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Category:Environmental Monitoring Report
MONTHYEARML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23047A4332023-02-16016 February 2023 Spent Fuel Storage Radioactive Effluent Release Report 2022 ML22118A0862022-04-28028 April 2022 Annual Radioactive Effluent Release Report (ARERR) ML22111A0682022-04-21021 April 2022 Annual Radiological Environmental Operating Report (AREOR) ML22053A1192022-02-22022 February 2022 Spent Fuel Storage Radioactive Effluent Release Report for 2021 GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report ML21119A1242021-04-28028 April 2021 Annual Radiological Environmental Operating Report ML20108F5752020-04-17017 April 2020 Annual Radiological Environmental Operating Report (AREOR) GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 ML19283A2592019-10-10010 October 2019 Transmittal of National Pollutant Discharge Elimination System NPDES Permit Approved on July 2, 2019 GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2018/00022, Annual Radiological Environmental Report (AREOR)2018-04-28028 April 2018 Annual Radiological Environmental Report (AREOR) GNRO-2018/00021, Annual Radioactive Effluent Release Report (ARERR)2018-04-25025 April 2018 Annual Radioactive Effluent Release Report (ARERR) GNRO-2018/00006, Spent Fuel Storage Radioactive Effluent Release Report for 20172018-02-27027 February 2018 Spent Fuel Storage Radioactive Effluent Release Report for 2017 GNRO-2017/00055, Revised Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for 20162017-09-0707 September 2017 Revised Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR) for 2016 GNRO-2017/00043, Amended Annual Radioactive Effluent Release Report (ARERR) for 20152017-07-0505 July 2017 Amended Annual Radioactive Effluent Release Report (ARERR) for 2015 GNRO-2017/00028, Annual Radioactive Effluent Release Report (Arerr)For 20162017-04-27027 April 2017 Annual Radioactive Effluent Release Report (Arerr)For 2016 GNRO-2017/00029, Annual Radiological Environmental Operating Report2017-04-27027 April 2017 Annual Radiological Environmental Operating Report GNRO-2017/00018, Spent Fuel Storage Radioactive Effluent Release Report for 20162017-03-30030 March 2017 Spent Fuel Storage Radioactive Effluent Release Report for 2016 ML16202A2352016-07-20020 July 2016 Transmittal of 2015 Annual Radioactive Effluent Release Report (ARERR) GNRO-2016/00020, Transmittal of 2015 Annual Radioactive Effluent Release Report2016-04-19019 April 2016 Transmittal of 2015 Annual Radioactive Effluent Release Report GNRO-2016/00019, Transmittal of 2015 Annual Radiological Environmental Operating Report (AREOR)2016-04-19019 April 2016 Transmittal of 2015 Annual Radiological Environmental Operating Report (AREOR) GNRO-2016/00011, Spent Fuel Storage Radioactive Effluent Release Report for 20152016-02-16016 February 2016 Spent Fuel Storage Radioactive Effluent Release Report for 2015 GNRO-2015/00028, Submittal of 2014 Annual Radioactive Effluent Release Report2015-04-27027 April 2015 Submittal of 2014 Annual Radioactive Effluent Release Report GNRO-2015/00027, Submittal of 2014 Annual Radiological Environmental Operating Report (AREOR)2015-04-23023 April 2015 Submittal of 2014 Annual Radiological Environmental Operating Report (AREOR) GNRO-2014/00037, 2013 Annual Radioactive Effluent Release Report2014-04-30030 April 2014 2013 Annual Radioactive Effluent Release Report GNRO-2013/00101, Annual Radioactive Effluent Release2014-01-0808 January 2014 Annual Radioactive Effluent Release GNRO-2013/00040, Submittal of 2012 Annual Radioactive Effluent Release Report, Revision 1 Per 10 CFR 50.36a(a)(2)2013-06-10010 June 2013 Submittal of 2012 Annual Radioactive Effluent Release Report, Revision 1 Per 10 CFR 50.36a(a)(2) GNRO-2013/00037, Annual Radiological Environmental Operating Report (AREOR)2013-05-0101 May 2013 Annual Radiological Environmental Operating Report (AREOR) ML13121A2442013-04-30030 April 2013 2012 Annual Radioactive Effluent Release Report ML12157A4932012-05-23023 May 2012 Attachment 41 to GNRO-2012/00039 - Black Bear Habitat Assessment (Provided as Attachment B on the Terrestrial Ecology Response Cd) ML12157A4952012-05-23023 May 2012 Attachment 43 to GNRO-2012/00039 - Er Reference-GGNS 2007g (2006 Depredation Report) ML12157A4422012-05-23023 May 2012 Attachment 44 to GNRO-2012/00039 - Er Reference-GGNS 2008e (2007 Depredation Report) ML12157A4432012-05-23023 May 2012 Attachment 45 to GNRO-2012/00039 - Er Reference-GGNS 2009g (2008 Depredation Report) ML12157A4252012-05-23023 May 2012 Attachment 37 to GNRO-2012/00039 - Ensr (Ensr Corporation), 2005 Appendix B, Review of Lower Mississippi Fishes. March 2005 ML12157A4132012-05-23023 May 2012 Attachment 34 to GNRO-2012/00039 - Er Reference - MDEQ 2011a (NPDES Permit Rationale) Rationale for Reissuance ML12157A4482012-05-23023 May 2012 Attachment 49 to GNRO-2012/00039 - Ggns. 2008g. Grand Gulf Nuclear Station (Ggns), Facility No. 0420-00023, Renewal of Existing Synthetic Minor Operating Permit No. 0420-00023, Correspondence GEXO-200810008. November 25, 2008 ML12157A4462012-05-23023 May 2012 Attachment 47 to GNRO-2012/00039 - Er Reference-GGNS 2011 H (2010 Depredation Report ML12157A4452012-05-23023 May 2012 Attachment 46 to GNRO-2012/00039 - Er Reference-GGNS 201 of (2009 Depredation Report) ML12157A5502012-05-23023 May 2012 Attachment 42 to GNRO-2012/00039 - Decision Notice and Finding of No Significant Impact Utility Corridor Maintenance for Wildlife Habitat Enhancement and Associated Environmental Assessment (Provided in Attachment C on the Terrestrial Ecolo ML12157A4512012-05-23023 May 2012 Attachment 51 to GNRO-2012/00039 Ggns. 2004. Air Pollution Control Permit to Operate Air Emissions Equipment at a Synthetic Minor Source, Permit No. 0420-00023. June 1, 2004 ML12157A4502012-05-23023 May 2012 Attachment 50 to GNRO-2012/00039 Enercon. 2011 B. Evaluation of Potential Air Emissions from Coal and Natural Gas Fired ML12157A4472012-05-23023 May 2012 Attachment 48 to GNRO-2012/00039 - Er Reference-USDA 1976 (Franklin Line Permit) ML12157A4272012-05-23023 May 2012 Attachment 39 to GNRO-2012/00039 - Mp&L (Mississippi Power & Light Company). 1981. Mississippi Power & Light Company, Middle South Energy, Inc., Grand Gulf Nuclear Station Units 1 and 2, Final Environmental Report, Docket Nos. 50-416 and 50 ML12157A2642012-05-23023 May 2012 Attachment 19 to GNRO-2012/00039, Er Reference - Entergy. 2008a. Entergy Nuclear Fleet Procedure EN-CY-109, Sampling and Analysis of Groundwater Monitoring Wells, Revision 2. April 1, 2008 ML12157A2472012-05-23023 May 2012 Attachment 23 to GNRO-2012/00039, Er Reference - Entergy 2011 a (EN-CY-111) Radiological Ground Water Monitoring Program ML12157A1842012-05-23023 May 2012 Attachment 11 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment Q Labeled Thermal Monitoring Reports for Winter and Summer 2007. GNRO-2012/00035, Annual Radioactive Effluent Release Report2012-04-30030 April 2012 Annual Radioactive Effluent Release Report 2023-04-27
[Table view] Category:Letter type:GNRO
MONTHYEARGNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors GNRO-2021/00037, 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 12021-11-30030 November 2021 2021 Annual Report of Changes and Errors to 10 CFR 50.46 Analysis Grand Gulf Nuclear Station, Unit 1 GNRO-2021/00017, Notification of Readiness for Supplemental Inspection2021-06-22022 June 2021 Notification of Readiness for Supplemental Inspection GNRO-2021/00014, Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency2021-06-0101 June 2021 Inservice Testing Program Relief Request VRR-GGNS-2021-1 Pressure Isolation Valve Testing Frequency GNRO-2021/00015, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report GNRO-2021/00011, Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 20202021-04-19019 April 2021 Revision of Original Report of 10CFR50.59 and Commitments Change Evaluations - July 1, 2018 Through May 21, 2020 GNRO-2021/00012, Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.22062021-04-13013 April 2021 Annual Report of Individual Monitoring - NRC Form 5 for 2020 Per 10 CFR 20.2206 GNRO-2020/00045, 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis2020-12-16016 December 2020 2020 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2020/00034, Notification of Spent Fuel Cask Use2020-10-0808 October 2020 Notification of Spent Fuel Cask Use GNRO-2020/00033, Response to NRC Integrated Inspection Report 05000416/20200022020-09-10010 September 2020 Response to NRC Integrated Inspection Report 05000416/2020002 GNRO-2020/00029, Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 20202020-08-18018 August 2020 Report of 10 CFR 72.48 Evaluations July 1, 2018 Through June 30, 2020 GNRO-2020/00022, Report of Technical Specification Bases Changes2020-07-21021 July 2020 Report of Technical Specification Bases Changes GNRO-2020/00027, Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-07-16016 July 2020 Core Operating Limits Report (COLR) Cycle 23 Revision 1 for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00023, Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-06-26026 June 2020 Response to Request for Additional Information - License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)2020-05-0505 May 2020 Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS) GNRO-2020/00018, Annual Radiological Effluent Release Report2020-04-30030 April 2020 Annual Radiological Effluent Release Report GNRO-2020/00016, Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.22062020-04-16016 