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Category:NON-RECURRING TECHNICAL REPORT (ENVIRONMENTAL)
MONTHYEARML20211Q0071986-12-31031 December 1986 Rept on Reactor Vessel Matl Surveillance Capsules, for 1986 ML20079N1941985-01-31031 January 1985 Demonstration Final Rept Jan 1985 ML20079N2761985-01-15015 January 1985 Final Rept Crystal River 316 Studies,850115 ML20090G4881984-07-16016 July 1984 Fourth Quarterly Progress Rept,Crystal River Studies 840702 ML19207B4651979-04-19019 April 1979 Draft Offsite Dose Calculation Manual ML19319D2001978-03-22022 March 1978 Environ & Cost/Benefit Assessment for Facility High Density Spent Fuel Storage Racks. ML19308D6541976-05-31031 May 1976 App 1 Analysis for Facility. ML19319D1321975-06-20020 June 1975 Predicted Thermal Plume Resulting from Operation of Units 1,2 & 3. ML19319D1551975-02-28028 February 1975 Summary Analysis & Supplemental Data, Rept to Interagency Research Advisory Committee ML19319D1381974-10-31031 October 1974 Environ Considerations, Vol 1, Final Rept to Interagency Research Advisory Committee ML19319D1431974-10-31031 October 1974 Environ Considerations, Vol 2,final Rept to Interagency Research Advisory Committee ML19319D1451974-10-31031 October 1974 Environ Considerations, Vol 3,final Rept to Interagency Research Advisory Committee ML19319D1491974-10-31031 October 1974 Environ Considerations, Vol 4,final Rept to Interagency Research Advisory Committee ML19308D9941973-07-31031 July 1973 Proposed Plankton & Water Quality Programs at Facility. ML19308D6421973-07-13013 July 1973 Verification Study of Dames & Moore Hurricane Storm Surge Model. ML19308D6671973-07-11011 July 1973 Facility Hurricane Study. ML19308D8281973-06-11011 June 1973 Facility Environ Research Program to Meet Current Federal Requirements. ML19308D7551973-03-0505 March 1973 Environ Research Programs at Facility:Technical Discussion. 1986-12-31
[Table view] Category:TEXT-ENVIRONMENTAL REPORTS
MONTHYEARML20217E3991999-10-12012 October 1999 Rev to App B Environ Protection Plan TS Pages,Incorporating Biological Opinion Issued by Natl Marine Fisheries Svc. Requirements from Biological Opinion Issued by Natl Marine Fisheries Svc 3F0999-26, NPDES Noncompliance Notification:On 990826,permitted Release of SDT-1 (I-FG) to Nuclear Svcs Seawater Sys (D-OF), Occurred.Required Sample Not Obtained Due to Failure of Technician to Collect Sample.Release of SDT-1 Was Diluted1999-09-28028 September 1999 NPDES Noncompliance Notification:On 990826,permitted Release of SDT-1 (I-FG) to Nuclear Svcs Seawater Sys (D-OF), Occurred.Required Sample Not Obtained Due to Failure of Technician to Collect Sample.Release of SDT-1 Was Diluted 3F0899-22, NPDES Noncompliance Notification:On 990714,cooling Towers Tripped Off Line.Caused by Failure of Transformer Providing Power to Cooling Towers Pumps.Reduced Load Causing Temp Measured at Point of Discharge to Begin Trending Downward1999-08-30030 August 1999 NPDES Noncompliance Notification:On 990714,cooling Towers Tripped Off Line.Caused by Failure of Transformer Providing Power to Cooling Towers Pumps.Reduced Load Causing Temp Measured at Point of Discharge to Begin Trending Downward ML20209H9641999-07-15015 July 1999 Environ Assessment & Finding of No Significant Impact Re Issuance of Exemption That Would Reduce Amount of Onsite Property Insurance Based on Permanently Shutdown Status of TMI-2 & That Plant Suitable for Long Term Management ML20202A7051999-01-0808 January 1999 Revised NPDES Permit FL0000159,issued to FPC ML20206R6281998-12-31031 December 1998 1998 Annual Radiological Environ Operating Rept for Crystal River,Unit 3 ML20206A9191998-12-31031 December 1998 FPC Annual ITS Dose Rept for Period Jan-Dec 1998 ML20206F5541998-12-31031 December 1998 Radioactive Effluent Release Rept - 1998 3F0798-19, NPDES Noncompliance Notification:During June 1998,limit of Copper from Fl State Water Quality Standard Fl Admin Code 62-302.530 Was Exceeded.Potential Resolutions to Issue Are Being Investigated by FPC1998-07-28028 July 1998 NPDES Noncompliance Notification:During June 1998,limit of Copper from Fl State Water Quality Standard Fl Admin Code 62-302.530 Was Exceeded.Potential Resolutions to Issue Are Being Investigated by FPC 3F0698-13, NPDES Noncompliance Notification:On 980502,observed Small Kemp'S Ridley Turtle Lodged Against Plant Intake Structure Bar.Efforts to Rescue Turtle Failed & Dead Turtle Was Found on 980512.Established 24 H Observation & Rescue Program1998-06-0808 June 1998 NPDES Noncompliance Notification:On 980502,observed Small Kemp'S Ridley Turtle Lodged Against Plant Intake Structure Bar.Efforts to Rescue Turtle Failed & Dead Turtle Was Found on 980512.Established 24 H Observation & Rescue Program 3F0598-03, NPDES Noncompliance Notification:On 980401,util Reported Mortality of Endangered Species Sea Turtle.Cause Unknown. Contributing Factor Could Be Change in Prey Abundance. Established 24 H Observation1998-05-0101 May 1998 NPDES Noncompliance Notification:On 980401,util Reported Mortality of Endangered Species Sea Turtle.Cause Unknown. Contributing Factor Could Be Change in Prey Abundance. Established 24 H Observation 3F0398-27, NPDES Noncompliance Notification:On 980223,sample Was Discarded Before Apparent Exceedence Was Recognized Preventing Reanalysis.Caused by Analytical Procedure. Procedure Will Be Changed to Include Noted Value Types1998-03-26026 March 1998 NPDES Noncompliance Notification:On 980223,sample Was Discarded Before Apparent Exceedence Was Recognized Preventing Reanalysis.Caused by Analytical Procedure. Procedure Will Be Changed to Include Noted Value Types 3F0598-05, Annual Radiological Environ Operating Rept for 1997, for Crystal River 31997-12-31031 December 1997 Annual Radiological Environ Operating Rept for 1997, for Crystal River 3 3F0498-08, FPC Annual ITS Dose Rept for Period 970101-12311997-12-31031 December 1997 FPC Annual ITS Dose Rept for Period 970101-1231 ML20206F5591997-12-31031 December 1997 Revised Crystal River Unit 3 Radioactive Effluent Release Rept - 1997 ML20247A3461997-12-31031 December 1997 Radioactive Effluent Release Rept - 1997 ML20211F8391997-09-29029 September 1997 Add 1 to NPDES FL0000159/IT09-154804F for Plant Re Wastewater Generated at Outfall Serial Number 015 (Osn 015) from Mariculture Ctr (Fish Hatchery) ML20151K1451997-07-31031 July 1997 NPDES Noncompliance Notification:Effluent Discharge Data for June 1997 Indicated Biological Oxygen Demand for Five Days Value of 12.0 mg/1.Caused by Mixing W/Water in Ditch Sys ML20151K1531997-07-31031 July 1997 NPDES Noncompliance Notification:Effluent Discharge Data for June 1997 Indicated Instantaneous Max Temp of 97.2 F.Caused by Inoperative Tide Level Indicator,Incoming Tide & Westerly Wind.Tide Level Indicator Returned to Service ML20210S4721997-07-31031 July 1997 Addendum 1 to NPDES Permit FL0000159/IT09-15480F for Plant to Wastewater from Fish Hatchery ML20151K1581997-07-31031 July 1997 NPDES Noncompliance Notification:On 970623,sample Obtained Indicated Exceedence of POD Oil & Grease.Caused by Ommission of Analytical Procedure.Steps Will Be Taken to Determine Technician'S Error 3F0597-01, FPC Crystal River,Unit 3 Annual Radiological Environ Operating Rept,19961996-12-31031 December 1996 FPC Crystal River,Unit 3 Annual Radiological Environ Operating Rept,1996 ML20138G7281996-12-31031 December 1996 Radioactive Effluent Release Rept 1996 3F0497-06, FPC Annual STS Dose Rept for Period 960101-12311996-12-31031 December 1996 FPC Annual STS Dose Rept for Period 960101-1231 ML20108C5851995-12-31031 December 1995 Radioactive Effluent Release Rept 1995 FPC Crystal River - Unit 3 3F0596-09, 1995 Annual Radiological Environ Operating Rept1995-12-31031 December 1995 1995 Annual Radiological Environ Operating Rept 3F0496-29, Whole Body Exposure for CY951995-12-31031 December 1995 Whole Body Exposure for CY95 3F0495-20, Radioactive Effluent Release Rept 1994 Crystal River Unit 31994-12-31031 December 1994 Radioactive Effluent Release Rept 1994 Crystal River Unit 3 3F0595-15, Annual Radiological Environ Operating Rept 19941994-12-31031 December 1994 Annual Radiological Environ Operating Rept 1994 3F0294-20, Semiannual Radioactive Effluent Release Rept Jul-Dec 1993 for Crystal River Unit 31993-12-31031 December 1993 Semiannual Radioactive Effluent Release Rept Jul-Dec 1993 for Crystal River Unit 3 3F0893-15, Semiannual Radioactive Effluent Release Rept,Crystal River, Unit 3 for Jan-June 19931993-06-30030 June 1993 Semiannual Radioactive Effluent Release Rept,Crystal River, Unit 3 for Jan-June 1993 ML20128D7431993-01-31031 January 1993 Us EPA Permit FL0000159 Semi-Annual Rept, for Jan 1993 ML20012G4621992-12-31031 December 1992 Semiannual Radioactive Effluent Release Rept,Crystal River Unit 3 for Jul-Dec 1992. W/930225 Ltr 3F0892-10, Semiannual Radioactive Effluent Release Rept for Jan-June 19921992-06-30030 June 1992 Semiannual Radioactive Effluent Release Rept for Jan-June 1992 3F0292-14, Semiannual Radioactive Effluent Release Rept Jul-Dec 19911991-12-31031 December 1991 Semiannual Radioactive Effluent Release Rept Jul-Dec 1991 3F0492-14, Annual Radiological Environ Operating Rept for 19911991-12-31031 December 1991 Annual Radiological Environ Operating Rept for 1991 ML20092F5521991-12-31031 December 1991 Whole