ML20029A694
| ML20029A694 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/28/1991 |
| From: | Eenigenburg E COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20029A695 | List: |
| References | |
| 91-089, 91-89, NUDOCS 9103040042 | |
| Download: ML20029A694 (11) | |
Text
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Commonwealth Edis:n O Morris,lilinois 60450 Dresden Nuclear Power Station R.R. # 1 Telephone 815/942 2920 February 28, 1991 EDE LTR #
91-089
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Mr. A. Bert Davis Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ell n,-Illinois (0137
Subject:
Dresden Nuclear Power Station Radioactive Effluent Report NnC_ Dos k e.t s_10-10.,_10: 23 LJ0:2M Enclosed is the Radioactive Effluent Report for July through December 1990 for Dresden Nuclear l'ower Station.
' A copy of 'this report will be furnished to the NRC Resident Inspector.
Sincerely Yours, 9p
-E. D. Eenigenburg Station Manager
'Dresden Nuclear Power Station EDEtSKimam i
Enclosure cci C. Kova11 File /NRC
= File / Numerical Attached Distribution List I
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e S:mi Annus1 Report Distribution All Stations Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station (1-137 Washington D.C. 20555 (Original plus one copy) 4
- or -
One White Flint North
- 11555 Rockville Pike Rockville. MD 20852 1111nois Department of Nuclear Safety Office of Nuclear Facil)<r Safety 1035 Outer Park Drive Springfield, IL 62704-AN1 Librarian I - Tech Processing The Exchange. Suite 245 270 Farmington Ave Farmington, CT 06032 American Electric Power Service Corp.
Nuclear Operations Division i Riverside Plaza Columbus, Ohio 43216 (2 copies)
U.S. Environmental Protection Agency Air and Radiation Branch, Region V ilealth Physicist 230 S. Dearborn St.
Chicago, IL 60606 Illinois Environmental Protection Agency Region III - DWPC/FO$
5415 North University i
Peoria. IL 61614 Illinois Environmental Protection Agency Division et Water Pollution Control Environmental Protection Specialist 2200 Churchill Rd Springfield, IL 62706' If delivered by private carrier (i.e. Federal Express) direct carrier to the lower back area of the One White-Flint North Bldg. Mail Station P1-137 ZEDE91/48 2 of 34 i
a Semi Annual Report Distriisution All Stations (Cont'd)
Murray & Trettel, Inc Environmental Meteorologist 414 West Frontage Rd Northfield IL 60093 Teledyne Isotopes Midwest Laboratory General Managet 700 Landwehr Rd Northbrook, IL 60062 Chemistry Serviceu Chemistry Services Director 1E3?
Emergency Preparedness Emergency Preparedness Director 1237E Nuclear Quality Programs and i
Assessments Genera. Manager Suite 300 Opus III West ZEDE91/48 3 of 34
_ _ _. ~. ~. _ _ _ _. _ _
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Semi Annuni Report Distribution Dresden Station Manager Dresden
!!calth Physics Services Supervisor llealth Physics Services Dresden NRC Senior Resident Inspector
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Dresden General Electric Co Plant Manager 7555 E. Colline Road Morris. IL 60450 U.S. Nuclear Regulatory Commission Region 111 799 Roosevelt Rd.
Glen Ellyn, IL 60137 (190 Copies)
Nuclear Quality Programa Nuclear Quality Programs Engineer Dresden i
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DRESDKN NUCLEAR POWF,R STATION DOCrf,T NOS. 50-10, 50-237, 50-249 REGULATORY LIMITS Gascous Effluents - Dose This Specif icat f or it. provided to ensure that the dose at the unrestricted area boundary itom gaseous effluents from the units on site will be within the annual done limits of 10 CFR Part 20 for unreatricted areas. The annual dose li# ts are the doses assoelated with the concentrations of 10 CFR Part 20, Appendix B.
Table II.
These limits provide renconable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individuol in an unrestricted area to annual averago concentrations exceeding the liroits specified in Appendix B, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)).
The specifitd release rete limits restrict, at all times, the corresponding gamma and betn dose rates above background to an individual at or beyond the unrestricted area bout.dary to less than or equni to 500 mrem / sar to the total body or to less than or equel to 3000 mrem / year to the siin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation p.thway to less than or equal to 1500 mtem/ year.
For purposes of calculating dones resulting from airborne releases, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode release point.
Dose, Noble Cases This Specification is provided to implement the regniremetts of Sections II.B. III.A and IV.A of Appendix 10 CFF Part
>0.
The Limiting Conditions For Operation implement the guides tiet f orth in Section 11.3 of Appendix 1.
