pliance with Radiological Effluent Technical Specifica-tions 3.11.1.1 and 3.11.1.2. l i

I.

R v.

3 D

={Pg[(X/Q)Q ] < 1500 mrem /yr (3.7) o i

1 Where:

Dose rate to any critical organ, in (mrem /yr).

D

=

g Dose parameter for radionuclides other than P

=

4 noble gases for the inhalation pathway for the child, based on the critical organ, in (mrem /yr) per (pCi/m ).

(Table 4) a Q.=

The-release rate of radionuclide, i, in 1

gaseous effluents, from all vent releases, in (pci/sec).

Q. is calculated as the product of the ventilatibn path design flow rate and the measured activity of the effluent stream as determined by grab sampling.

Flow rates for the ventilation pathways can be found in ref-erences 9.6.21,-9.6.22, 9.6.23, and 9.6.24.

(X/Q) is as previously' defined.

The dose parameter (P ) includes the internal dosimetry of radionuclidel, i, abd the receptor's breathing rate, which are functions of the receptor's age.

Therefore the child age group has been selected as the limiting age group.

For the child exposure, separate values of Pa are tabu-lated in Table 4 for the inhalation pathway." These values were calculated according to (Ref. 9.8.9):

i.

Pg = K' (BR) DFA (3.8)

+

i Where:

Units conversion factor: 1pCi = 1E06 pCi.

K'

=

- 33

x;r:

m : >-,mnv ~+4+ na*dehui$b;$M%4,e-+xww v

~-r. e :;..yx. a

Rnv. 3 3.5.2 Individual Dose Due To Gaseous Effluents i

3.5.2.1 Radiological Effluent Technical Specification 3.11.2.2 The air dose due to noble gases released in gaseous ef-

! fluents, to areas at and beyond the SITE BOUNDARY shall be limited to the fellowing:

a.

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

1 1

3.5.2.1.1 Noble Gases The air dose at the SITE BOUNDARY due to noble gases released from the site is determined according to the following methodology (Ref. 9.8.10 ):

't t

During any calendar quarter, for gamma radiation:

D

= 3.17 E-08 I [Mg {(X/Q) Qg + (X/q) q }] $5 mrad (3.9) g g

During any calendar quarter, for beta radiation:

D

= 3.17 E-08 I [Ng {(X/Q) Qg + (X/q) qf}] 5 10 mrad (3.10) b 1

During any calendar year, for gamma radiation:

D

= 3.17 E-08 I [Mg {(X/Q) Qg + (X/q) q }] 1 10 mrad (3.11) g g

1 tf

\\r During any calendar year, for beta radiation:

D

= 3.17 E-08 I [Ng {(X/Q) Qi + (X/q) qi}] 1 20 mrad (3.12) b

, t 1

t.

4 I i.

l (b

'L1

+...

sw.. L; - - i

Rtv. 3 Where:

Air dose from gamma radiation due to noble D

=

9

-gases released in gaseous effluent.

D3 =-

Air dose from beta radiation due to' noble gases released in gaseous effluents.

(X/q) =

The relative concentration for areas at or beyond the SITE BOUNDARY for short-term i

releases (equal to or less than 500 hrs / year).

Refer to Tables 9, 10, 11, and 12.

q. =

The average release of noble gas radionu-1 clides, i, in gaseous effluents from all vent releases for short-term releases (equal to or j

less than 500 hrs / year), in (pCi).

Releases are cumulative over the calendar quarter or year, as appropriate.

The air dose factor due to beta emissions for N. =

1 each identified noble gas radionuclide, i, in (mrad /yr) per (pci/m3). (Table 3 )

Q. =

The average release of noble gas radion~u-1 clides, i, in gaseous effluents from all vent releases for long-term releases (greater than 500 hrs / year), in (pCi).

Releases are cumula-tive over the calendar quarter or year, as i

appropriate.

The highest calculated annual average relative (X/Q)

=

concentration for areas at or beyond the SITE BOUNDARY for long-term releases (greater than 500 hrs /yr).

Refer to Tables 9,

10, and 12.

3.17E-08 = The inverse of the number of seconds per year.

M is as previously defined. (Refer to Section 3.4.1.2) g 3.5.2.2 Radiological Effluent Technical Specification 3.11.2.3

! The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef-

! fluents released, to areas at and beyond the SITE BOUN-DARY shall be limited to the following (Ref. 9.8.10):

a.

During any calendar quarter:

Less than or equal to 7.5 mrem to any organ and, l W.f, :.2..x 7..,-.

a~~,esb.k.y;lsbyhbMbh+ ::

3mmm.

R v. 3 b.

During any calcndar year:

Lose thtn or cqual to 15 mrem to any organ.

3.5.2.2.1 Radionuclides Other Than Noble Cases

! The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef-t fluents released, to areas at and beyond the SITE BOUN-DARY, is determined according to the following expressions:

During any calendar quarter:

Dg = 3.17E-08 I Rg [W Qg + w g ] 5 7.5 mrem (3.13) g i

During any calendar year:

Dg = 3.17E-08 I Rg [W Qg + w q ] 1 15 mrem (3.14) g 1

I Where:

i Dose to a MEMBER OF THE PUBLIC from radionu-l

! D. =

l 1

clides other than noble gases.

Q. =

The releases of radionuclides, radioactive 1

materials in particulate form, and radionu-clides other than noble gases, i, in gaseous effluents, for all vent releases for long-term releases (greater than 500 hrs /yr), in (pCi).

Releases are cumulative over the calendar quarter or year as appropriate.

l

q. =

The releases of radionuclides, radioactive 1

j materials in particulate form and radionu-clides other than noble gases, i, in gaseous effluents for all vent releases for short-term releases (equal to or less than 500 hrs /yr),

in (pCi).

Releases are cumulative over the calendar quarter or year as appropriate.

The dose factor for each identified radionu-R.

=

1 clide, i, in m2(mrem /yr) per (pci/sec) or (mrem /yr) per (pci/m3). (Table 5) l I

40 -

l

''84 9 ir 7 h \\*a OM

f =* k*h b 31F= h W.*$!

I N 98 00 0 8%

II M

MdMM dig,

Rtv. 3 i

W=

The dispersion parameter for estimating the dose'to an' individual at the controlling loca-tion for long-term releases (greater than 500 hrs /yr):

I W=

(X/Q) for the inhalation and tritium pathways, in(sec/m3).

1 W= (D/Q) for the food and ground plane

]

pathways, in(meters 2),

i Refer to Tables 9, 10, and 12.

The dispersion parameter for estimating the w=

dose to an individual at the controlling loca-tion for short-term releases (equal to or less than 500 hrs /yr):

w = (X/q) for the inhalation pathway, in(sec/m3)

I w = (D/q) for the food and ground plane pathway, in (meters 2).

Refer to Tables 9, 10, 11, and 12.

% 3.17 E-08

= The inverse of the number of seconds per year.

(D/g)' =

the average relative deposition of the ef-l fluent at or beyond the SITE BOUNDARY, consid-ering depletion of the plume during transport, for long term releases igreater than t

500 hrs /yr), in (meters 2).

! (D/q) =

the relative deposition of the effluent at or j

beyond the SITE BOUNDARY, considering deple-tion of the plume during transport, for'short term releases (less than or equal to 500 hrs /yr), in (meters 2).

l Note:

For the direction sectors with existing pathways within 5 miles from the site, the appropriate R values 4

I are used.

If no real pathway exists within 5 miles i

from the center of the building complex, the cow-milk i

R. value is used, and it is assumed that this pathway

+

l elists at the 4.5 to 5.0 mile distance in the limiting-case sector.

If the R for an existing pathway within 4

5 miles is less than a*ccw-milk R at 4. 5 to 5. 0 miles,

i then the value of the cow-milk ~R at 4.5 to 5.0 miles g

is used. (Rev. 9.8.10.)

Although the annual average relative concentration (X/Q) and the average relative deposition rate (D/Q).

T 4.

P u;bp%UDEMUA#d11:diW h a.- C.S -

e

,a.m.,m.

._,.a--.,

Rev. 3 TABLE 5-(Contd.)

PATHWAY DOSE FACTORS (Rg ) FOR RADIONUCI. IDES OTHER THAN NOBLE GASES Ground Plane Pathway (M2 mrem /yr) per (pci/sec)

Nuclide Total Body Skin Na-24 1.19E7 1.39E7 Cr-51 4.65E6 5.51E6 Mn-54 1.39E9 1.63E9 Mn-56 9.03E5 1.07E6 Fe-59 2.72E8 3.20E8 Co-58 3.79E8 4.44E8 Co-60 2.15E10 2.53E10 Ni-65 2.97E5 3.45ES Cu-64 6.07E5 6.88E5 Zn-65 7.47E8 8.59E8 Br-83 4.87E3 7.08E3 Br-84 2.03E5 2.36ES Rb-86 8.99E6 1.03E7 Rb-88 3.31E4 3.78E4 Rb-89 1.23E5 1.48E5 Sr-89 2.16E4 2.51E4 Sr-91 2.15E6 2.51E6 Sr-92 7.77E5 8.63E5 Y-90 4.49E3 5.31E3 Y-91m 1.00E5 1.16E5 Y-91 1.07E6 1.21E6 Y-92 1.80E5 2.14E5 Y-93 1.83E5 2.51E5 Zr-95 2.45E8 2.84E8 Zr-97 2.96E6 3.44E6 Nb-95 1.37E8 1.61E8 Mo-99 3.98EG 4.62E6 Tc-99m 1.84E5 2.11ES Tc-101 2.04E4 2.26E4 Ru-103 1.08E8 1.26E8 Ru-105 6.36E5 7.21ES Ru-106 4.22E8 5.07E8 Ag-110m 3.44E9 4.01E9 Te-125m 1.55E6 2.13E6 Te-127m 9.16E4 1.08E5..~;,1;. k.1.R$i:

g;.w,y.gg

Rtv. 3 TABLE 5 (Contd.)

Ground Plane Pathway (M2 mrem /yr) per (pci/sec)

Nuclide Total Body Skin Te-127 2.98E3 3.28E3 Te-129m 1.98E7 2.31E7 Te-129 2.62E4 3.10E4 Te-131m 8.03E6 9.46E6 i

Te-131 2.92E4 3.45E4 Te-132 4.23E6 4.98E6 I-130 5.51E6 6.69E6 I-131 1.72E7 2.09E7 I-132 1.23E6 1.45E6 I-133 2.45E6 2.98E6 I-134 4.47E5 5.30E5 I-135 2.51E6 2.93E6 Cs-134 6.86E9 8.00E9 Cs-136 1.53E8 1.74E0 Cs-137 1.03E10 1.20E10 Cs-138 3.59E5 4.10E5 Ba-139 1.06E5 1.19E5 Ba-140 2.05E7 2.35E7 Ba-141 4.15E4 4.73E4 Ba-142 4.44E4 5.06E4 La-140 1.92E7 2.18E7 La-142 7.40E5 8.89E5 Ce-141 -

1.37E7 1.54E7 Ce-143 2.31E6 2.63E6 Ce-144 6.96E7 8.04E7 Pr-144 1.84E3 2.11E3 l

Nd-147 8.41E6 1.01E7 W-187 2.36E6 2.74E6 Np-239 1.71E6 1.98E6 i

i,

.. a i...La,d fdE,i, ~.;Misr.i w $ M % : w sc:. w ; v.s + _ %,c a. ; y e

Rov. 3 TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway-(m2 mrem /yr) per (pCi/sec)

! Total

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

! H-3 ND 11.57E3 11.57E3

!1.57E3 11.57E3 11.57E3

!1.57E3

! C-14

!1.19E9 12.39E8 12.39E8

!2.39E8 12.39E8 12.39E8

!2.39E8

! Na-24 !8.89E6

!8.89E6 18.89E6

!8.89E6

!8.89E6

!8.89E6 18.89E6

! P-32

!7.77E10 !3.64E9 13.00E9 ND ND ND 12.15E9

! Cr-51 !