Body Exposure for Calendar Yr 1991 ML20082K7901991-06-30030 June 1991 Semiannual Radioactive Effluent Release Rept 910101-0630 3F0491-08, 1990 Annual Radiological Environ Operating Rept1990-12-31031 December 1990 1990 Annual Radiological Environ Operating Rept 3F0291-12, Semiannual Radioactive Effluent Release Rept for Jul-Dec 19901990-12-31031 December 1990 Semiannual Radioactive Effluent Release Rept for Jul-Dec 1990 ML20059D7761990-06-30030 June 1990 Semiannual Radioactive Effluent Release Rept for Jan-June 1990 for Crystal River Unit 3 ML20042F1411989-12-31031 December 1989 1989 Annual Radiological Environ Operating Rept. W/900430 Ltr ML20012A4061989-12-31031 December 1989 Whole Body Exposure for CY89. ML20012B5551989-12-31031 December 1989 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1989, Crystal River Unit 3. W/900227 Ltr 3F0889-11, Semiannual Radioactive Effluent Release Rept,Jan-June 19891989-06-30030 June 1989 Semiannual Radioactive Effluent Release Rept,Jan-June 1989 3F0289-17, Semiannual Radioactive Effluent Release Rept,Jul-Dec 19881988-12-31031 December 1988 Semiannual Radioactive Effluent Release Rept,Jul-Dec 1988 ML20247M1611988-12-31031 December 1988 Offsite Radiation Dose Assessment for Jan-Dec 1988 ML20235E7091988-12-31031 December 1988 Whole Body Exposure for CY88 3F0489-19, Annual Radiological Environ Operating Rept,19881988-12-31031 December 1988 Annual Radiological Environ Operating Rept,1988 ML20153G1091988-06-30030 June 1988 Semiannual Radioactive Effluent Release Rept for Jan-June 1988 1999-09-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
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DRAFT OF CRYSTAL RIVER - UtilT 3 0FFSITE DOSE CALCULATI0t1 fMfiUAL APRIL 19, 1979 (for use with Draft of Crystal River - Unit 3 Technical Specifications, April 19,1979, Based on NUREG-0472, Revision 2, February 1978) e 853 221 7908290506 ,
TABLE OF CONTENTS 1.0 Introduction 2.0 Radioactive Liquid Effluent Instrumtr.t ? tion Setpoints (Speci fication 3.3.3.8) 3.0 Radioactive Gaseous Process and Effluent Instrumentation Setpoints (Specification 3.3.3.9) 4.0 Radioactive Liquid Effluent Releases and Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) 4.2 Radioactive Liquid Effluent Projected Dose (Specification 4.11.1.3) 5.0 Radioactive Gaseous Effluent Dose Caiculations 5.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1) 5.2 Radioactive Gaseous Effluent Other Than Noble Gas Dose Rate (Speci fIcation 4.11.2.1.4) 5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Speci fication 4.11.2.2) 5.4 Radioactive Gaseous Effluent Other Than Noble Gas Cumulative Dose (Specification 4.11.2.3) 5.5 Radioactive Gaseous Effluent Projected Dose (Speci fica tion 4.11.2.4.1) 6.0 Radiological Environnental Monitoring 6.1 Replacement of Sample Locations (Specification 3.12.1, Action c) 6.2 Census Results (Specification 3.12.2, Actions a and b) 7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports (Specification 6.9.1.9) 8.0 Revisions to the ODCM (Specification 6.14.2) 853 222
1.0 Introduction This Offsite Dose Calculation Manual (0DCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable Limiting Conditions for Operation (LCOs) contained in the Appendix A Technical Specifications for Crystal River Unit 3, 853 223
2.0 Radficactive_ Liqui.d Ef fluent Instrumentation Setpoint Specification 3.3.3.G 3.0 Radoiactive Gaseous Process and Effluent Instrumentation Setpoints Specification 3.3.3.9)
The radiological effluent Technical Specifications require alann/ trip setpoints fer radiation monitors and flow measurement devices for each
~
effinc ut line. Mpoint values are to be calculated to assure that alani and trip actions occur prior to exceeding the limits of 10 CFR 20 a? the release point to the unrestricted area. The calculated alann and trip action setpoints to be specified in the ODCM for each radioactive liquid effluent line monitor and flow measurement device must satisfy the following equation:
cf Rf $ C where:
C= the cffluent concentration limit (Specification 3.11.1) implementing 10 CFR 20 for the site, in uCi/ml c= The setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentracion in the effluent line prior tc dilution and subsequent reiease; the setpoint, which is propo.-tional to the volumetric flow of the effluent line and inversely proportional to the volumetric flow of the dilution stream plus the effTuent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area f= the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in the same units as F, below F= the dilution water flow setpoint as measured prior to the release point, in volume.per unit time.