The statements provide the required operating flexibility and at the same time isnplement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements laplement the requirements in Section III.A of Appendix I that conformance with tho guides of Appendf x 1 is to be shown by calculational procedures based on models and data such that the actuni exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.
The dose calculations established in the otCM for eciculating the doses due to the actual release rates of radioactive nobic gases in gaseous effluents will be consistent with the methodolopy provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111. "; Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"
Revision 1. July 1977.
The ODCM equations provide f or detennining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
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DRESDEN NUC1 EAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 Dose, Radiolodines, Radioactive Material lu Particulate Form and Radionuclides Other than Noble Cases This specification is provided to irnplement the requirements of Sections II.C. Ill.A and IV.A of Appendix 1, 10 CFR ! art 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.
The statements provide the required operating flexibility and at the same time Arnplement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievabic." The ODCM calculational methods specifled in the surveillance requirements implement the requirements in Section III.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways le unlikely to be substantially underestimated.
The ODCM calculational methods npproved by NRC for calculating the doseo dee to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Cornpliance with 10 CFR Part 50 Appendix 1",
i Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersian of Caseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1. July 1977.
These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.
The release rate specifications for radiciodines, radioactive material in i
particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these specifications were:
- 1) individual inhalation of airborne radionuclidts. 2) deposition of radionuclides onto green leafy vegetation with subsequent consunption by man and 3) deposition onto grassy areas where milk animals graze with consumption of the milk by man.
Gareous Waste Treatment The OPERABILITY of the gascons waste treatment which reduces amounts or concentrations of radioactive materials ensuren that the system will be available for use whenever gaseous effluents wquire treatment prior to release to the environment. The requirement tha; the appropriate l
portions of this system he operable when specified oroviden reasonable assurance that the releases of radioactive materials in gaocous effluents will be kept "as low as reasonably achievatle".
This specification implements the requirements of 10 CFR Tart 50.36a, General Design Criterlon 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix ! to 10 CFR Part 50.
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DRESDEN NUCLEAR POWER STATION DOCKET.iOS. 50-10, 50-237, 50-249 L10 TID _EEELUENIS Concentration This specification is provided to ensure the concentration of radioactive materials released in liquid waste effluents frce the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Table II, Column 2. The concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using tbc International Commission on Radiological Protection (ICRP) Publication 2. Dose This specification is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I, 10 CFR Part 504 The Limiting Conditica for Operation implements the guides set forth in Section II.A of Appendix 1. The statements provide the required operating flexibility and at the same time implement t'ie guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III. A of Appendix I that conformance wiui the guides of Appendix I be shown by calculciional procedures based on models and data such that the actual exposure of an individual through sporopriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of A;mual Doses to Man f rom Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revisie. 1, October 1977 and Lcgulatory Guide 1.113, " Estimating Aquatic Dispersior. of Effluents from Accidental and Routine Reactor Releases for the Purtone of Implementing 'ndix I", April 1977. NUREG-0113 provides rethods for dose calculew with Reg Guide 1.109 and 1.113. Liquid Waste Treatment The-operability of the liquid radwaste treatment system ensures tha' this system will be available for use whenever liquid' effluents re: .e treatment prior to release to the environment. The requirement th ; the apprope! ate portions of this system be used when specified provides . assurance that the releases of radioactive materials in liquid effluents will he kept "as low as reasonably achievable". This specification impicuents the requirements of 10 CFR Part 50 and design objective Section II.D of /ppendix I to 10 CFR Part 50. ZEDE91/48 7 of 34
.-..~ ~. _. - - - - - -. -... -..... -. -... ~. -.. - - -. - - - - DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) The concentration of radioactive materials released in gaseous and liquid effluents from the site to unrestricted areas will be less than the concentration P.s la specifled in 10 CFR Part 20, Appendix P. Columns 1 and 2. 'M concentration limit for nobic gases, MPC fu air (submersion), was e, orted to an equivalent concentration in water using the International Commission on Radiologien1 Protection (ICRP) Publication 2. MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE CASES RELEASED FROM Tile SITE TO UNRESTRICTED AREAS IN LIQUID WASTE HL!CL1DE Mt01uC1hnih Kr-85m 2.02-04 Kr-85 5.0E-04 Kr-87 4.0E-05 Kr-88 9.0E-05 Ar-41 7.0E-05 Xe-631m 7.0E-04 Xe-133m 5.0E-04 Xc-133 6.0E-04 Xe-135m 2.0E-04 Xe-135 2.0E-04 Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for _ infinite cloud submersion in water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0. 1 ZEDE91/48 8 of 34
DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 AVERAGE ENERGY The average energy of fission and activation gases was calculated for the gaseous effluents released from the site. The average energy is based on the percentage of each fission gas nuclide present and its average energy per disintegration (E in MeV/ dis) fo gamma and beta emissions separately. E = 2.48E-01 MeV/ dis g E = 3.17E-01 MeV/ dis B Radioactive Effluent Monitor: lng Equipment out of service greater than thirty consecutive days. The 2/3 Reactor Building Vent SPING was out of service f rom October 23, 1990 to December 19, 1990 'or calibration testing. The Instrument Maintenince Department encot atered equipment dificulties and were delayed with delivery of new equi;nent. The Reactor Building Vent Radiation Monitors and the Reactor Bulining Vent iodine and particulate. sampling stations were oparable during this time, i l ZEDd91'48 l 9 of 34
-.= 4 DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 Process Control Program Revision 2 Per Dresden. Technical Specifications, it is required to report revisions to the Process Control Program (PCP) in the Radioactive Release _ Report for the period in which the change was made. On September 21, 1990 Revision 2 of the PCP was reviewed and found acceptable by the On-Site Review Function of Dresden Station. The change to the PGP did not reduce the overall conformance of the solidified waste product to existing criteria for sn11d wastes. The revision to the PCP was directed by NRC Generic Letter 89-01 which specifies the transfer of Radiological Effluent Technical Specifications (RETS) to the administrative controls section of the Technical Specifications and the relocation of procedural details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program. Consistent with Generic Letter 89-01, the PCP has added Definitions and Administrative Controls sections to accommodate the relocation of RETS. Attachment A of this Semi-Annual Radioactive Effluent Report contains Revision 2 of the Process Control Program along with the On-Site Review Assignment Form and the On-Site Review Report Form to provide _the documentation that the change has been reviewed and found acceptable by the On-Site Review Function. ZEDE91/48 10 of 34
\\ I DRESDEN NUCLEAR POWER STAYION DOCKET NOS. 50-10, 50-237, 50-249 MEASURPMENTS AND APPROXIMATIONS A. Fission and activation gases: The D-1 chimney, D2/3 chimney and D2/3 Reactor Building Vent are sampled weekly via a grab sample. The samples are analyzed for speelfic isotopes present in the release using a Hyper-Pure Germanium (HP Ge) Spectrometry System. Tritium is sampled monthly via a grab sample on the D-1 chimney. D2/3 Chimney, and D2/3 Reactor Building vent and analyzed using a Liquid Scintillation Counter. Krypton-85 is estimated in the D2/3 chimney using a recoil or non-recoil calculation using the fission per second plot and the sum of Kr-85m, Kr-87 Kr-88, Xe-133, Xe-135, and Xe 138 octivities present in Reactor Off-Gas. B. Iodine and Particulate: Iodine and particulate samples from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Building Vent are collected for a maximum seven day period. These samples are analyzed for specific nuclides present in the release using a HP Ge spectrometry system. When iodine or particulate samples are not used for reporting the release rate due to management decision that the sample may not be representative, an average of the preceding sample and the following sample is used to calculate the release. A monthly composite of the particulate samples is sent to a vendor to be analyzed for Fe-55, Sr-89, Sr-90, and Groca Alpha activity. C. Liquid Effluents: Analyzed for specific isotopes present in the release-using a HP Ge spectrometry system. A coernalte of all batches for the month is sent to a vendor to be m21yzed for Sr-89, Sr-90, Fe-55 H-3, and Gross Alpha activity. A sample of each Containment Cooling Service Water (CCSW) system is analyzed each month for specific isotopes present in the release using a HP Ge spectrometry system. A sample of each CCSW system is sent each month to a vendor to be analyzed for Sr-89, Sr-90, Fe-55. H-3, and Gross Alpha activity. The September Radwaste Liquid Discharge -sample was inadvertently disposed of before analysis by the vendor therefore the average of the preceding sample and the following sample was used to calculate the release. D. Estimation of Overall Errors: The methods used for estimating overall errore associated with radioactivity measurements vary with discharto path and form of isotopes. Factors that contribute to the error incivde such items as calibra ion of counting equipment, counting statistics, sampling error, discharge volume, and flow rate monitors. 3. Estimation of Vendor Analyzed Information: The vendor analyzed -data for Sr-89, Sr-90, Fe-55. H-3 and Gross Alpha was projected, where applicable, for the months of November and December using October data. A corrected Effluant Report will be submitted with the next Semi-Annual Effluent R-eport. ZEDE91/48 11 of 34 l l _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _}}