April 2020 Annual Report of Individual Monitoring -NRC Form 5 for 2019 Per 10 CFR 20.2206 GNRO-2020/00015, Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test2020-04-0707 April 2020 Response to Request for Additional Information - License Amendment Request for One-Cycle Extension of Appendix J Type a Integrated Leakage Rate Test and Drywell Bypass Leakage Rate Test GNRO-2020/00007, Spent Fuel Storage Radioactive Effluent Release Report for 20192020-02-20020 February 2020 Spent Fuel Storage Radioactive Effluent Release Report for 2019 GNRO-2020/00006, License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies2020-02-19019 February 2020 License Amendment Request for Permanent Extension of Appendix J Type a Integrated Leakage Rate Test Frequencies GNRO-2019/00052, Report of Changes and Errors to 10 CFR 50.46 Analysis2019-12-13013 December 2019 Report of Changes and Errors to 10 CFR 50.46 Analysis GNRO-2019/00051, Notification of Readiness of 92723 Inspection2019-12-11011 December 2019 Notification of Readiness of 92723 Inspection GNRO-2019/00045, Emergency Plan, Revision 792019-10-29029 October 2019 Emergency Plan, Revision 79 GNRO-2019/00037, Notification of Spent Fuel Cask Use2019-09-20020 September 2019 Notification of Spent Fuel Cask Use GNRO-2019/00036, Correction to Gnro 2019-00017 Emergency Plan Revision 782019-08-0808 August 2019 Correction to Gnro 2019-00017 Emergency Plan Revision 78 GNRO-2019/00027, Notification of Readiness of 95001 Supplemental Inspections2019-07-0303 July 2019 Notification of Readiness of 95001 Supplemental Inspections GNRO-2019/00031, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report2019-06-25025 June 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 - Corrected Report GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.2019-06-13013 June 2019 Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation. GNRO-2019/00026, Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval2019-05-0606 May 2019 Response to Requests for Additional Information Regarding Relief Request Number GG-ISI-023, Inservice Inspection Impracticality - Limited Coverage Examinations During the Third 10-Year Inservice Inspection Interval GNRO-2019/00024, Annual Radioactive Effluent Release Report2019-04-30030 April 2019 Annual Radioactive Effluent Release Report GNRO-2019/00020, Annual Radiological Operating Report (AREOR)2019-04-30030 April 2019 Annual Radiological Operating Report (AREOR) GNRO-2019/00022, Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.22062019-04-22022 April 2019 Annual Report of Individual Monitoring - NRC Form 5 for 2018 Per 10 CFR 20.2206 GNRO-2019/00017, Emergency Plan, Revision 782019-03-14014 March 2019 Emergency Plan, Revision 78 GNRO-2019/00014, Snubber Testing Program for Fourth Inspection Interval2019-03-13013 March 2019 Snubber Testing Program for Fourth Inspection Interval GNRO-2019/00012, Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2019-03-0606 March 2019 Internal Events Probabilistic Risk Assessment (PRA) Sensitivity Study Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program GNRO-2019/00016, Spent Fuel Storage Radioactive Effluent Release Report for 20182019-02-21021 February 2019 Spent Fuel Storage Radioactive Effluent Release Report for 2018 GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation2019-01-23023 January 2019 Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation GNRO-2018/00057, Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan2018-12-0404 December 2018 Submittal of Revision 17 to the Grand Gulf Nuclear Station Physical Security, Safeguards Contingency, and Training and Qualification Plan GNRO-2018/00055, Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ...2018-11-30030 November 2018 Response to Request for Additional Information for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a ... GNRO-2018/00054, Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval2018-11-30030 November 2018 Relief Request No. GG-ISI-023, Inservice Inspection Impracticality: Limited Coverage Examination During the Third 10-Year Inservice Inspection Interval GNRO-2018/00052, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information2018-10-24024 October 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Partial Response to Request for Additional Information and Extension of Response to Request for Additional Information GNRO-2018/00051, Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-10-23023 October 2018 Supplement to Revise Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control GNRO-2018/00046, Submittal of 2018 Report of Changes and Errors to 10CFR50.462018-10-16016 October 2018 Submittal of 2018 Report of Changes and Errors to 10CFR50.46 GNRO-2018/00047, Submittal of 2018 Inservice