(Note that if no dilution is pruided, c 1 C. Also, note that when (F) is large compared to (f), then F+f 2 F.)
The equation is satisfied when the following alarm / trip setpoints are provided for each effluent line in the ODCM:
f 1[F_ (in ml/sec; for example),
c F1 (in ml/sec; for example).
cf (in uCi/ml; for example).
Scme plants may be operated using a fixea value for or re of these three variables, c, f or F.
~
853 224
Eg mple 1 By using a constant capacity radwaste system discharge pump (on the undiluted stream) the value of (f) is fixed; therefore, the setpoints to be given are:
f= ml/sec (fixed)
F> ml/sec = cf/C c= xF uCi/ml I CF/f If c = 3x10-8 pCi/ml, f = 4000 ml/sec and F > 4x106 ml/sec, the radiation monitor setpoint is calculated as follows:
c 1 CF/f
,(3x10-81F = 7.5x10-12F pCi/ml.
4000-If F is measured at some value in excess of the limiting value (the 6
limiting value is 4x10 ml/sec in this exgmple), then c may be established proportionately. If F = 8x10 ml/sec, the alarm setpoint is:
c = 7.5x10-12F (uCi/ml per ml/sec)(ml/sec)
= 7.5x10-12.(8x106) = 6x10-5 pCi/ml.
In this case, the alarm setpoint for the radioactive liquid effluent line nomitor can be established at 6x10-5 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:
c/F < 7x5x10-12 pCi/ml per ml/sec.
Example 2 By using a constant capacity dilution pump (on the dilution stream prior to a mixing box), the value of (F) is fixed; therefore, the setpoints to be given are:
- < ml/sec = CF/c F= ml/sec (fixed) c= x (1/f)uCi/ml I CF/f If C = 3x10-8 uCi/ml, F = 4x106 ml/sec and f < 4000 ml/sec, the radiation monitor setpoint is calculated as follows:
c I CF/f
= (3x10-8 x 4x106 1 = 0.12(1/f) uCi/ml.
f 853 225
If f is measured at some value less than the limiting value (the limiting salue is 4000 ml/sec in this example), then c may be establisned proportionately. If f = 1000 ml/sec, the alarm setpoint is:
c = 0.12(1/f)(uCi/sec)(sec/ml)
= 0.12 = 1.2x10-4 uCi/ml.
1000 In this case, the alarm setpont for the radioactive liquid effluent line monitor can be established at 1.2x10-4 pCi/ml, provided that an automatic isolation / control trip action occurs to satisfy the condition:
cf > 0.12 pCi/sec.
Value of c A detailed description of the ethod to be used to obtain the value of (c) should be provided. Since (c) is dependent on the radionuclide distribution, yields, calibration and the monitor's parameters, each of these sariable: should be considered and the fixed or adjustable setpoint method o# determination described for each effuent monitor.
This may be accomplished by tabulation.
853 226
4.0 Radioactive Liquid Effluent Dose Calculations 4.1 Radioactive Liquid Effluent Cumulative Dose (Specification 4.11.1.2) m The dose contributions for the total time period I att shall be t=1 determined by calculation at least once per 31 days and a cumulative sumation of these total body and any organ doses shall be maintained for each calendar quarter. These dose contributions shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:
m Dt =I[Ait I att Ci g Fr]
i t=1 where:
Dt = the cumulative dose or dose commitment to the total body or an organ t fran the liquid effluents for the total time period m
I atg in mrem t=1 at g= the length of the gth time period over which Cjg and Fg are averaged for all liquid releases, in hours.
Ci g= the average concentration of radionuclide i in undiluted liquid effluent during the time period att from any liquid release, in pCi/ml.
Ait= the site related ingestion dose or dose cannitment factor to the total body or any organ t for each identified principal gamma and betta emitter listed in Table 4.1-1, in mrem-ml per hr-uCi .
Fr= the near field average dilution factor for Cig during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the produce of the average flow from the site discharge structure to unrestricted receiving water times 1.0.
For radionuclides not detennined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative summation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly canposite analyses. However, for reporting purposes, the calculated dose contributions shall be based on the actual canposite analyses.
The dose factor Ait for each nuclide, i, embodies the dose factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin.
The adult total body dose factor and the maximum adult organ dose factor for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose factor is written:
Ait = ko(Uw/Dw + UfBFi + UjBIj)DFj 853 M
where:
Ait = composite dose parameter for the total body or critical organ of an adult for nuclide, i, for all appropriate pathways, mrem /hr per pCi/ml.
ko= units conversion factor,1.14x105 = 106 pCi/uCi x 10 3ml/kg +
8750 hr/yr.
Uw = 730 kg/hr, adult water consumption (fresh water cite only).
Vf = 21 kg/hr, adult fish consumption (all sites).
Uj = 5 kg/yr, adult invertebrate consumption (salt water site only).
BFj = Bioaccumulation factor for nuclide, i, in fish (fresh or salt water site, as applicable), pCi/kg per Ci/1, from Table A-1 of Regulatory Guide 1.109 (Rev.1,10/77).