ND ND

!1.03E5 15.65E4

!1.56E4

!1.04E5 15.40E6 I

! Mn-54 !

ND

!2.10E7 15.59E6 ND

!5.88E6 ND 11.76E7

! Mn-56 !

ND 11.29E-2 12.90E-3 !

ND

!1.56E-2 !

ND

!1.86E0

! Fe-55 11.12E8 15.93E7 11.84E7 ND ND

!3.35E7 11.10E7

! Fe-59 11.20E8

!1.94E8

!9.69E7 ND ND

!S.64E7

!2.02E8

! Co-58 !

ND 11.21E7 13.71E7 ND ND ND

!7.07E7

! Co-60 !

ND 14.32E7

!1.27E8 ND ND ND

!2.39E8

! Ni-08 12.69E10 !1.59E9 11.01E9 ND ND ND

!1.07E8

! Ni-65 11.66E0

!1.56E-1

!9.01E-2 !

ND ND ND

!1.91El

! Cu-64 !

ND

!7.46E4 14.51E4 ND

!1.80E5 ND

!3.50E6

! Zn-65 !4.13E9 11.10E10

!6.85E9 ND 16.94E9 ND

!1.93E9

! ! Zn-69 !

0 0

0 ND 0

ND

!1.12E-9 !

! Br-83 !

ND ND ND ND ND ND ND

! Br-84 !

ND ND ND ND ND ND ND i

! Br-85 !

ND ND ND ND ND ND ND 1

! Rb-86 !

ND

!8.80E9

!5.41E9 ND ND ND

!S.66E8

! Rb-88 !

ND 0

0 ND ND ND 0

! Rb-89 !

ND 0

0 ND ND ND 0

! Sr-89 !6.62E9 ND

!1.89E8 ND ND ND

!2.56E8

! Sr-90 !1.12E11 !

ND

!2.83E10 !

ND ND ND

!1.51E9

! Sr-91 !1.30E5 ND

!4.92E3 ND ND ND

!2,8BE5 51 -

..m.m......e,2..a.;.Sa Li W e 4. w % w : e w --, e,,- -c _ _:7,

i Rcv. 3 l

TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Cow-Milk Pathway (m2 mrem /yr) per (pCi/sec) l'

! Total i

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

! Sr-92 12.18E0 ND

!8.75E-2 1 ND ND ND 14.13E1

! Y-90 13.22E2 ND

!8.62E0 ND ND ND 19.17ES

! Y-91m !

0 ND 0

ND ND ND 0

! Y-91

!3.90E4 ND

!1.04E3 ND ND ND 15.20E6

! Y-92

!2.53E-4 !

ND 17.24E-6 !

ND ND ND 17.31E0

! Y-93

!1.05EO ND 12.90E-2 !

ND ND ND 11.57E4

! Zr-95 !3.83E3

!8.42E2 17.50E2 ND

!1.21E3 ND 18.79E5 1

I Zr-97 !1.92E0 12.77E-1 11.64E-1 !

ND

!3.98E-1 !

ND

!4.20E4

! Nb-95 13.18E5

!1.24E5 18.84E4 ND

!1.16E5 ND 12.29E8

! Mo-99 !

ND 18.14E7

!2.01E7 ND

!1.74E8 ND 16.73E7

! Tc-99m!1.32E1 12.59El 14.29E2 ND

!3.76E2 11.32E1

!1.47E4 i

! Tc-141!

0 0

0 ND 0

0 0

! ! Ru-103!4.28E3 ND

!1.65E3 ND 11.08E4 ND

!1.11E5

! ! Ru-105!3.82E-3 !

ND

!1.39E-3 !

ND 13.36E-2 !

ND

!2.49E0

! Ru-106!9.24E4 ND 11.15E4 ND

!1.25E5 ND 11.44E6

!Ag-110m!2.09E8

!1.41E8

!1.13E8 ND

!2.63E8 ND

!1.68E10 !

'! Te-12 5m ! 7. 3 8E7 12.00E7

!9.84E6

!2.07E7 ND ND 17.12E7

!Te-127m!2.08E8

!5.60E7 12.47E7 14.97E7

!5.93E8 ND 11.68E8

!Te-127 13.05E3 18.22E2 16.54E2

!2.11E3 18.67E3 ND

!1.19ES 1

i

!Te-129m!2.71E8

!7.57E7

!4.21E7

!8.74E7

!7.96E8 ND

!3.31E8

!Te-129 !

0 0

0 0

12.90E-9 !

ND 16.17E-8 !

!To-131m!1.60E6 15.53E5

!5.89ES

!1.14E6

!5.35E6 ND

!2.24E7

!Te-131 !

0 0

0 0

0 ND 0

!Te-132 11.02E7 14.52E6

!S.46E6 16.58E6

!4.20E7 ND 14.55E7

!I-130

!1.73E6

!3.49E6

!1.80E6

!3.84E8 15.22E6 ND

!1.63E6 1

l s..mb

.+..Mli,L.;.:.1,..; A;2 d m. e u m _.. _, _._,

Rcv. 3 TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (R ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES g

Grass-Cow-Milk Pathway (m2 mrem /yr) per (pCi/sec)

! Total

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

II-131

!1.30E9 11.31E9

!7.45E8

!4.33E11

!2.15E9 ND 11.17E8

!I-132

!6.02E-1 11.11E0

!5.08E-1 !S.13E1

!1.69EO ND 11.30E0

!I-133 11.74E7

!2.15E7 18.13E6

!3.99E9

!3.58E7 ND

!8.66E6

!I-134 1

0 0

0 0

0 ND 0

l II-135 15.40E4 19.72E4

!4.60E4 18.61E6 11.49ES ND 17.40E4

!Cs-134 12.26E10 13.72E10

!7.84E9 ND 11.15E10 !4.13E9 12.00E8

! !Cs-136 11.01E9 12.77E9 11.79E9 ND 11.48E9 12.20E8

!9.74E7

!Cs-137 !3.22E10 13.09E10

!4.56E9 1

ND

!1.01E10 13.62E9 11.93E8 1

!Cs-138 !

0 0

0 ND 0

0 0

!Ba-139 !1.89E-7 !

0

!S.48E-9 !

ND 0

0

!1.09E-5 !

!Ba-140 !1.17ES

!1.03E5 16.84E6 ND

!3.34E4 16.12E4 15.93E7

! Ba-144. !

0 0

O ND O

0 O

!Ba-142 !

0 0

0 ND 0

0 0

l ILa-140 !1.95El

!6.80E0

!2.29E0 ND ND ND

!1.90E5

!La-142 !

0 0

0 ND ND ND

!2.90E-6 !

!Co-141 !2.19E4 11.09E4

!1.62E3 ND

!4.78E3 ND

!1.36E7

!Co-143 !1.87E2 11.02E5 11.47El ND

!4.26El ND

!1.49E6

!Cc-144 !1.62E6

!5.09E5 18.66E4 ND

!2.82E5 ND

!1.33E8

!Pr-143 !7.19E2

!2.16E2

!3.57El ND

!1.17E2 1

ND

!7.75ES

!Pr-144 !

0 0

0 ND 0

ND 0

!Nd-147 14.45E2

!3.61E2

!2.79El ND

!1.98E2 ND 15.71E5

!W-187 12.91E4 11.73E4

!7.73E3 ND ND ND

!2.42E6

!Np-239 !1.72E1

!1.23E0 18.68E-1 !

ND 13.57E0 ND 19.14E4

! 4.-9.ywappaQ.www-

.:-~ =,r_

Rsv. 3 TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES I

Grass-Goat-Milk Pathway (m2 mrem /yr) per (pCi/sec) i i

! Total i

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

! H-3 ND

!3.20E3 13.20E3 13.20E3 13.20E3

!3.20E3 13.20E3 l

! C-14 11.19E9 12.39E8

!2.39E8 12.39E8 12.39E8

!2.39E8

!2.39E8

! Na-24 11.07E6 11.07E6 11.07E6 11.07E6 11.07E6

!1.07E6 11.07E6

! P-32 19.33E10 14.37E9

!3.60E9 ND ND ND

!2.58E9

! Cr-51 !

ND ND 11.23E4

!6.78E3

!1.87E3 11.25E4

!6.48E5

! Mn-54 !

ND 12.52E6 16.70E5 ND 17.06ES ND

!2.11E6

! Mn-56 !

ND 11.54E-3 13.49E-4 !

ND 11.87E-3 !

ND 12.24E-1 !

! Fe-55 11.45E6 17.71ES 12.39E5 ND ND 14.36E5 11.43E5

! Fe-59 !1.56E6

!2.53E6

!1.26E6 ND ND

!7.33E5 12.63E6

! Co-58 !

ND 11.45E6 14.45E6 ND ND ND

!8.49E6

! Co-60 !

ND 15.18E6 11.53E7 ND ND RD

!2.87E7 i

! Ni-93 !3.56E9 11.90E8

!1.21E8 ND ND ND

!1.28E7

! Ni-65 !1.99E-1 11.87E-2

!1.09E-2 !

ND ND ND

!2.29E0

! Cu-64 !

ND

!8.31E3

!5.02E3 ND

!2.01E4 ND

!3.90E5

! Zn-65 !4.96E8 11.32E9 18.22E8 I

ND

!8.33E8 ND

!2.32E8

! Zn-69 !

0 1

0 1

0 ND 0

ND

!1.35E-1C!

l

! Br-83 !

ND ND ND ND ND ND ND I

! Br-84 !

ND ND ND ND ND ND ND

! Br-85 !

ND ND ND ND ND ND ND

! Rb-86 !

ND

!1.06E9 16.50E8 ND ND ND

!6.80E7 0

! Rb-88 !

ND 0

0 ND ND ND

! Rb-89 !

ND 0

0 ND ND ND 0

! Sr-89 11.39E10 !

ND 13.97E8 ND ND ND

!5.38E8

! Sr-90 !2.35E11 !

ND 15.95E10 !

ND ND ND

!3.16E9

! Sr-91 !2.74E5 ND 11.03E4 ND ND ND

!6.04E5

,.L A a_ L !N.. M..:d L f t h y a. ; p w

~

.,-gf

l Rev. 3 i

TABLE 5 (Contd.)

FATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass-Goat-Milk Pathway (m2 mrem /yr) per (pCi/sec)

! Total

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

! Sr-92 !4.58E0 ND

!1.84E-1 !

ND ND ND 18.68E1

! Y-90

!3.87El ND

!1.03E0 ND ND ND

!1.10E5

! Y-91m !

0 ND O

ND ND ND 0

! Y-91

!4.68E3 ND

!1.25E2 ND ND ND 16.24E-5 !

! Y-92

!3.04E-5 !

ND

!8.69E-7 !

ND ND ND

!8.77E-1 !

! Y-93 11.27E-1 !

ND

!3.48E-3 !

ND ND ND

!1.89E3

! Zr-95 14.60E2 11.01E2

!9.00E1 ND

!1.45E2 ND 11.05ES

! Zr-97 !2.30E-1 13.33E-2

!1.96E-2 !

ND 14.78E-2 !

ND

!5.04E3

! Nb-95 !3.81E4

!1.48E4

!1.06E4 ND 11.39E4 ND

!2.75E7 i

! Mo-99 !

ND

!9.76E6

!2.42E6 ND

!2.09E7 ND

!8.08E6

! Tc-99m!1.59E0

!3.11E0

!5.15El ND

!4.52E1

!1.58E0 11.77E3

! Tc-LQ1!

0 0

0 ND 0

0 1

0

,i! ! Ru-103!5.14E2 ND

!1.98E2 ND

!1.29E3 ND 11.33E4

!! ! Ru-105!4.58E-4 !

ND 11.66E-4 !

ND

!4.03E-3 !

ND 12.99E-1 !

! Ru-106!1.11E4 ND 11.38E3 ND

!1.50E4 ND 11.72E5

!Ag-110m!2.51E7

!1.69E7 11.35E7 ND 13.15E7 ND 12.01E9

!Ta-125m!8.85E6

!2.40E6

!1.18E6

!2.48E6 ND ND

!8.54E6

!Te-127m!2.50E7

!6.72E6

!2.96E6 15.97E6

!7.12E7 ND 12.02E7

!Tc-127 !3.66E2 19.86El

!7.85El

!2.53E2 11.04E3 ND 11.43E4

!Te-129m!3.25E7

!9.09E6

!5.05E6

!1.05E7 19.55E7 ND

!3.97E7

!Te-129 !

0 O

O 0

0 ND 17.40E-9 !

!To-131m!1.92E5

!6.64E4

!7.07E4

!1.37E5 16.43E5 ND

!2.69E6

!Te-131 !

0 0

0 1

0 0

ND 0

!Te-132 !1.23E6

!5.42E5

!6.55ES

!7.90E5 15.04E6 ND

!5.46E6

!I-130 12.07E6

!4.19E6

!2.16E6

!4.61E8 16.26E6 ND

!1.96E6 J

I.

a !

Na des MM1NOmO*+i=s'h wer-e.-ye.teg Ae.n 2

.y n e-5

Rev. 3 TABLE 5 (Contd.)

1 PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN h0BLE GASES Grass-Goat-Milk Pathway (ma mrem /yr) per (pci/sec)

! Total

!Nuclide!

Bone Liver Body 1 Thyroid ! Kidney !

Lung

! GI-LLI !

!I-131 11.56E9 11.57E9 18.94E8

!5.20E11

!2.58E9 ND

!1.40E8

! !I-132 17.22E-1 11.33E0

!6.10E-1 16.15El

!2.03E0 ND

!1.56E0 II-133

!2.09E7 12.58E7

!9.76E6 14.79E9 14.30E7 ND

!1.04E7

!I-134 0

0 0

O 0

1 ND 0

!I-135 16.48E4 11.17ES 15.52E4

!1.03E7 11.79E5 ND 18.88E4

!Cs-134 !6.79E10 11.11E11 12.35E10 !

ND

!3.45E10 !1.24E10 16.01E8

!Cs-136 !3.03E9 18.32E9 15.38E9 ND 14.43E9 16.61E8

!2.92E8

!Cc-137 19.67E10 19.26E10 11.37E10 !

ND

!3.02E10 11.09E10 !S.80E8

!Cs-138 !

0 0

1 0

ND 0

1 0

0

!Ba-139 !2.27E-8 !

0 1

0 ND 0

0 11.31E-6 !

t

!Ba-140 !1.41E7

!1.23E4

!8.20E5 ND

!4.01E3

!7.34E3 17.12E6

!Ba-141 !

0 1

0 0

ND 0

0 0

i

!Ba-142 !

0 0

0 t

ND 0

0 0

!La-140 !2.34E0 18.17E-1

!2.75E-1 !

ND ND ND

!2.28E4

!La-142 !

0 0

0 ND ND ND

!3.49E-7 !

i

!Cc-141 12.62E3 11.31E3

!1.94E2 ND

!5.74E2 ND

!1.63E6

!Co-143 12.25El 11.22E4

!1.77E0 ND

!5.12E0 ND

!1.79E5

!Ca-144 11.95E5 16.11E4 11.04E4 ND

!3.38E4 ND

!1.59E7

!Pr-143 !8.62E1

!2.59El

!4.28E0 t

ND

!1.40E1 ND 19.30E4

!Pr-144 !

0 O

0 ND 0

ND 0

!Nd-147 !5.34E1 14.33E1 13.35E0 ND

!2.37El ND

!6.85E4

!W-187

!3.49E3

!2.07E3

!9.27E2 ND ND ND

!2.90E5

(

!Np-239 !2.06E0

!1.48E-1 11.04E-1 !

ND

!4.28E-1 !

ND

!1.10E4 i

i 56 -

.. +

e4M 47g

, Q g h gedmy p q ~

"g.g..,.,

y

Rev. 3 TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway (m2 mrem /yr) per (pCi/sec)

! Total

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney ?

Lung

! GI-LLI !

! H-3 ND

!4.01E3

!4.01E3

!4.01E3 14.01E3 14.01E3 14.01E3

! C-14 18.89E8

!1.78E8

!1.78E8

!1.78E8 11.78E8 11.78E8 11.78E8

! Na-24 13.75E5 13.75ES

!3.75E5

!3.75ES

!3.75ES

!3.75ES

!3.75ES

! P-32

!3.37E9 11.57E8

!1.30E8 ND ND ND

!9.30E7

! Cr-51 !

ND ND

!1.17ES

!6.50E4 11.78E4 11.19ES

!6.21E6

! Mn-54 !

ND

!6.65E8

!1.77E8 ND 11.86E8 ND

!5.58E8

! Mn-56 !

ND 11.88E1

!4.24E0 t

ND

!2.27El ND 12.72E3

! Fo-55 18.01E8

!4.25E8

!1.32E8 ND ND 12.40E8

!7.87E7

! Fe-59 13.97E8 16.43E8 13.20E8 ND ND

!1.86E8 16.69E8

! Co-58 !

ND

!6.44E7 11.97E8 ND ND ND

!3.76E8

! Co-60 !

ND

!3.78E8 11.12E9 ND ND ND 12.10E9

! Ni-@3 !3.95E10 !2.11E9

!1.34E9 ND ND ND

!1.42E8

! Ni-65 !1.05E2 19.89EO

!5.77E0 ND ND ND

!1.21E3

! Cu-64 !

ND

!1.10E4

!6.64E3 ND

!2.66E4 ND

!5.16E5

! Zn-65 !8.12E8

!2.16E9 11.35E9 ND 11.36E9 ND

!3.80EB

! ! Zn-69 11.09E-5 !1.57E-5 11.45E-6 !

ND

!9.52E-6 !

ND

!9.11E-4 !

! Br-83 !

ND ND

!5.37E0 ND ND ND 0

! Br-84 ?

ND ND 0

ND ND ND 0

! Br-85 !

ND ND 0

ND ND ND 0

! Rb-86 !

ND

!4.58E8

!2.82E8 ND ND-ND

!2.94E7

! Rb-88 !

ND 0

0 ND ND ND 0

! Rb-89 !

ND 0

0 ND ND ND 0

! Sr-89 !3.59E10 !

ND

!1.03E9 ND ND ND

!1.39E9

! Sr-90 11.24E12 !

ND

!3.15E11 !

ND ND ND 11.67E10

! Sr-91 15.24E5 ND

!1.98E4 ND ND ND

!1.16E6 I

l 1

i 1

l i

}

i h4;Jer ew swe Au ; v -

--.m

~ _ -.

.<e

Rev. 3 TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway (m2 mrem /yr) per (pCi/sec)

! Total

!Nuclide!

Bone Liver Body

! Thyroid ! Kidney !

Lung

! GI-LLI !

! Sr-92 !7.28E2 ND 12.92E1 ND ND ND 11.38E4

! Y-90

!2.31E4 ND

!6.18E2 ND ND ND

!6.57E7

! Y-91m !S.87E-9 !

ND

!3.23E-10!

ND ND ND

!1.74E-5 !

! Y-91 11.86E7 ND

!4.99ES ND ND ND

!2.48E9

! Y-92

!1.58E0 I

ND

!4.53E-2 !

ND ND ND

!4.58E4

! Y-93

!3.01E2 ND 18.25E0 ND ND ND

!4.48E6

! Zr-95 !3.86E6

!6.45E5 17.55E5 ND

!1.21E6 ND

!8.84E8

! Zr-97 15.70E2

!8.24E1

!4.86El ND

!1.18E2 ND

!1.25E7

! Nb-95 !4.10E5

!1.59ES

!1.14E5 ND 11.50E5 ND

!2.95E8

! Mo-99 !

ND 17.71E6 11.91E6 ND

!1.65E7 ND

!6.38E6

! Tc-99m!4.71E0 19.24E0

!1.53E2 ND

!1.34E2

!4.69E0

!5.26E3

! Tc-lb1!

0 0

0 ND 0

0 0

! Ru-103!1.54E7 ND

!S.90E6 ND

!3.87E7 ND

!3.97E8

! Ru-105!9.16El ND 13.32E1 ND

!8.05E2 ND

!5.98E4

! Ru-106!7.45E8 ND

!9.30E7 ND

!1.01E9 ND

!1.16E10 !

!Ag-110m!3.22E7 12.17E7 11.74E7 ND

!4.05E7 ND

!2.58E9

!Tc-125m!3.51E8 19.50E7

!4.67E7 19.84E7 ND ND

!3.38E8

!To-127m!1.32E9

!3.56E8 11.57E8

!3.16E8

!3.77E9 ND

!1.07E9

!Te-127 !1.00E4

!2.69E3

!2.14E3 16.91E3

!2.84E4 ND

!3.90E5 i

!To-129m!8.38E8 12.34E8

!1.30E8 12.70E8 12.46E9 ND

!1.02E9

!To-129 11.16E-3 13.23E-4 12.75E-4 !8.26E-4

!3.39E-5 !

ND

!7.20E-2 !

! Te-131m !1. 54E6

!5.33E5

!5.68E5 11.10E6

!5.16E6 ND

!2.16E7

!Te-131 !