Inspection Summary Report2018-10-16016 October 2018 Submittal of 2018 Inservice Inspection Summary Report GNRO-2018/00048, Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 62018-10-10010 October 2018 Response to Request for Additional Information License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 GNRO-2018/00042, Core Operating Limits Report Cycle 22, Revision 12018-09-18018 September 2018 Core Operating Limits Report Cycle 22, Revision 1 GNRO-2018/00043, Revised Offsite Dose Calculation Manual2018-09-18018 September 2018 Revised Offsite Dose Calculation Manual GNRO-2018/00039, Report of Technical Specification Bases Changes2018-08-20020 August 2018 Report of Technical Specification Bases Changes GNRO-2018/00040, Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 20182018-08-20020 August 2018 Report of 10CFR50.59 Evaluations and Commitment Change Evaluations - July 1, 2016 Through June 30, 2018 2023-06-06
[Table view] Category:Manual
MONTHYEARML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment ML22104A0782022-04-14014 April 2022 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML17109A4872017-04-10010 April 2017 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G GNRO-2014/00058, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)2014-08-29029 August 2014 Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330) ENOC-13-00029, Planned Modification of the Entergy Quality Assurance Program Manual (EA-11-096)2013-11-0404 November 2013 Planned Modification of the Entergy Quality Assurance Program Manual (EA-11-096) GNRO-2013/00033, Offsite Dose Calculation Manual, Revs. 38 & 39, Page 2.0-31 Through End2013-04-30030 April 2013 Offsite Dose Calculation Manual, Revs. 38 & 39, Page 2.0-31 Through End CNRO-2013-00007, Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2013-04-26026 April 2013 Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update2012-12-21021 December 2012 Technical Requirements Manual and Technical Specification Bases Update ML12157A2532012-05-23023 May 2012 Attachment 29 to GNRO-2012/00039 Er Reference - Ggns. 2011 J. Site Procedure 08-S-03-10, Chemistry Sampling Program, Revision 48. January 20, 2011 ML12157A2482012-05-23023 May 2012 Attachment 24 to GNRO-2012/00039, Er Reference - Entergy 2011 C (EN-EV-112) Chemical Control Program. ML12157A2472012-05-23023 May 2012 Attachment 23 to GNRO-2012/00039, Er Reference - Entergy 2011 a (EN-CY-111) Radiological Ground Water Monitoring Program ML12157A2442012-05-23023 May 2012 Attachment 20 to GNRO-2012/00039, Er Reference - Entergy. 2008b. Entergy Nuclear Fleet Procedure EN-EV-106, Waste Management Program, Revision 2. August 18, 2008 ML13121A2452012-04-30030 April 2012 Offsite Dose Calculation Manual, Revs. 38 & 39, Cover Through Page 2.0-30 GNRO-2011/00072, Technical Requirements Manual and Technical Specification Bases Update2011-09-12012 September 2011 Technical Requirements Manual and Technical Specification Bases Update ML0913100172009-04-28028 April 2009 Offsite Dose Calculation Manual, Attachment II GNRO-2009/00024, Technical Requirements Manual Update to the NRC Dated March 31, 20092009-03-31031 March 2009 Technical Requirements Manual Update to the NRC Dated March 31, 2009 GNRO-2009/00005, Technical Requirements Manual Update to the NRC Dated January 19, 20092009-01-19019 January 2009 Technical Requirements Manual Update to the NRC Dated January 19, 2009 ML0904103222008-04-15015 April 2008 Entergy'S Quality Assurance Program Manual, Revision 18; Effective: April 15, 2008 ENOC-07-00020, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 162007-06-15015 June 2007 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes, Revision 16 GNRO-2007/00017, Technical Requirements Manual Update to NRC for Period Dated March 1, 20072007-03-0101 March 2007 Technical Requirements Manual Update to NRC for Period Dated March 1, 2007 GNRO-2006/00052, Technical Requirements Manual Update to NRC for Period Dated September 21, 20062006-09-21021 September 2006 Technical Requirements Manual Update to NRC for Period Dated September 21, 2006 GNRO-2006/00009, Technical Requirements Manual Update to the NRC for Period Dated February 16, 20062006-02-16016 February 2006 Technical Requirements Manual Update to the NRC for Period Dated February 16, 2006 CNRO-2005-00024, Entergy Quality Assurance Program Manual, Revision 122005-04-0606 April 2005 Entergy Quality Assurance Program Manual, Revision 12 ML0312600022003-04-24024 April 2003 Issuance of Entergy Quality Assurance Program Manual (Qapm), Revision 8 GNRO-2002/00033, 2001 Annual Radioactive Effluent Release Report (ARERR)2002-04-22022 April 2002 2001 Annual Radioactive Effluent Release Report (ARERR) 2023-04-20
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Text
nter erati 6.