BIj = Bioaccumulation factor for nuclide, i, in invertebrates (salt water only), pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109 (Rev. 1, 10/77).
DFj = Dose conversion factor for nuclide, i, for adults in pre-selected organ, t, in mrem /pCi, from Table E-11 of Regulatory Guide 1.109 (Rev. 1, 10/77).
Dw = Dilution factor from the near field area within one-quarter mile of the release point (s) to the potable water intake for the adult water consumption (fresh water site only).
Inserting the usage factors of Regulatory Guide 1.109 (Rev.1,10/77) as appropriate into the equation gives the following expression:
Ait = 1.14x10 5(21BFj + 5BI j)DFj 853 228
~
Table 4.1-1 LIQUID EFFLUENT INGESTION DOSE FACTORS Ait Dose or Dose Conmitnent Factors BF BI Critical DF (mrem-ml per br-pCi)
Radionuclide (t/kg) (t/kg) Orga n (mrem /pCi) Total Body Critical Or9ans H-3 9.0E-01 9.3E-01 All 1.05E-07 2.80E-01 2.80E-01 Na-24 6.7E-02 1.9E-01 All 1.70E-06 4.60E-01 4.60E-01 P-32 2.9E+04 3.0E+04 Bone 1.93E-04 6.45E+05 1.67E+07 C r-51 4.0E+02 2.0e+03 GI-LLI 6.69E-07 5.58E+00 1.40E+03 Mn-54 5.5E+02 4.0E+02 GI-LLI 1.40E-05 1.35E+03 2.16E+04 Fe-55 3.0E+03 2.0E+04 Bone 2.75E-06 8.23E+03 5.llE+04 Fe-59 3.0E+0i 2.0E+04 GI-LLI 3.40E-05 7.27E404 6.32E+05 Co-58 1.0E+02 1.0E+03 GI-LLI 1.51E-05 1.35E+03 1.22E+04 Co-60 1.0E+02 1.0E+03 GI-LLI 4.02E-05 3.82E+05 3.25E+04 Zn-65 2.0E+03 5.0E+04 Liver 1.54E-05 2.32E+05 5.13E+05 Sr-89 2.0E+00 2.0E+01 Bone 3.08E-04 1.43E+02 4.99E+03 S r-90 2.0E+00 2.0E+01 Bone 7.58E-03 3.01E+04 1.23E+05 Zr-95 2.0E+02 8.0E+01 GI-LLI 3.09E-05 3.50E+00 1.62E+04 Nb-95 3.0E+04 1.0Et02 GI-LLI 2.10E-05 1.34E+02 1.51E+06 f50-99 1.0E+01 1.0E+01 GI-LLI 9.99E-06 2.43E+01 2.96E+02 Tc-99M 1.0E+01 5.0E+01 GI-LLI 4.13E-07 5.00E-01 2.17E401 Ag-llOn GI-LLI 6.04E-05 2.55E-01 1.75E+02 I-131 1.0E+01 5.0E+01 Thyroid 1.95E-03 1.79E+02 1.02E+05 I-132 1.0E+01 5.0E+01 Thyroid 1.90E-05 1.00E+01 9.96E+02 1-133 1.0E+01 5.0E+01 Thyroid 3.63E-04 3.95E+01 1.90E+04 I-135 1.0E+01 5.0E+01 Thyroid 7.65E-05 2.24E+01 4.01E+03 Cs-134 4.0E+01 2.5E+01 Liver 1.48E-04 1.33E+04 1.63E+04 Cs-137 4.0E+01 2.5E+01 Liver 1.09E-04 7.85E+03 1.20E+04 Ba-140 1.0E+01 1.0E402 GI-LLI 4.18E-05 1.08E+02 3.38E+03 cy3 La-140 2.5E+01 1.0E+03 GI-LLI 9.25E-05 2.00E-01 5.83E+04 t;, Ce-141 1.0E+01 6.0E+02 GI-LLI 2.42E-05 3.00E-01 8.86E+03 tsa Ce-144 1.0E+01 6.0E+02 GI-LLI 1.65E-04 9.60E+00 6.04E+04 Np-239 1.0E+01 1.0E+01 GI-LLI 2.40E-05 1.91E-03 7.llE+02 N
N 4
4.2 Radioactive Liquid Effluent Projected Dose (Soecification 4.11.1.3) 853 230
5.0 Radioactive Gaseous Effluent Dose Calculations 6.1 Radioactive Gaseous Effluent Noble Gas Dose Rate (Specification 4.11.2.1.1)
- a. Release rate limit for noble gases:
E [Kj (x/Q) Qj] < 500 mrem /yr, and i .
I [(Lj + 1.1 Mj)(x/Q) Qj)] < 3000 mrem /yr i mrem /yr where:
Kj = The total body dose factor due to gamma emissions for eqch identified noble gas radionuclide, in mrem /yr per uCi/mo.
Lj = The skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, iij = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 (unit conversion constant of 1.1 mrem / mrad converts air dose to skin dose).
Qi = The release rate of radionuclides, i, add in gaseous effluent from ail release points at the site in pCi/sec.
(x/Q) = sec/m3 The highest calculated annual average relative concentration for any area at or bayond the exclusion area bounda ry.
