ML20056G002

Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1993, Rev 8 to ODCM for Comanche Peak Steam Electric Station Units 1 & 2 & Rev 2 to Pcp

ML20056G002
Person / Time
Site:	Comanche Peak
Issue date:	08/27/1993
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20056G003	List: ML20056G002 ML20056G005 ML20056G007 ML20056G009
References
TXX-93303, NUDOCS 9309010141
Download: ML20056G002 (2)

Text

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File # 911 (clo)

I 10010 10160 (clo) 1UELECTRIC 953 (C' *)

954 (clo)

Ref. # 10CFR50.36a(a)(2)

WiHimm J. Cahilt,Jr.

August 27, 1993 U. S. Nuclear Regulatory Commission Attn: Document Control Room Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET N05. 50-445 AND 50-446 c SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Gentlemen:

In accordance with Section 6.9.1.4 of the CPSES Unit 1 and 2 Technical Specifications (Appendix A to License Nos. NPF-87 and NPF-89) and the CPSES Of fsite Dose Calculation Manual (0DCM), enclosed is the Semiannual Radioactive Effluent Release Report which covers the six month reporting period from January 1, 1993 through June 30, 1993.

The tabular summaries of radioactive liquid and gaseous releases are provided in the format defined in Appendix B of Regulatory Guide 1.21 Rev. 1, dated June, 1974.

During this six month reporting period there were changes to the CFSES ODCM; therefore, as required by Section 6.14c of the ODCM, a complete copy of the entire ODCH (Revision 8), current as of June 30, 1993, is included as Attachment 8.1 to the subject report.

310004 9309010141 930827 8DR ADDCK 05000445

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R PDR We N. Olive street LB. El Dallas, Texas 75201

Comanche Peak Steam Electric Station Units 1 and 2 Semiannual Radioactive Effluent Release Report January 1,1993 - June 30,1993 l

Prepared By: C der ~ [ bo Date: 8-23' 73 l E. T. Floyd, Staff H6alth Physicist Reviewed By: cm 44 b.j / Date: 3-23-i3

() D. C. Kaff Radiation Protection Supervisor Approved By: e, Date: 8.J $ '[]

R. J.' Prince Radiation Protection Manager

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TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS

1.0 INTRODUCTION

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to the offsite Dose Calculation Manual 6.3 New Locations for Dose Calculations or Environmental Monitoring 6.4 Liquid Holdup and Gas Storage Tanks 6.5 Noncompliance with Radiological Effluent Control Requirements 6.6 Resin Releases to the LVW Pond 6.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems i

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1.O INTRODUCTION This Semiannual Radioactive Effluent Release Report, for Comanche Peak Steam Electric Station Unit 1 and Unit 2, is submitted as required by Technical Specification 6.9.1.4 and Offsite

6. 9.1.4Dose Calculation for the Manual1,(ODCM) Administrative Control period January 1993, through June 30, 1993.

Information pertaining to the following areas is included in this report:

A summary of the quantities of radioactive liquid and gaseous effluents released from Unit I and Unit 2 during the reporting period in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.

A summary of solid waste shipped from Unit 1 and Unit 2 in the format shown in Appendix B ef Regulatory Guide 1.21, Revision 1, June 1974, supplemented with additional categories: class of waste (per 10CFR61), type of container (Strong Tight, HIC) and shipped and buried volumes and curies.

An explanation of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days.

Changes to the ODCM in the form of a complete, legible copy of the entire ODCM.

A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census.

A description tanks or gas of storage the events leading to liquid holdup tanks exceeding Technical Specification limits.

• A list and description of abnormal releases of radioactive material from the site to unrestricted areas.

A description of resin releases to the LVW Pond.

A description of major changes to radioactive waste treatment systems (liquid, gaseous and solid).

2.0 SUPPLEMENTAL INFORMATION 2.1 Reaulatory Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections:

2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive materials 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 mrems/yr to the whole body and less than or equal to 3000 mrems/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 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.2 Iodine-131. Todine-133, Tritium and Radioactive Material in Particulate Form The dose rate due to iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 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, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, 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 7.5 mrems to any organ, and

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

2.1.3 Licuid 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 2, 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 gCi/ml total activity.

The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

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

2.1.4 LVW Pond Resin Inventory The quantity of radioactive material contained in resins transferred to the LW pond shall be limited by the following expression:

(264/V) E; A/C; < l.0 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:

Aj =

pond inventory limit for a single radionuclide j (Curies),

Cj =

10CFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (pCi/ml),

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TABLE OF CONTENTS 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary 7.2 Abnormal Batch Liquid and Gaseous Release Summary 7.3 Gaseous Effluents--Summation of All Releases 7.4 Gaseous Effluents--Ground Level Releases 7.5 Liquid Effluents--Summation of All Releases 7.6 Liquid Effluents 1

7.7 Solid Waste and Irradiated Fuel Shipments 8.O ATTACHMENTS 8.1 Offsite Dose Calculation Manual For TU Electric Comanche Peak Steam Electric Station Units 1 and 2, Revision 8

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ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPSES Comanche Peak Steam Electric Station ECL Effluent Concentration Limit LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks REC Radiological Effluent Control SORC Station Operations Review Committee WHUT Wastewater Holdup Tanks WMT Waste Monitor Tanks iii

TXX-93303 Page 2 of 2 Finally, a copy of the current CPSES Process Control Program (PCP), Revision 2 issued March,1993, is also enclosed for your information.

Sincerely, William J. Cahill, Jr By:

D. R. Woodlan Docket Licensing Manager CLW/grp Enclosures c- Mr. J. L. Milhoan, Region IV (clo)

Resident Inspectors CPSES (2) (clo)

Mr. T. A. Bergman, NRR w/att 8.1 and PCP

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