Waterloo Road P.O. Box 756 Pot-l Gibson, MS 39150 Tel 601 437 6299 WkS er Manager Plant Licensinq April 22, 2002 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: Document Control Desk
SUBJECT:
2001 Grand Gulf Nuclear Station (GGNS) 2001 Annual Radioactive Effluent Release Report (ARERR)
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2002100033 Gentlemen:
Attached is the GGNS Annual Radioactive Effluent Release Report (ARERR) for the period January 1, 2001 through December 31, 2001. This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNS Technical Specification (TS) 5.6.3.
The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).
If you have questions or require additional information concerning these reports, please contact Mr. B. D. Bryant at (601) 437-6316, or this office at (601) 437-6685. This letter does not contain any commitments.
Yours truly, CAB/M JL attachments: 2001 Annual Radioactive Effluent Release Report cc: (See Next Page)
April 22, 2002 GNRO-2002100033 Page 2 of 2 cc:
Hoeg T. L. (GGNS Senior Resident) (w/a>
Levanway D. E. (Wise Carter) (w/a>
Reynolds N. S. (w/a>
Smith L. J. (Wise Carter) (w/a)
/ Thomas 1 H. L. 1 I (w/o) I Mr. E. W. Merschoff (w/2) ALL LETTERS Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 U.S. Nuclear Regulatory Commission ALL LETTERS - U.S. POSTAL ATTN: Mr. S. P. Sekerak, NRR/DLPM (w/2) SERVICE MAIL DELIVERY ATTN: FOR ADDRESSEE ONLY ADDRESS ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop 07Dl Washington, D.C. 205550001
January 1,200l-December 31,200l
TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 II. DETAILED INFORMATION 5 A. Regulatory Limits 5
- 1. 10CFR20 Limits 5
- a. Fission and Activation Gases 5
- b. Radioiodines and Particulates 5
- c. Liquid Effluents 5
- 2. 10CFR50, Appendix I Limits 6
- a. Fission and Activation Gases 6
- b. Radioiodines and Particulates 6
- c. Liquid Effluents 6
- 3. 40CFR190 Limits 7 B. Effluent Concentrations 7
- 1. Airborne 7
- 2. Liquid 7 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8
- 1. For Fission and Activation Gases 8
- 2. For Particulates and Radioiodines 9
- 3. For Continuous Releases 9
- 4. For Batch Releases: Gases 9
- 5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10
- 1. Liquid 10
- 2. Gaseous 10 F. Unplanned Releases 11 I. Liquid 11
- 2. Gaseous II
TABLE OF CONTENTS (CONTD)
SUBJECT PAGE G. Estimate of Total Error 11
- 1. Liquid 11
- 2. Gaseous 12
- 3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 12 I. Meteorological Data 12 J. Radioactive Effluent Monitoring Instrumentation Operability 12 K. Annual Sewage Disposal Summary 12 Ill. RADIATION DOSE
SUMMARY
13 A. Water-Related Exposure Pathway 13 B. Airborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 15 A. Offsite Dose Calculation Manual (ODCM) 15 B. Radioactive Waste Treatment Systems 15 LIST OF TABLES PAGE IA Gaseous Effluents - Summation of All Releases 16 19 Gaseous Effluents - Elevated Releases 17 AC Gaseous Effluents - Ground-Level Releases - Continuous 18 1D Radioactive Gaseous Waste Sampling and Analysis Program 19 2A Liquid Effluents - Summation of All Releases 20 2B Liquid Effluents - Continuous and Batch Modes 21 2c Radioactive Liquid Waste Sampling and Analysis Program 22 3 Solid Radioactive Waste and Irradiated Fuel Shipments 23 LIST OF ATTACHMENTS PAGE Attachment I - Offsite Dose Calculation Manual, Revision 23 25 491 env-tedARERR0.i -3
I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31,ZOOl is submitted in accordance with Offsite Dose Calculation Manual (ODCM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS) License No. NPF-29.