5.2 Gaseous Effluents Other than Noble Gas Dose Rate (Specification 4.11.2.1.4)
Release rate limit for all radionuclides and radioactive materials in particulate fonn and radionuclides other than noble gases:
I Pj [W Qj] < 1500 mrem /yr i
where:
Pj = The dose factor for radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases for the inhalation pathway, in mrem /yr oer aCi the food and ground plane pathways in /yr) m2 (mrem per /m3 and fo pCi/sec from Tchle 4.11-4. The dose factors are based on the critical individual organ and most restrictive age group (i nfa nt) .
W= The high calculated annual average dispersion parameter for estimating the dose to an individual at the controlling location:
W= sec/m3, for the inhalation pathway. The location is the exclusion area boundary in the sector.
853 231
W= meter-2, for th- food and ground plant pathways.
The location is the exclusion area boundary in the sector.
Qj = The release rate of radionuclides, i, add in gaseous effluent from all release points at the site in uCi/sec.
853 232
SPECIAL NOTES: (1) In all cases, the tritium relgases use the first W parameter, based on relative concentration (sec/m ). (2) All radio-iodines are assumed to be released in elemental form. If analysis includes the capability of detemining elemental and nonelemental foms in all releases, the food pathway rarameter may be adjusted accordi ngly.
The dose rate from the ith radionuclide (except tritium) is:
Pj(inhalation)(x/Q) Q + [Pj(food) + Pj(ground plant)] (F/iJ) Q (mrem /yr) and for tritium, is:
Pj (inhalation)(x/Q) Q + P j(food)(x/Q) Q = 3.0 x 10 (x/Q) 3 Q (mrem /yr)
Calculation of P4 (Inhalation)
Pj = K'(BR) DFAj (mrem /yr per pCi/m3) where:
K' = a constant of unit conversion,106 pCi/pCi.
BR = the breathing rate of the infant age group, in m /yr.3 DFAj = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFA j.
is the infant group. The infant's breathing The age group considereg/yr rate is taken as 1400 m from Table E-5 of Regulatory Guide 1.109 (Rev. 1, 10/77). The inhalation dose factors for the infant, DFAj are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem /pC1.
Resolution of the units yields:
Pj (inhalation) = 1.4 x 109 DFAj Calculation of Pi (Ground Plane)
Pj = K'K"DFGj (1-e-Ai t)Aj (m2 . mrem /yr per pCi/sec) where:
K' = a constant of unit conversion,106 pCi/pCi.
K" = a constant of unit conversion, 8760 hr/ year.
Aj = the decay constant for the ith radionculide, sec -1 t = the exposure period, 3.15 x 10 sec7 (1 year).
DFGj = the ground plane dose conversica factor for the ith radionculide (mrem /hr per pCi/m').
853 233
The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for the ith radionuclide, DFG-are presented in Table E-6 of Regulatory Guide 1.109 (Rev.1,10/7f),,
in units of mrem /hr per pCi/m2 ).
Resolution of the units yields:
Pj (Ground) = 8.76 x 199 DFGj (1-e-Ai t)f39, Calculation of P4 (Food)
Q P j = K ' r _F(Vap) F 0Fl i [e-A tif
] y2. mrem /yr per uCi/sec)
Yp TAj+Aw ) m where:
K' = a constant of unit conversion 106 pCi/uCi.
QF = the cow's consumption rate, in kg/ day (wet weight).
Uap = The infant's milk consumption rate, in liters /yr.
Yp = the agricultural productivity by unit ared, in kg/m2 ,
Fm = the stable element transfer coefficients, in days / liter, r = fraction of deposited activity retained on cow's feed grass.
DFLj = the maximum organ ingestion dose factor for the ith radionuclide, in mrem /pCi.
Aj = the decay constant for the ith radionuclide, in sec -1 Aw = the dacay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-time),
tf = the transport time from pasture to cow, to milk, to infant, in sec.
A fraction of the airborne deposition is captured by the ground plant vegetation cover. The captured material is removed from the vegetation (grass) by both radiological decay and weathering p rocesses.
The values of QF, Va o, and Y are provided in Regulatory Guide 1.109 (Rev.1,10/77), Tables E-3,pE-5, and E-15, as 50 kg/ day, 330 liters / day and 0.7 kg/m2 respectively. The value tf is provided in Regulatory Guide 1.109 (Rev.1,10/77), Table E-15, as 2 days (1.73 x 10 seconds). The fraction, r, has a value of 1.0 for radiciodines and o.2 for particulates, as presented in Regulatory Guide 1.109, (Rev. 1, 10/77), Table E-15.
853 234
Table E-1 of Regulatory Guide 1.109 (Rel,10/77) provides the stable element transfer coefficients, F m, and Table E-14 provides the ingestion dose factors, DFLj , for the infant's organs. The organ with the maximum value of DFLj is to be used.
Resolut. ion of the units yields:
Pj (food) = 2.4 x 10 10 % DFLj[e-A if t ](m . 2mrem /yr per uCi/sec)
A i 'A w f;r all radionuclides, except tritium.
The concentration of tritium in milk is based on its airborne concentration rather than the deposition rate.