0 0

0 0

0 t

ND 0

l

!To-132 !6.98E6 13.09E6

!3.73E6

!4.50E6 12.87E7 ND

!3.11E7

.: !I-130

!6.16E5

!1.24E6

!6.38E5 11.37E8 11.86E6 ND 15.79E5 I

I l

l l

l

!,a.

k N3 NN4W -~Ot 4*4 i in.

.. U - '.' ) i 2Th$

c

Rsv. 3 TABLE 5 (Contd.)

PATHWAY DOSE FACTORS (Rg) FOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway (m2 mrem /yr) per (pCi/sec)

! Total

!Nuclide!

Bone Liver Body 1 Thyroid ! Kidney !

Lung

! GI-LLI !

!I-131 11.43E8

!1.44E8 18.17E7 14.75E10 12.36E8 ND

!1.28E7

!I-132 18.58E1 11.58E2

!7.25El 17.31E3 12.41E2 ND 11.86E2 i

II-133

!3.56E6

!4.40E6 11.67E6

!8.18E8

!7.34E6 ND

!1.77E6 l

!I-134 11.55E-4 !2.88E-4 11.32E-4 16.62E-3 14.40E-4 !

ND 11.91E-4 !

't 11-135 16.62E4

!1.13E5 15.33E4

!9.97E6 11.70E5 ND 18.58E4 ICs-134 !1.60E10 !2.63E10

!5.55E9 ND 18.15E9 12.93E9

!1.42E8 l

!Cc-136 !8.17E7 12.25E8 11.45E8 ND 11.20E8 11.78E7

!7.90E6

!Cs-137 !2.39E10 12.29E10 13.38E9 ND 17.46E9

!2.68E9 11.43E8

!Cs-138 !

0 0

0 1

ND 0

0 0

!Bn-139 !4.80E-2 !2.56E-5

!1.39E-3 !

ND

!2.24E-5 11.51E-5 !2.77E0

!Ba-140 !2.77E8 12.42E5 11.62E7 ND 17.89E4 11.45ES 11.40E8

!Ba-lea !

0 0

0 ND 0

0 0

!Ba-142 1 0

0 0

ND 0

0 0

!La-140 13.25E3 11.14E3

!3.83E2. !

ND ND ND

!3.17E7

!La-142 12.50E-4 !7.98E-5

!2.50E-5 !

ND ND ND 11.58E1

!Co-141 16.56ES

!3.27ES 14.86E4 ND

!1.43E5 ND 14.08E8

!Co-143 !1.72E3 19.31E5 11.35E2 ND

!3.91E2 ND

!1.36E7

!Co-144 !1.27E8 13.98E7 16.78E6 ND 12.21E7 ND

!1.04E10 !

!Pr-143 11.46ES 14.38E4

!7.25E3 ND

!2.37E4 ND

!1.58E8

!Pr-144 !

0 0

0 ND 0

ND 0

• !Nd-147 !7.17E4

!5.81E4

!4.50E3 ND 13.19E4 ND 19.20E7

!W-187

!6.47E4 13.83E4

!1.72E4 ND ND ND

!5.38E6 i

!Np-239 12.55E3 11.83E2

!1.29E2 ND

!S.30E2 ND

!1.36E7 l,..~.e ~,..,sA.,.,4.ed$ g,wqe.,~ s_,

,s.;,, ww

%e_

TABLE 6 (Continu-d)

RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM s

.;j Stction C de Sector Site Description Location q

40 P

Callaway Electric Cooperative Utility 4.2 mi. @ 291* WNW it Pole No. 18145

I l

39 Q

Callaway Electric Cooperative Utility 5.4 mi. @ 312

• NW Pole No. 17516 38 R

Callaway Electric Cooperative litility 4.5 mi. @ 334" MNW Pole No. 34708

.g t-

[

Eight Stations to be placed in special interest areas such as e

population centers, nearby resi-g dences, schools, and in 1 or 2 areas to serve as control stations.

I}. '

33 City of Hams Prairie 7.3 mi. @ 271* W 31 City of Hokane 7.6 mi. @ 218* SW

)

26 Town of Americus 12.1 mi. @ 82* E a;

[

27 Town of Bluffton 9.5 mi. @ 112* ESE 35 City of Toledo 5.8 mi. @ 340* NNW 23 City of Yucatan 6.7 mi. @ 14 NNE ll 11 City of Portland 5.0 mi. @ 136* SE I

20 City of Readsville 4.8 mi. @ 45* NE 1

34 (P-Control) 2.5 Hiles South of 0 and C 9.5 mi. @ 291* WNW 9

Junction i

TABLE 6 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

.s s

.I Station Ccde Sector Site Description Location 4:i A-8 B

County Road 448, 0.9 mi.

.9 mi. @ 20" NNE t

South of liighway 0

! B-3 A

0.6 mile east of Highway 0 1.9 mi. @ 355' NNW and CC Junction

.p I

One sample from the community r: I with the highest D/Q V-P I A-9 R

Community of Heform 1.7 mi. @ 336* NNW ip

~

t

, gj i One sample from a control location,

&w as for example 15-30 km distant

f and in the least prevalent wind

.(;

direction.

s..

,hIA-7 Q

C. Bartley Farm 9.5 mi. @ 312' NW j.;

if

3. Waterborne (i

a. Surface

• One sample upstream Composite sample over a Gamma isotopic analysis

.j period of less than or of each sample. Tritium

,)

equal to 31 days.

analysis of composite sample at least occe per y

P.

92 days.

i f

S01 11 84 feet upstream of discharge, 4.8 mi. @ 144' SE

]p-north bank f

One sample downstreau

r i

V

^l

{

TABLE 6 (Continued)

RADIOLOGICAL ENVIRONNENTAL HONITORING PROGRAM s

Stetion Code Sector Site Description Location

'f I'

['

C G

1.0 river mile downstream 5.1 mi. @ 135* SE of discharge, north bank sq

4. Ingestion t.

k((7

.c. Milk Samples from milking animals Semimonthly when Gamma isotopic (d) and I-131 in three location within animals are on analysis semimonthly when 5 km distance having the pasture, monthly at animals are on pasture; DI highest dose potential g.

If other times.

monthly at other times.

J.

there are acne, then one

' t;1 i sample from milking animals s

in each of three areas u

between 5 to 8 km distant where doses are calculated t

]{J l

to be greater than 1 mrem per year

.cr

.c

.f One sample from milking animals at a control location, 15 to l[

30 km distant and in the least

.y prevalent wind direction.

r l}

Dua to a lack of milk animals which satisfy these requirements, the milk pathway is currently not if included as a part of the Callaway Plant Radiological Environmental Monitoring Program. Should l{

the Annual Land Use Census identify the existence of milking animals in locations which satisfy these requirements, then the program will be revised to include this pathway.

+

b i

e

I y

TABLE 6 (Continued) 1l; RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM l

s

'f St ti r on Location

'{.

Cede Sector Site Descri g g

~t Gamma Isotopic (d) and I-131

,9 Samples of three Monthly when available analysis.

10' different kinds of lF broad leaf vegetation

!,(

grown nearest each of two M..

different offsite locations 1%

of highest predicted annual

, }?-

average ground-level D/Q

;3.

if milk sampling is not iK performed.

D 1.8 mi. @ 344' NNW R

Becker Farm 3[-lV-6 1.8 mi. @ 356' N A

Heehan Farm

![;!V-7 Gamma isotopic (d) i.

{!-

One sample of each of Monthly when available the similar broad leaf analysis.

-N ip m vegetation grown 15 to "I

30 km distant in the least prevalent wind direction if milk g-sampling is not performed.

i

\\

15 mi. @ 224* SW V-3 L

llazlett Farm l[

.I a

1 1

'l t

e

t TABLE 7 i

e, REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

! bi f

j,%

Reporting Levels u

. f.f.

s; i

i

'it-t Water Airborne Particulate Fisti Hilk Food Product I

h IAnalysis (pCi/1) or Cases (pCi/n )

(pci/kg), wet (pCi/1)

(pCi/kg, wet) 2 I

,E H-3 20,000

• I f'_[E_N I

Hn-54 1,000 30,000 t

I ef'.

t l

'h Fe-59 400 10,000 l

]

(ff f

I l*p Co-58 1,000 30,000 t

$y t

I i

b.

a, 1 Co-60 300 10,000 l

t oi g

i-8 I Zr-Nb-95 400 **

I y[-

1 l

t I-131' 2

0.9 3

100 1

Cs-134 30 10 1,000 60 1,000 t-1 I

Cs-137 50 20 2,000 70 2,000 l

t Ba-La-140 200 **

300**

I 0-kk IO For drinking water samples.

For surface water samples a value of 30,000 pCi/l is used.

q l ** Total activity, parent plus dr.uglater activity.

e e

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TABLE 8 I'.

I.

HAXINUM VALUES FOR THE LOWER L1 HITS OF DETECTION (LLD)"'

1 t

.s I

I Water Airborne Particulate Fist Milk Food Product Sediment t

i IAnalysis (pci/1) or Gases (pCi/m )

(pCi/kg), wet (pCi/1)

(pCi/kg, wet) (pCi/Kg, dry) 3 i

'i~

t 1

E IGross Beta 4

.01 I

[.'_'

t I

M I

H-3 2000

• N:

I t

130

'D t

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[

t Fe-59 30 t

ci t

t 130

[1 i

Co-58,60 15 O

t I

5 I

Zr-Nb-95 15 **

i

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fg i 1-131 1(d)

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60 l

I l

I j

t Cs-134 15

.05 130 15 60 150 t

t I

~

i Cs-137 18

.06 150 18 80 180 t

I i

g 15**

I I

Ba-La-140 15 **

l-t*

For surface water samples, a value of 3000 pCi/l is used.

1 1ota, ac<1.it...ar..<,,.s da,t.ter a<<i.it,.

}s a

}'

4 4

'i

~.

Rnv. 3 at =

the elapsed time between sample collection (or end of the smaple collection period) and time of counting (for environmental samples, not plant effluent samples).

Typical values of E, V, Y and at shall be used in the calculations.

It should be recognized that the LLD is defined as a a priori (before the fact) limit representing the capa-~

bility of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Analyses are performed in such a manner that the stated LLDs are achieved under routine conditions.

Occassionally background fluctuations, unavoidable small sample sizes, the presence of inter-fering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

! (b)

This list does not mean that only these nu-clides are to be considered.

Other peaks that are identifiable, together with those of the above nuclides, shall also be anlayzed and reported in the Annual Radiological Environ-mental Operating Report.

3

! (c)

Required detection capabilities for thermolu-minescent dosimeters used for environmental measurements shall be in accordance with the reccommendations of Regulatory Guide 4.13, Revision 1, July 1977, t

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Values of the slope factor (S), are presented in TABLE 11.

i Short term dispersion estimates are applicable to short i

term releases which are not sufficiently random in both time of day and duration (e.g.,

the short term release periods are not dependent solely.on atmospheric condi-tions or time of day) to be represented by the annual

! average dispersion conditions.

(Ref. 9.8.12.)

6.1.2.1 The Determination of the Slope Factor (S).

j The general approach employed by subroutine PURGE of j

XOQDOQ (Ref. 9.17.4) was utilized to produce values of the slope of the (X/Q) curves (Slope Factor (S)) for I

both' the Radwaste Building Vent :and the Unit' Vent.

However, instead of using approximation procedures to l

produce the 15 precentile (X/Q) values, the 15 percen-I tile (X/Q) value -for each release and at each location j

was determined by ranking all the 1-hour (X/Q),ing values for-that release and at'the location in descend order.

The (X/Q)y value which corresponded to the 15 j

percentile of all the calculated (X/Q) values within a i

sector was extracted for use in the intermittent release (X/Q) calculation.

s i

% The intermittent release (X/Q) curve was constructed i

using the calculated 1-hour 15 percentile (X/Q), and j

its corresponding annual average (X/Q)a.

A graphic re-

! presentation, of how the computational procedure works j

! is illustrated by. Figure 4.8 of reference 9.17.4.

The straight line connecting these points represents (X/Q)1 i

values for intermittent releases, ranging in duration

! from one (1) hour to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />.

The slope (S) of the curve is expressed as:

i l

)

-log ( (X/Q),/(X/Q)_)

(6.8)

^

l S=

i log (Ta/T1) i or i

-(log (X/Q), - log (X/Q)1)'

(6.9) j S=

log Ta - log T

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.N ])]pf WY R)?L q,.... u. m _ __ _,'- 5k$ TABLE 9 c li 2 - [~j ; HIGHEST ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS (a) . 4+.- h. RADWAS_TE BUILDING VENT DISTANCE X/Q X/Q .gif LOCATION (b) SECTOR (METERS) XfQ Decayed /Undepleted Decayed / Depleted Dfg

j; I

(sec/m ) (sec/m3) .(sec/m3) (m 2} W-3 d hIf I SITE BOUNDARY S 1300 1.3E-6 .1.3E-6 1.2E-6 4.4E-9 ')c ! Nearest Cow (c) NW 5053 4.3E-7 4.2E-7 3.3E-7 1.lE-9 .h I Nearest Goat (c) NW 5053 4.3E-7 4.2E-7 3.3E-7 1.1E-9 .pl ' Nearest Meat Animal NNW 2736 7.6E-7 7.6E-7 6.4E-8 2.4E-9 .l: I Hearest Vegtable (c) .d il Garden NNW 2865 8.2E-7 8.1E-7 6.8E-7 2.5E-9 id I Lfr ! Hearest Residence (c) NNW 2865 8.2E-7 8.1E-7 6.8E-7 2.5E-9 ? Boundary, Area Closed to Public Use (c) NW 1154 4.0E-6 4.0E-6 3.5E-6 1.4E-8 - i . -J7 (a) Values given are from FSAR, Table 2.3-84, and Table 2.3-86 it I (b) Data from 1984 Land Use Census I { (c) Values derived from FSAR, Table 2.3-81, using the methodology presented in Equation (6.2) b ,,e

h Building Shape Parameter (C) = 0.5 (Ref. 9.5.4)

/

Vertical Height of Highest Adjacent Building (V) = 19.96 meters (Ref. 9.5.4) .d i'

e TABLE 10 .=, T HIGHEST ANNUAL AVERAGE ATMOSPHERIC DISPERSION PARAMETERS (a) h -Yj@ UNIT VENT pp DISTANCE X/Q X/Q LOCATION (b) SECTOR (METERS) XM Decayed /Undepleted Decayed / Depleted DJ (sec/m3}_ (sec/m ) (sec/m3) (m 2) a SITE BOUNDARY S 1300 9.9E-7 9.8E-7 8.8E-7 4.4E-9 I Nearest.CGW (c) NW 5053 3.6E-7 3.6E-7 2.8E-7 1.1E-9 f,I I Hearest Goat (c) NW 5053 3.6E-7 3.6E-7 2.8E-7 1.lE-9 Nearest Meat Animal NNW 2736 5.9E-7 5.9E-7 5.0E-7 2.4E-9 J i! Nearest Vegtable (c) 'fy1 Garden NNW 2865 6.4E-7 6.3E-7 5.3E-7 2.5E-9 p. r ! Nsarest Residence (c) NNW 2865 6.4E-7 6.'lE-7 5.3E-7 2.5E-9 iI Boundary, Area Closed to Public Use (c) NW 1154 2.8E-6 2.8E-6~ 2.5E-6 1.4E-8 7 j (a) Values given are from FSAR, Table 2.3-82, and Table 2.3-85 { l (b) Data from 1984 Land Use Census l (c) Values derived from FSAR, Table 2.3-83, using the methodology presented in Equation (6.2) fs' Building Shape Parameter (C) = 0.5 (Ref. 9.5.4) f Vertical Height of Highest Adjacent Building (V) = 66.45 meters (Ref. 9.5.4) 9 I 4 ' S, L =

Rnv. 3 TABLE 11 SHORT TERM DISPERSION PARAMETERS (a) (c) Slope Factor (S) Location (b) Sector Distance Unit Vent Radwaste (meters) Building Vent ! Site Boundary S 1300 .328 .320 1 N;arest Cow NW 5053 .263 .266 l ! N2arest Goat NW 5053 .263 .266 ! Nstrest Meat NNW 2736 .262 .268 Animal f! Naarest Vegetable NNW 2865 .264 .268 l Garden l l '! Naarest Residence NNW 2865 .264 .268 (a) Reference 9.5.4 ! (b) Data from 1984 Land Use Census (c) Recirculation Factor = 1.0 i r - 93

n =.. s w a

,c. s u a is. n

Rnv. 3 7.0 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation are submitted within 60 days after January 1 and July 1 of each year. The period of the first report begins with the date of initial criticality. The Radioactive Effluent Release Reports include a sum-m2ry of the quantities of radioactive liquid and grsaous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and G2seous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B is supplemented with three additional categories: class of solid waste (as defined by 10 CFR ! Part 61), type of container (e.g., LSA, Type A, Type B, ! Large Quantity), and SOLIDIFICATION agent or absorbent ! (o. g., cement, urea formaldehyde). The Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year includes an annual summary of hourly meteorological data collected over the previous year which may be either in the form of an hour-by-hour listing on magnetic tape of wind cpeed, wind direction, atmospheric stability, and pre-cipitation, or in the form of joint frequency distribu-tions of wind speed wind direction, and atmospheric ctability.* This same report includes an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report also includes, the asessment of the radiation doses from radioactive liquid and gaseous effluents to MEM-BERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assump-tions used in making these assessments, i.e., specific activity, exposure time and location, is included in I these reports. Acceptable methods for calculating the dose contributions from liquid and gaseous effluents ! are given in Regulatory Guide 1.109, and the ODCM. The Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year also includes, as r; quired by Technical Specification 3.11.4, an assess-ccnt of radition doses to the likely most exposed MEM-BER OF THE PUBLIC from Reactor releases and other naarby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the. l l W A %. e s.-e- - =. m _ x _ v,. .s

R;v. 3 previous calender year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power Operation". The Radicactive Effluent Release Reports include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. The Radioactive Effluent Release Reports include any changes made during the reporting period to the PROCESS CONTROL PROGRAM and to the ODCM, pursuant to Specifica-tion 6.13 and 6.14, respectively, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment System, pursuant to Specification 6.15. It also in-cludes a listing of new locations for dose calculations and or environmental monitoring identified by the Land i Une. Census pursuant to Specification 3.12.2. The Radioactive Effluent Release Reports also include i the following information: An explanation as to why the inoperability of liquid or gaseous effluent moni-toring instrumentation was not corrected within the time specified in Specification 3.3.3.10 or 3.3.3.11, respectively; and descriptio.1 of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Specification 3.11.1.4 or 3.11.2.5, respectively.

• In lieu of submission, the Union Electric Company has the option of retaining this summary of required msteorological data on site in a file that shall be provided to the NRC upon request.

(Ref.9.4) L M 1 L J A.. b u e w w - - y

Rev. 3 8.0 IMPLEMENTATION OF ODCM METHODOLOGY The ODCM provides the mathematical relationships used to implement the Radiological Effluent Technical specifications. For routine effluent release and dose assessment, com-puter codes are utilized to implement the ODCM ! m2thodologies. These codes have been evaluated by a ! qualified independent reviewer to ensure that they pro- ! duce results consistent with the methodologies pre- ! &;nted in the ODCM. (Ref. 9.5.5) i > l l f 1. Assh hd Ma$mJnF*b% &%Wr=> m &_ :,'u '

• y v

1*..

e,; _ s-_ y e. e -.r? s em p< v % < e

Ruv. 3

9.0 REFERENCES

9.1 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 20; U.S. Government Printing Office, Washington, D.C. 20402. 9.2 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S. Govern-ment Printing Office, WaGhington, D.C. 20402. 9.3 Title 40, " Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S. Government Printing Office, Washington, D.C. 20402. 9.4 Callaway Technical Specifications, Section 3.3.3.9, 3.3.3.10, 3/4.11, 3/4.12, and 6.9.1.7 as submitted to the U.S. Nuclear Regulatory Commisssion, August 1983. 9.5 Communications 9.5.1 Letter NEO-54, D.W. Capone to S.E. Milten-berger, dated January 5, 1983; Union Electric Company correspondence.

9. 5.h Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values",

J. H. Smith (Bechtel Power Corporation), to D. W. Capone (Union Electric Co.), dated February 27, 1984. 9.5.3 Letter BLUE 1159, J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Electric Company), dated January 18, 1984. 9.5.4 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Elecctric Co.), dated February 9, 1984. ! 9.5.5 Letter BLUE 1358, " Comparison of Callaway Plant Offsite Dose Calculations for Routine Effluents", J.H. Smith (Bechtel Power Corpora-tion) to D.W. Capone (Union Electric Company), dated March 22, 1984. 9.6 Union Electric Company Callaway Plant, Unit 1, Final Safety Analysis Report. 9.6.1 Section 11.5.2.2.3.1 9.6.2 Section 11.5.2.2.3.4 98 - i ' N* t"$dT*11 %'WjoA%iM E_:Q., b - - y % * ' de -1*

Rnv. 3 9.6.3 Section 11.5.2.1.2 9.6.4 Section 11.5.2.2.3.2 9.6.5 Section 11.5.2.2.3.3 9.6.6 Section 11.2.3.3.4 9.6.7 Section 11.2.3.4.3 9.6.8 Section 11.5.2.3.3.1 9.6.9 Section 11.5.2.3.3.2 9.6.10 Section 11.5.2.3.2.3 9.6.11 Section 11.5.2.3.2.2 9.6.12 Section 2.3.5 9.6.13 Section 2.3.5.1 ! 9.6.14 Section 2.3.5.2.1.2 9.6.15 (Reference Deleted) 9.6.46 (Reference Deleted) 9.6.17 Section 9.2.6 9.6.18 Section 9.2.7.2.1 9.6.19 Section 6.3.2.2 9.6.20 Table 11.1-6 9.6.21 Table 9.4-6 9.6.22 Table 9.4-8 9.6.23 Table 9.4-11 9.6.24 Table 9.4-12 9.6.25 Table 2.3-66 9.6.26 Table 2.3-68 9.7 Union Electric Company Callaway Plant Environ-mental Report, Operating License Stage. 9.7.1 Table 2.1-19 &J ; zi+.t. asm-n.t-,.s,&x :~~w.s;c : u. u. .x . a,,-..a