Pj = K'K"F 0 Um F apDFLj [0.75(0.5/H)] (mrem /yr per pCi/m3 )
where:
K'" = a constant of unit conversion,103 gm/kg.
H = absolute humidity of the atmosphere, in gm/m3 ,
0.75 = the fraction of total feed that is water.
0.5 = the ration of the specific activity of the feed fass water to the atmospheric water.
From Table E-1 and E-14 of Regulatory Guide 1.lg9 (Rev.1,10/77), the values of Fm and DFLj for tritium are 1.0 x 10- day / liter and 3.08 x 10-7 mrem per pC , respectively. Assuming an average ab. solute humidity of 8 grams / meter {, the resolution of units yields:
Pi (food) = 2.4 x 103 mrem /yr per uCi/m3 for tritium, only.
853 235
5.3 Radioactive Gaseous Effluent Noble Gas Cumulative Dose (Specification 4.11.2.2)
The air dose due to noble gases released in gaseous effluents from the site shall be limited during any calendar quarter to the following expressions:
For gamma radiation:
3.17 x 10-8 EMj ((x/Q) Qj + (x/q) gj) 15 mrad, and i
for beta radiation:
3.17 x 10-8 I Nj ((x/Q) Qj + (x/q) gj) i 10 mrad i
where:
3.17 x 10-8 = The inverse of the number of seconds in a year.
M j = The air dose factor due to gamma emissions for eagh identi-fied noble gas radionuclide, in mrad /yr per uCi/m f rom Table 4.11-3.
each identified Nj = The nobleairgas dose factor due in radionuclide, to mrad beta emissions fog from Table
/yr per pCi/m 4.11-3.
x/Q = sec/m3 . The highest calculated annual average relative concentration for any area at or beyond the exclusion area boundary for long term releases (greater than 500 hrs / year).
x/q = sec/m3 . The relative concentration for any area at or beyond the exclusion area boundary for short term releases (equal to or less than 500 hrs /yr).
Qj = The release of noble gas radionuclides, i, in gaseous effluents, for long term releases (greater than 500 hrs /yr),
in pCi. Releases shall be cumulative over the calendar qua rte r.
qj = The release of noble gas radionuclides, i, in gaseous effluents, fer short term releases (equal to or less than 500 hrs /yr), in uCi. Releases shall be cumulative over the calendar quarter.
853 236
5.4 Radioactive Gaseous Effluent Other than Noble Gas Cumulative Dose Specification 4.11.2.3)
The dose to an individual from radiciodines, radioactive materials in particulate fonn and radionuclides other than noble gases in gaseous effluents released to unrestricted areas shall be limited during any calendar year to the following expression:
3.17 x 10-8 I Rj (W Qj + w gj ) f 7.5 mrem, and i
where:
3.17 x 10-8 = The inverse of the number of seconds in a year.
Qj = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for long term releases (greater than 500 hrs /yr), in pCi. Releases shall be cumulative over the calendar quarter or year as appropriate, qj = The release of radiciodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, i, for short tenn releases (equal to or less than 500 hrs /yr), in pCi . Releases shall be cumulative aver the calendar quarter or year as appropriate.
W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location for long tena releases (greater than 500 hrs /yr):
W= x/Q for the inhalation pathway, in sec/m3 f rom Table 4.11-6a.
W= D/Q for the food and ground plane pathways, in meters-2 f rom Table 4.11-6b.
w= The dispersion parameter for estimating the dose to at the controlling location for short term releases less than 500 hrs /yr):
w= x/q for the inhalation pathway, in sec/m3 from Table 4.11-6c.
w= D/q for the food and ground plane pathway, in meters-2 from Table 4.11-6d.
2 Rj = The dose factor for each identified radigriuclide, i, in m mrem /yr per uCi/sec or mrem /yr per pCi/m f rom Table 4/11-7.
The dose factors are based on the most critical individual organ and most restrictive age group from historical dose calculations.