Rnv. 3 9.7.2 Section 2.1.2.3 9.7.3 Section 2.1.3.2.8 9.7.4 Section 2.1.3.3.4 9.7.5 Section 2.1.3.1.3 9.7.6 Section 5.2.4.1 9.7.7 Table 2.1-19 9.8 U.S. Nuclear Regulatory Commission, " Preparation of Radiological Effluent Techni-cal Specification For Nuclear Power Plants", USNRC NUREG-0133, Washington, D.C. 20555, Oc-tober 1978. 9.8.1 Pages AA-1 through AA-3 9.8.2 Section 5.3.1.3 9.8.3 Section 4.3 9.8.4 Section 4.3.1 9. 8.3 Section 5.3.1.5 ) 9.8.6 Section 5.1.1 9.8.7 Section 5.1.2 9.8.8 Section 5.2.1 9.8.9 Section 5.2.1.1 9.8.10 Section 5.3.1 9.8.11 Section 3.8 9.8.12 Section 3.3 9.9 U.S. Nuclear Regulatory Commission, "XOQDOQ, Program For the Meterological Evaluation Of Routine Effluent Releases At Nuclear Power Stations", USNRC NUREG-0324, Washington, D.C. 20555. 9.9.1 Pages 19-20 Subroutine PURGE - 100 -

~

., V

Rnv. 3 9.10 Regulatory Guide 1.111, " Methods For Estimat-ing Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Cooled Reactors", Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, July, 1977. 9.10.1 Section c.1.b 9.10.2 Figures 3 through 6 9.10.3 Figures 7 through 10 9.10.4 (Reference Deleted) 9.10.5 Section c.4 9.11 Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases Of Reactor Effluents For the Purpose Of Evaluating Com-pliance With 10 CFR Part 50, Appendix I", Revision 1, U.S. Nuclear Regulatory Commis-sion, Washington, D.C. 20555, October 1977. 9.11.1 Appendix C, Section 3.a 9.11g2 Appendix E, Table E-15 9.11.3 Appendix C, Section 1 9.12 U.S. Nuclear Regulatory Commission, " Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C. 20555, January 1980. 9.12.1 Section I, Page 2 9.12.2 Section IV, Page 8 9.12.3 Section IV, Page 9 9.12.4 Section III, Page 6 9.13 U.S. Nuclear Regulatory Commission, " Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors", USNRC NUREG-0472, Draft Revision 3, Washington, D.C. 20555, January 1983. 9.13.1 Definition 1.7, Page 1-2 - 101 - L:a,

Rnv. 3 9.14 Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 21, 1982. 9.14.1 Exhibit A 9.15 Wildlife Code of Missouri, Rules of the Con-servation Commission, Issued January 1, 1983. 9.16 Miscellaneous References 9.16.1 Drawing Number M-109-0007-06, Revision 5. 9.17 U.S. Nuclear Regulatory Commission, "X0QDOQ: Computer Program for the Meterological Evalua-tion of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2929, Septem-ber, 1982, Washington, D.C. 20555. 9.17.1 Section 4.1, " Subroutine ANNUAL", pages 23-25. 9.17.2 Section 4.1, " Subroutine ANNUAL", page 25. 9.17.3 Section 4.:1, " Subroutine DEPOS", page 26. 9.17.4 Section 4, " Subroutine PURGE", pages 27 and 28. l 1 102 - - tun m__

1 ATTACHMENT 4 i DESCRIPTION OF RADWASTE TREATMENT SYSTEM CHANGES This Attachment,contains the following: 1. ULNRC-937, Mr. Donald F. Schnell to Mr. Harold R. Denton, dated j october 3,1984. page 1 through 10 2. Letter Mr. B. J. Youngblood to Mr. D. F. Schnell,

Subject:

Callaway Plant, Unit 1 - Amendment No. 2 to License NPF-30. page 1 through 9 i 4 + J 4 1 e A J 1 f i i ese*U dh h*2 %* _ __ - " - - - T g..g m s % y e.,, ,,r,,,,,,, ere

,,.y es ATTACHMENT 4 3 t... -.: a ,.,. - -. n ). ; 6f LI I l i ) PJ t *., C ";* 11 6C (. ' s ' ' 1 r A.'. Y 1j e,j l t) i...v c n r rio r.s r ae i. v. r pM'., C om.. 1 2e ,q/ I s r. i.ouis...u s.ou m J < u) I /('. ~~ mm.. w.. u _...> -. \\.. a.. g / r -- / i <, 3,; / i, L g(,u t, /\\,. y/< J n +r .;f;q 4 ,g g' $ i -2 . ~. 934 ,o . o. c- ~ o...-.-~,u.- o_.4 r. .,On.1- ) s 1 ~............! /.a u..,..;.;....-. y i. q i 4 6.- W 2 )' Wl ,- / 3.. . J.e i .t. w d_ ! _. w.1; L.: ..v. 7>;_w .a ..s n.. ./ P,Y ...!.- '. LLU -N I-w%s. o ' i. /<../.., 3 _ _ ill t i . /... _.! _.. -. w U-- d!M M-b!! ![N/gfj} t Mr. Harold R. Denton db & ! ' l- -- 5 Office of Nuclear Reactor Reculation t. i %. [I i ' A I Regulatory Cc.mn? ,r] p-j' i sston U.S. Nuc ear

n. - i.

i. t.'a s h ing t: n, D.C. 20555 i._ _ i ,u...

Dear Mr. Denton:

2.3Cr0 i /9 //W_, COCKET NUMBER 50-483 M CALLAWAY PLANT, UNIT 1 J / ADDITION TO TECHNICAL SPECIFICATION TA3LE 4.11-1 /90 Union Electric Company is transm'itting three (3) original and forty (4 0) conformed copies of an application for Araendment to Tac;.lity Opera ting License No. ';PF - 2 5 for tha Callaway Plant, Unit 1. This applicc. tion reriuests that Tec hr. i c a l Spec:.fication Table 4.11-1 be revised to include two addit ional Satch ','a cte Release Tanks. Two 100,000 gallon tanks are required 'for storage and/or discharga due to an inci case in the volume of v:condary liquid

aste, gecifically waste from condensate d

mineralizer regenerationc.

Originally, the volume of ,;a s t e from regeneration of the c ndensate domineralizers,as estimated at 17,000 gallons per day. .%c e n t opera t ing e::pericace has s:.cwn taste /olumes asce ragi...; 4 3,0 00 ca llc ns per day Two additional 100,000 gallon tanks s.tuid procida adaquate capability based on revised estimates. The n<.,.ased chan gs u'd en:"ma effecttce for Union '. t t a c..me n t 1 to this Electric i pl amc ta tion up n '.3C ar;;rcva l. letter describes all enclosures transmitted herewith, m., ,..g i..a, g,.. S. s 1 a :- c ; ' :- 015C m1 :. ; ;- f

a a

t E.'. b L E.2 3t.../ b71.21.

1. w;u e s t.

_m. 9 /,7 h.-/ Very truly yours, O C T O c, 8 - WC4'u. y /, f DMid. DOCU. EliT C0itia0L A v5.: ' / g:;ph..c/4!/ b4 AC'L ROJECT 7186 M / F -/ p Ja ' ic-Donatd r. schnetl NW/1w At tach:m n ts .a.- < n.4 c.. - c..,..,.,,,,,..._,,,.

ATTACIDENT 4 STATE OF :CSSOURI ) ) SS ~ CITY OF ST. LOUIS ) Canald F. Schnell, of lawful age, being first duly sworn upon cath says that he is Vice President-Nuclear and an otficer ot Union Elec ric Ccmpany; that he has read the foregoing doct..ent and knows the content thereof; that he has e:<ecuted the same for and on behalf of said company with full pcwer and authority to do so; and that the facts therein stated are true and correct to the best of his

< nov iedc e, information and belief.

/' , Q :w k W.6,N.4 b By Donald F. Scnnell Vice President Nuclear SUBSCRISED and sworn to before me this fAI-. day of d f 4 v', 198M N hflsL.b J,L.Ls' f

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ATTACHMENT 6 .. ),.... N Enclosure A Safety Evaluation Enclcture 3 Significant !!a:ards Consideration Incicsure C P.ar ';ed rech'nical S,r ac i f f.ca tion Page s .:.nc,tes ure D Environ: ental Zvaluation G Md N N D%N N e b'O Y )- t/

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/ . / / ATTACHMENT 4

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. i..i.. S a f e t '., svaluation This amendment recuest ;s der revision of echnical S:ecifica:ica Ticia 4.ll-l to include two additional Satch Waste .[el use T2:<2. These twc l'O,'C0 ~ ga' ion tanks are required for ~ c ..,.,, p. %... v o i m-. e o i. -a .,.a c ~. du..s<1*e , e u n,.. : : :,. ~ 2,... -. >.. w =,,.., n w.. ; deminerzi.:er regeneratices. O r i7.a at.y, the volume of.aste fr:m regeneraticn ci :he condens ate demineralize rs sas estinated a: :. 7,0 0 0 ; 1 ' '.o n s p e r d ai, .e;en: cperat ng 2:<per :.ence has shcwn w2ste 701.2a5 averaging 43,000 gallons per day. .liste warer f:c.n demineral::ers vill be neutr alized and processed through a filter to remove :ccal suspended solids. No other treatment will be provided unless it is required to meet MPDES limits for discharge or Technical Specification limits. If a primary to secondary leak should occur, this waste stream would be processed through a and a filter, the secondary liquid waste evaporator, demineralizer for dischar e or for recycle. The tanks will be located near the - southwes t corner of the radwagte building and will be protected by a concrete dike built to'contain one tank volume in the event of a tank failure. Tank overflows <ill be piped directly to the diked area sump. The drain frca this sump will be diracted to the Dirty 'sadwasta Equipment and Floor Drain system. iiig h level ala::ms on the tanks will immediately signal valves to close on the taak fill lines .and to trip off the system's transfer pumps which vill terminate flow going to the tanks. A radiation monitor located inside the radwaste building will continuously monitor waste water being discharged from the tanks to.he discharge line. A valve located downstream of this.ncnitor will be isolated on a high radiation signal wnich will terminate the' discharge. Quality requirements and design features of the system aill ccrptv. with r.0;ulatorv. % d' 1 143. Water can also be routed to these tanks f r o., liquid radwaste and steam generator clo.. ir e n ; how.ver, the volume of waste frcm these vaste streams is not e:< pec t ed to increase from ..e .: p e c r ee ficws gi.en in '.2 r i u C':- a r. e r 11. -ince the ..,-.i 3 ...a-'.'., '. '.. e c., d .e i '. '. m....-.-. . 2. ;...' >....i.. v, t a. a m. activity in these tanks is expected to be consider ably less than that of the refueling water storage tank. A greater volume of waste water will be discharged than originally est; mated; ,,., h o w e v e r, because the activity of the secondary liquid waste system is normally negligable, the amount of radioactivity ~ released to the environment will not incr ease significantly and will not approach the activities for liquid ef fluents given in Table 11.2-1 of the FSAP.. rh'refore, the revision to this Tec.ical .mcification.ioes rot 9 /er wly affect or e n d a r.3 e r the h"alth or..ifety of the g. eral j.blic md does not involve an unreviewed ;afety question. h w m,-.w 4-

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? ATTACHMENT 6 ~ 7,,'~ <.. u i ),? 3,e 1/. '! a n a r '.:s Cons Ide r a t ton Stqn1:tcant This amendment request .3 fo: revision of Technical 5pecifi:2: ion Ta: Le 4.L1-1 to include two additional 32tch 'iaste Releasa 72nis. !nese t-o LOO,'C0 3allon tanxs are required for s;::2:a a n d.'o r discnarne due :: an increase in the estimated so '.ume a f s eccnd a r,. liquid waste, :pecificallc aste from cendensi:e deminer al :e: regene:ations. Originally, the volume of was:s f:ca receneration of the condensa te domineralice: s was es ima ed at 17,000 gallons per da, Recent operating e.<per ance r.a s s h c w.- vasta /olcmes averaging 4 3,000 gallons per day The two tan;;s -ill be protected by a concete dike built to ccntain one tank sclume in tne event of a tank failure. Tank overficws will be piped directly to' the diked area sump. The drain fccm this sump will be directed to the Dirty Radwaste Ecuipment and Floor Drain system. The activity in these tanks is expected to be considerably less than the activity in the refueling water storage tank, or in the reactor makeu.o water storac.e tank, since the largest portion of water going to these tanks will be secondary liquid was te. Although a greater volume of waste water will be discharged f rcm original estimates, the volume of.aste from %aste streams is not expected to inc case fecm the ficus given in Chapter 11 of the FSAR. In addition the activity of the

ecend 2:y '.iquid was te s y.; t em is ac:mally negligable inq t c. e c.ount of :2dioactivity released to the environment will not increase significantly.

The activities will not approach the activities for liquid effluents given in Table 11.2-1 of the FSAR. The Commission has p:cv4.ded guidance concerning the application of the standar.ds in 10 CFR S0.92 by providing certain amp es (43 FR 14370) One of tne a :ampt.:s of actions in/olving ,c significant ha:ards cor;;dara:icn c ela t.s s tc a change that

cnsti:utes 2n add::icnal liri.aticn, :est;ict;on, or :cnt: 31,ot presently in the Technical Specificatier.s.

The a.id i t ion of two 160,000 gallon tanks will p:o.;de ..;; tion 01 ltqaid was'_e s.st..;a ccatrol .,t presently in t_ h e T :-c h n i c a l Specifications. This amendment request does not involve a significant _n::cace in the 7:ohability or ccrsecuence of an acci'2nt or ,.2: .G. 5: de..: :iticr c.2: p; : .o';. e. a ';. a t i c r ;, or c; Arc ...e p:ssibility of a .w w or differen: kir.d of accident or i:oncition over previous evaluations; or involve a significant reduction in a margin of safety. Based on this information, the requested license amendment does not present a significant hazard. s Y

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b ATTACHMENT 4 1 ,J 1 ..i- ..........si . i3,:,s o? u. * ~. ...., e. 1, M,. T'. i s amendment r e., :e s t .3 for revision of Technical Specifica.icn Table 4.11-1 te include two additional 3atch Waste Release T20.3. The two 100,000 c:llon tanks are required for stora;c :nd/or discharge due tc an increase .a the estimated volume of 2ccondary liquid easte; specifically waste from condensate demineralizer re rencrations. Althoug'.' water can also be cou:ed to these tanks fren ;icuid radwaste and 3:2am 72nerator blewacwn, the volume of easte f e c.n these sources is not expected to signifirantiv increase frnr. that civen in tne Invironmental ?,eport. .i greater volume o:..,s t a wa:er ell.t ce cisccarged t.c.a n originally estimated; however, cecause the activity of the secondary liquid waste system is small, the amount of radioactivity released to the invironment will not increase significantly and will not app:cach the activities for liquid effluents given in the Envizcamental Report. Therefore, the change dces not constitute an unreviewed environmental question. In addition, the tanks are located in the southwest corner of thq radraste building (cutside). During the original cons tructica of the plant, this area underwent significant impact ..:..... 4... a,. .,l o o l.,,. y t , J. ..,._.o.,,,,J. ..t. _C .v .s. s m.a e . I. 'e 1^ }.'gI,.

ATTACDENT 6 cc.. ac......3,,.c, .a .+-.- ..m. .m.. .,t........,. 2,.- r .e,,.. ... : n. .,. ~ ..a a ..-..s. .y. g. n. .4 .6 s . v. '3 s[.;.- ~~. *. _.:.

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.( . <.................. *., s. 3., . -..... s,.. -..=... ......e ,,.: a,., .......u .e., -.a-.. ...... :,.. 9 _:.:.:, s,.. ;.. ..s....,. ,. :.......i o n .3..,_,.e .n...,1 - Steedman, Missouri 65077 ...., t am c orney win Division of Projects and Resident Programs, Chief, Section LA U.S. Nuclear Regulatory Commission Region III 799.icosevelt Road bienEllyn, Illinois 60137 t., t l e e u v., 2 su Callaway Resident Of fice U.S. ':uclear Regulatory Ccmmission RRil Steedman, Micsouri 65077 3cn ,2c e r a, C e r. u t v. Director

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..;r o n o D. F Sci' wll J. F. McLaugalin J. E. Birk ' ~ =ii. ~. *dObOC -/ F. C. Field R. J. Schukai M. A. Stiller S. E. Miltenberger J. J. Beisnan is s o u r :. Public Service Cc mission D.

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C. Pa30 water T. E. McFarland R. P. 'd e n d li ng D. E. Shafer D. J. Walker G56.37 (CA-4 6 0) Ccmpliance (J. E. Davis) NSRB (Laura Robertson) G 4-. M,*~. e.. .. <== +. 4 ...f + s a.= ~ o....6,' 8,'1, r.,y 4 .jp,

C /. j[,,/; UNITED sTAf ts f NUCLEAR REGULATORY COMMISSION . /, P' . wasmscros c.c. :asas e . /,, ] FEB 4 1MS Dockst No.: STN 50 483 Mr. O. F. SchnelT Vice President - Nuclear Union. Electric Company P. O. Box 149 St. Louis, MO 63166

Dear Mr. Schne1T:

Callaway Plant, Unit 1 - Anendment No. 2 to License NPF-30

Subject:

Tha Comission has issued the enclosed Amendment No. 2 to Operating License The amendment consists of a change NPF-30 for the Callaway Plant, Unit 1.to thi Technical Specification in res 27, 1984, October 3,1984, as supplemented December 6,1984 and Decembergallon tanks d ide 100,000 which recuested the addition of twosufficient storage time for secondary ef show acceptability of the water prior to release to the environment. The amenc: ent modifies Table 4.11-1 of the Callaway Technical Specifications to include wo additional Batch Waste Release Tanks. The notice of issuance A copy of the related Safety Evaluation is enclosed.will be included Federal Register Notice. Sincerel,, f. ' -(' .bb / 7u. J Y ungblood, Chief Li ns ng Branch No. I Divisi'an of Licensing

Enclosures:

1. /cendment No. 2 to NPF-20 2. Safety Evaluation Renner cc: See next page REC EiVb..] l FEB 8 rd ~- 1 l D. F. SCHNEL1 ^ I .,,,,,,(g 1 ..=u

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k t CALLAW/Y Y i-. Mr. D. F. I:nnell 1 Vice Pres':ent - Nuclear Unicr Elec--ic Ccmeany Post Office Sox 149 St. Louis, "issouri 63166 'cc: Mr. Nicholas A. Petrick Mayor Howard Steffen Executive Director - SNUPPS Chamois, Missouri 65024 5 Chcke Cherry Road Rockville, Maryland 20850 Professor William H. Miller Missouri Kansas Section, American Gersid Charnoff, Esq. Nuclear Society Themas A. Baxter. Esq. Department of Nuclear Engineering Shaw, Pittman, Potts & Trowbridge 1026 Engineering Building 1800 M Street, N. W. University of Missouri Wasnington, D. C. 20036 Columbia, Missouri 65211 Mr. J. E. Birk Mr. Robert G. Wright Assistant to the General Counsel Assoc. Judge, Eastern Of strict Unica Electric Ccmpany County Court, Callaway County, Post Office Sox 149 Missouri St. Lcuis, Missouri 63166 Route #1 Fulton, Missouri 65251

r. John Neisler Lewis C. Green, Esc.

u U. 5. Nuclear Regulatory Cemission Green, Hennings & Henry Pesicent Inspectors Office Attorney for Joint Intervenors RR41 314 N. Broadway, Suite 1830 Steedman, Missouri 65077 St. Louis, Missouri 63102 Mr. Jonald W. Cacone, Manager Mr. Earl Brown Nuclear Engineering School District Superintendent Uni:n Electric Ccmpany Post Office Box 9 ?cs: Office Sox 149 Kingdom City, Missouri 65262 St. Lcuis, Missouri 63166 Mr. Harold Lottman A. Scott Cauger, Esq. Presiding Judge, Dasconade County Assistant General Counsel for the Route 1 Missouri Public Service Com. Owensville, Missouri 65066 Post Office Box 360 Jef'erson City, Missouri 65101 Mr. John G. Reed Route #1 Ms. Marjorie Reilly Kingdom City, Missouri 65262 Energy Chaiman of the League of Wcmen Voters of Univ. City, M0 Mr. Dan I. Bolef, President 7065 Pershing Avenue Xay Drey, Representative University City, Missouri 63130 Board of Directors Coalition for the Environment Mr. Donald Boilinger, Member St. Louis Region Missourians for Safe Energy 6267 Celmar Boulevard 6267 Delmar Boulevard University City, Missnuri 63130 University City, Missouri 63130 ~ ---

2-CALLA' A' I cc: Reg *cnal Administrator

u. 5. NRC, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

~ Mr. Ronald A. Xucera, Deputy Director Cecartment of Natural Resources P. O. Box 176 Jefferson City, Missouri 65102 Mr. Glenn L. Xcester Vice President - Nuclear Xansas Gas and Electric Ccmpany 201 North Market Street Post Office Sox 2C8 Wichita, Kansas 67201 Eric A. Eisen, Esq. Sirch, Horton, Bittner and Mccre Suite 1100 1140 Connecticut Avenue, N. W. Washington, D. C. 10036 I s ,,....d;........a,-.,-; _ m.., u _ _s _ _ %. _