853 237
For the direction sectors with existing pathways within 5 miles from the unit, use the values of Rj for these pathways. If no real pathway exists within 5 miles from the center of the building complex, use the cow-milk Rj assuming that this pathway exists at the 4.5 to 5.0 mile distance in the worst sector. If the Rj for an existing pathway within 5 miles is less than a cow-milk R at 4.5 to 5.0 miles, then use the 3
value of the cow-milk Rj at 4.5 to 5.0 miles. The values used for calculating dose contributions shall be consistent with the results of the land use census performed pursuant to Specification 3.12.2. The controlling value for each radionuclide of Table 4.11-7 shall be determined and made effective within 30 days after the completion of each required land use census. The parameters W and w shall correspond to the applicable Rj for the same sector, pathway and location con
500 HR/YR OR > 125 llR/QTR Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-L/ 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.1E-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.1E-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.lE-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.1E-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A U N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NU LJ' N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.lE-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07 u
NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.1E-07 2.0E-07 1.5E-07 1.lE-07 8.8E-08 7.2E-08 N
-P-N
TABLE 5.1-3 -
DISPERSION PARAMETER (D/Q) FOR LONG TERM RELEASES > 500 HR/YR OR > 125 HR/QTR ,
Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 2.3E-06 8.2E-07 3.6E-07 2.1E-07 1.3E-07 9.6E-08 7.3E-08 5.7E-08 4.7E-08 NNE N/A 2.3E-06 8.lE-07 3.6E-07 2.0E-07 1.3E-07 9.5E-08 7.lE-08 5.6E-08 4.6E-08 NE N/A 2.9E-06 1.0E-06 4.3E-07 2.5E-07 1.6E-07 1.1E-07 8.6E-08 6.7E-08 5.5E-08 ENE N/A 3.4E-06 1.2E-06 5.lE-07 2.9E-07 1.9E-07 1.3E-07 1.0E-07 7.9E-08 6.4E-08 E N/A N/A 1.4E-06 6.0E-07 3.4E-07 2.2E-07 1.6E-07 1.2E-07 9.2E-08 7.5E-08 ESE N/A N/A 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.4E-07 1.1E-07 8.6E-08 7.0E-08 SE N/A N/A N/A 4.3E-07 2.5E-07 1.6E-07 1.2E-07 8.9E-08 7.0E-08 5.7E-08 SSE N/A N/A N/A 3.8E-07 2.2E-07 1.4E-07 1.0E-07 7.9E-08 6.2E-08 5.lE-08 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A NW N/A N/A 2.3E-06 1.0E-06 6.lE-07 4.1E-07 2.9E-07 2.3E-07 1.8E-07 1.5E-07
[jk NNW N/A 3.4E-06 1.2E-06 5.4E-07 3.lE-07 2.0E-07 1.5E-07 1.1E-07 8.8E-08 7.2E-08 w
N
.P.
CO
2 TABLE 5.1-4 DISPERSION PARAMETER (x/q) FOR SHORT TERM RELEASES < 500 HR/YR OR < 125 HR/QTR Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 4.0-4.5 4.5-5.0
{3.5-4.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.1E-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-16 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.lE-10 5.lE-10 3.8E-10 ' 0E-10 E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.1E-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNU N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A co NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LT.
d NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N
W
TABLE 5.1-5 .'
DISPERSION PARAMETER (D/q) FOR S110RT TERM RELEASES < 500 HR/YR OR < 125 ilR/QTR Distance to the control location, in miles Sector 0 0-0.5 0.5-1.0 1.0-1.5 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N N/A 1.5E-08 4.9E-09 1.9E-09 1.0E-09 6.3E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 NNE N/A 1.8E-08 5.7E-09 2.3E-09 1.2E-09 7.3E-10 4.9E-10 3.6E-10 2.7E-10 2.lE-10 NE N/A 2.0E-08 6.4E-09 2.5E-09 1.3E-09 8.2E-10 5.5E-10 4.0E-10 3.0E-10 2.3E-10 ENE N/A 2.5E-08 8.2E-09 3.2E-09 1.7E-09 1.0E-09 7.1E-10 5.iE-10 3.8E-10 3.0E-10 E N/A N/A 1.2E-08 4.6E-09 2.4E-09 1.5E-09 1.0E-09 7.2E-10 5.4E-10 4.2E-10 ESE N/A N/A 9.lE-09 3.6E-09 1.9E-09 1.2E-09 7.9E-10 5.7E-10 4.3E-10 3.3E-10 SE N/A N/A N/A 2.lE-09 1.1E-09 6.8E-10 4.6E-10 3.3E-10 2.5E-10 1.9E-10 SSE N/A N/A N/A 1.5E-09 8.0E-10 4.9E-10 3.3E-10 2.4E-10 1.8E-10 1.4E-10 S N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SSW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A s.'SW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A W N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A WNW N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A cy3 NW N/A N/A 7.lE-09 2.8E-09 1.5E-09 9.0E-10 6.lE-10 4.4E-10 3.3E-10 2.6E-10 LJ7 L/4 NNW N/A 1.5E-08 4.8E-09 1.9E-09 1.0E-09 6.2E-10 4.2E-10 3.0E-10 2.3E-10 1.8E-10 N
LD C3
TABLE 5.4-1 -
PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES ,
Inhalation Meat Ground Plane Cow-Milk-Infant Leafy Vegetables Pathway Pathway Pathway Pathway Pathway R- R- R- Rj Radio- (mrem /yr (m2. mrem /yr (m2. mrem /yr (m2. mrem /yr (m2. mrem /yr nucliae per pCi/mh per pCi/sec) per pCi/sec) per pCi/sec) per pCi/sec)
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7.0 Assessment of Dose for Semiannual Radioactive Effluent Release Reports Specification 6.9.1.91
8.0 Revisions to the ODCM (Specification 6.14.2)
Changes to the ODCM shall be made by the following method:
- 1. Shall be submitted to the Comnission by inclusion in the Monthly Operating Report within 90 days in which the change (s) was made effective and shall contain:
- a. sufficiently detailed information to totally support the rationale for the change without berefit of additional or supplemental information. Infonnation submitted should consist of a package of those pages of 00CM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
- b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detenninations; and
- c. documentation of the fact that the change has been reviewed by the PRC and approved by the Plant Manager.
- 2. Shall become effective upon review by the PRC and approval by the Plant Manager.
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