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/' UNITt0 STATES NUCLEAR REGULATCRY COMMISSION N y WASHINGTON O. C. 20555 k. ~ k h 4....-, I UNION ELECTRIC COMPANY 00CKET NO. 50 a83 CALLAWAY PLANT. UNIT 1 ANENCHENT TO FACILITY OPERATING LICENSE Amendment No. 2 License No. NPF-30 1. The Nuclear Regulatory Ccmission (the Comission) has found that: i I A. The application for amendment b Union Electric Company (the licensee), dated October 3,1984, as suoplemented December 6,1984 and k December 27, 1984, ccmolies with the standards and requirements of tne Atcmic Energy Act of 1951, as amended (the Act), and the Ccmission's rules and regulations set forth in 10 CFR Chapter I-I The facility will operate in conformity with the appif cation, the S. provisions of the Act, and the rules and regulations of the Ccmission; C. There is reasonable assurance (i) that the activities authori::ed by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in comoliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by a change to the Technical Speciff-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Operating License No. NPF-30 is hereby amended en read as follows: (2) Technical Saecio cations and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Artendment No. 2, and the Environmental Protection Plan contained in Appendix R, both of which are attached hereto, are j herebv incorporated intn this licanse. UE shall operate the facility in accordarce with the Technical Specificar. inns and the Environmental Protection Plan. f f

Atttchment 4 2 l I This license amencment is effective as of the date of its issuance. 3. FOR NUCLEAR REGULATORY CCNMISSION 2 S< ~ B. d. _oungbl od, Chief Lichn ing Br nch No. 1 DiviponofLicensing

Attachment:

Change to the Technical Specifications Date of 'ssuance: February 4, 1995 ) 1 n..~-

Attachm:nt 4 l AT ACH. MEN 7 'O LICENSE AMENDNEtl* ?!O. ? OPERATING LICENSE NO. NPF-30 DOCKET NO. STN 50-4P,3 Revise A:pendix A, as follows. 4 REPOVE INSERT 3/4 1*-2 3/4 11-2 s \\ s I

,-{ R f TA8LE 4.11-1 r RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OFDETECTg LIQUID RELIASE. SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD) TYPE FREQUENCY FREQUENCY ANALYSIS (pCl/ml)

1. Bat:n Maste P

P 7 Release Each Batch Each Satch Principal Gamma 5x10 Tanks (2) Emitters (3) -6 I-131 lx10 'a. Wasta Monitor -5 Tank ,P M Dissolved and lx10 One 8atch/M Entrained Gases (Gamma Emitters)

b. Secondary Liquid

-5 Wasta P M H-3 1x10 Monitor Each Batch Composite (#) 7 Tank Gross Alpha 1x10

c. Disc arge P

Q Sr-89, Sr-90 5x10'S ) Monitor aEaca Batch Composite (4) ~0 Tank Fe-55 lx10 -7

2. Continuous W

Principal Gamma 5x10 Releases (') Daily (6) Composite (4) Emitters (3) Grab Sample i ~0 I-131 lx10 Steam Generator 5 l Slowdown M M Dissolved and 1x10 i Grab Sample Entrained Gases (Gamma Emitters) ~5 M H-3 lx10 Daily (6) Composite (#) Grab Samole Gross Alpha lx10 j -8 Q Sr-89, Sr-90 5x10 Daily (6) CcapositeI4) 4 i Grab Sauple Fe-55 1x10 ) CALLAWAY - UNIT 1 3/4 11-2

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lttachment 4 ?p*a.., *, unirso n M Es [N. \\ NUCLEAR REGULATORY COMMISSION mssincres a c.:osss m....- 5AFET EVALUATION SY THE CFFICE OF HNLEAR 2CACTOR REG::LATI St.:CRTING AMEN 0 MENT NO. ? TO FACILITY OPERATING LICENSE UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. STN 50 483

1.0 INTRODUCTION

Sy letter dated Octocer 3,1984, as supplemented December 5,1984 and Dececcer 27, 1984, amendment to Facility Operating License No. NPF-30 for operation of the Callaway Plant in Callaway County, Missouri. ) The amendment would modify Table 4.11-1 of the Callaway Technical Specifications (TS) to include two additional Batch Waste Release p i \\ Tanks. 2.0 E'/AL"ATION ) 100,000 gallon tanks for The licensee requested the addition of two i the purpose of storing liquid waste generated from the secondary coolant This waste water originates from the condenser hat well sluice water. and is used as the working fluid to transport resins from the condensate 3 demineralizers ir.tc the ccndensate demineralizer regeneration system, anc also to carry acid and caustic into the samp system. As this sluice water leaves the condensate demineralizer regeneration system, it contains accunts of dissolved solids and conductivity that is unacceptable for The returning to the condenser hot well without additional treatment. seconcary liquid waste system cassesses the flexibility to either process this water through an evacorator and/or demineralizer so that it can be returned to the condenser hatwell, or to directly discharge the untreated water to the river. In a telephone conversation on Decemoer 19, 1984, Union Electric stated that if this stream contains radioactivity, as determined by sampling and/or monitoring of the secondary waste discharge, it would ce redirected through the secondary waste evaporators and remineralizers at which time However, because it would then be returned to the condenser hc t well. there normally is insignificant radioactivity in this stream, Union Electric has chosan, for financial censidera' ions, to t'v-pass the secondary waste evaporator and demineralizers and dir arr]e the water to the eavi-nnrent ani!a making up Ge lou c cenc nsate by evace.:cchod. 3 To <<ure releases arn wi.hin technical sca i ficacico radinac'.iv i *v.wd 1:FDEI limits, Union Electric will add stora je tanks (twn 100,000 g'allon tanks) in parallel with the two existing ss condary iIquid wasta monitor tanks (15,000 gallons each) to provide suf ficient ti:ne for samoling and analyses prior to discharge. , ~ w-. w g., ~ .~

2 t ns : a" finds the design :aane M.idd M:n '.00,GP a l len d i ;c m e ;e man r tank: Iad :ne associc?c Tecnnical Spe :i fic:rw caangs :o be ac:so: b'e. This conclusion is based on the followinc Scts: a) Even though the secondary waste evaporator and demineralizers are oy-cassed, there will only be an insignificant increase in racinactivity release via this stream. b) All seccndary waste is sampled and monitored for radioactivity prior to and during releases. c) Releases of secondary waste pollutants (such as radioactivity, chemicals and total dissolved solids) is limited by Technical Specification and NPDES limits. d) Prc:er tank protection features meeting the recuirements of Regulatory Guide 1.143 for radioactive wasta treatment systems are ornvided. e) All radioactive effluents are limited by Technical Specifications. This amendment does not affect these limits.

3.0 ENVIRONMENTAL CONSIDERATION

N This amendment involves a change in the installation or use of a facility ccmconent located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant cnange in the types or significant increase in the amounts of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation excesure. The Ccmmission has previously issued a procosed finding that this amercment invcives no significant hazards consideration and there has been no puclic commen-on such ff.iding. Accordingly, this amendment mee s the eligibiiicy criteria for categorical exclusion set forth in 10 CFR Section 51.22(cHN. An environmental assessment was.crecared for this amencmen: request (49FR50848) in which it was determined that an environmental impact statement was not required for bis action. 4.0 CONCUJSION We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; anc (2) such activities will be conducted in ccmpliance witn the Commission's regulations and the issuance of this amendment will not be inimical to the ccman defense and security or to the health and safety of the public. Date: February 4,1985 Principal Contribatcrt: R. W. Feli. METB J. A. Stevens, L2+1 8 3

d. N.

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AT AC'c3.E:iT 3 PROCESS CCliT20L PRCGRR4 CHANGES This Attaci=ent centains the following: 1. Callaway Plant ORC Sfeeting Stinutes (applicable sections) page i through 3 2. Process Control Progras Precedure Request For= Package page i through 5 l J s 4 l l l ls - i.. '4.sf n s ... C i k[.M N*YE * [k'. d..- 2__Y _ ~ _ _ _ _N]_'_?_] _ "_ __ y_

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• e=s =ust be rescheduled fer ft:nre =eetings.

Disappr= val and Open za:egeries =us have su: porting rationale attached in wr.:ing. Dissen:=g sp=icr.s recuire an at: ached sca:e=en: of reason. A: a:hed pages shall be uniquely identified by indicating in a pre =en: =anner the =eeting nu=her :he date and page nu=ber of :he a::ac==en: :o :his f= =. ':RC Chai_ an!"i e-2"nair:an Cis:ribucica ORC File - v/A::ach=ents (QA Record) Me=bers - w/ Attach =cncs Esd - v/A::ach=ents Su:t.. raining - v/A::ach=en:s ~~ 5EG - w/A:~ach:en 3 CA-#138 02/11/84 APA-Z -00050 '"his is page ! of of -he =inu:es fer :his =ee:in- = ~ 1 s l S$' .*.56 4 & ~.*.%.tL,%)..~. m * . j ',e .t .t- ,, t a. <a a.

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ATTACIE;T 3 y 'l Page 1 of .i/ OQR-x h id -Lw.UbN. DATE: 7, b T[ 4 j d3 CM: n 1 c

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@h s \\ i co 'l> Rev. NO.: .CCEDURE NC.. TERENCES: PROCEDURE COSD!ENT SHEET ate: For any comment listed, there must be an Action and Approval. ACTION TAKEN ACTION l 2MMENTS ACCEPTABLE t b tc *bw \\ J i A, ' A sL4 Lt'4 di y( _. -@ k Submitted by: / tW i av.. w w ATTACH TO PROCEDURE REQUES~ TORM1 I \\ Oc: AD5R AD t'7 F0 7 (w/ccccents) Line ~-.:~.

-C ( q" \\ .+< T eaa M 3ECTRIC COMPANY 1901 Gratiot Street St. Louis August 29, 1985 hid F. N Vice President P_AICRITY ROUTING hhW-l*s mL ! ny -se.g f!F~ s ~ L n s Mr. James G. Keppler M- &}{- $&c [} LW rB' J-i i Regional Administrator Office of Inspection & Enforcement FILE W ~ U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 ULNRC-ll63

Dear Mr. Keppler:

DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 FACILITY OPERATING LICENSE NPF-30 SEMI-ANNUAL RADIOACTIVE EFFLUENT REPORT The enclosed Semi-Annual' Effluent Report for the 4 first half of 1985 is submitted pursuant to section 6.9.1.7 of the Callaway Unit 1 Technical Specifications. Very truly yours, I Donald F. Schnell i l l' t ' f,' I t W

1. p SEP 9 1985.

Mailing Address RO Box 149. St Louis MO 63166 b_

r cc distribution for ULNRC-ll63 with enclosures Director, Resource Management U. S. Nuclear Regulatory Commission Washington, DC 20555 Director Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Bill Kesler Regional Administrator Jefferson City Regional Office Department of Natural Resources P. O. Box 1368 Jefferson City, MO 65102 NRC Resident Inspector Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 (18 enclosures) ,,ene,,;;1cy;J.!h;ika i-j-tgeh;giigW%f-2,g@h. h$ghb gi...-.- -f7 _ "a ,,}}