The monitoring of radioactive effluents is referenced in ODCM Appendix A, Sections 6.11 and 6.12.
Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM. Projected offsite doses were within the dose limits specified by the ODCM.
The summation of all gaseous releases during the reporting period is given in Table IA, while elevated releases and ground-level releases are given in Tables 1 B and 1 C, respectively. Table 1 D describes the radioactive gaseous sampling and analysis program implemented at GGNS.
The summation of all liquid releases during the reporting period is given in Table 2A, while continuous and batch mode releases are given in Table 28. Table 2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS.
Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.
The annual summary of meteorological data (ioint frequency distribution) will be maintained on site in a file that shall be provided to the Nuclear Regulatory Commission (NRC) upon request. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3.
II. DETAILED INFORMATION A. Regulatory Limits
- 1. 1 OCFRZO Limits
- a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary shall be such that:
& = average total body dose rate in the current year (mremlyr)
= XIQ Zi Ki Q i < 500 mremlyr DS = average skin dose rate in the current year (mrem/yr)
= XIQ Xi (L, + 1 .I Mi ) Q i 5 3000 mremlyr where the terms are defined in the GGNS ODCM.
- b. Radioiodines and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:
D, = average organ dose rate in current year (mremlyr)
= Ci W Pi 5, < 1500 mremlyr where the terms are defined in the GGNS ODCM.
C. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 1 OCFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x 1 Oe4microcurieslml total activity.
II. DETAILED INFORMATION (CONTD)
- 2. IOCFRSO, Appendix I Limits
- a. Fission and Activation Gases - The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that:
Dy = air dose due to gamma emissions from noble gases
= 3.17 x 10. Zi Mi XIQ Qi 5 5 mradlqtr 2 IO mradlyr
= air dose due to beta emissions from noble gases DP
= 3.17 x 1 O-8Ci Ni XIQ Q, c 10 mradlqtr I 20 mradlyr where the terms are defined in the GGNS ODCM.
- b. Radioiodines and Particulates - The dose to an individual from tritium, l-l 31, I-l 33 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:
D,= dose to an individual from tritium, l-l 31, l-l 33 and radionuclides in particulate form with half-lives greater than 8 days (mrem)
= 3.17 x 1 O-*Xi Ri w Qi < 7.5 mremlqtr Any Organ 5 15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.
- c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:
m DTau = c [AiTau C At, Ci, F, ] 2 1.5 mremlqtr Total Body i I=1 5 5 mremlqtr Any Organ 2 3 mremlyr Total Body 2 10 mremlyr Any Organ where the terms are defined in the GGNS ODCM.
Il. DETAILED INFORMATION (CONTD)
- 3. 4OCFRl90 Limits Doses are calculated for Fission and Activation Gases; Radioiodines and Particulates; and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:
525 mremlyr, Total Body or any Organ except Thyroid 275 mrem/yr, Thyroid 110 mrad ylqtr or r20 mrad ylyr, Fission and Activation Gases 220 mrad Plqtr or 540 mrad P/yr, Fission and Activation Gases 515 mremlqtr or 530 mrem/yr, any Organ, Iodine and Particulates 23 mremlqtr or 56 mrem/yr, Total Body, Liquid Effluents
= 8 days 1 1. Total Release Ci 1.583-05 7.393-06 8.503-06 1.29'3-06 3.303-05 1 II 3.
- 2. Average Percent Release of TS LimitRate uCi/sec
% 2.10E-04 2.043-06 2.733-04 9.393-07 1.483-04 l.O7E-06 7.743-08 1.633-07 2.51E-04 l.O5E-06 II Tritium II
- 1. Total Release Ci 2.24E+Ol 1.65E+Ol 1.72E+Ol 2.06E+Ol 7.683+01
- 2. Average Release Rate uCi/sec 2.883+00 2.10E+OO 2.17E+OO 2.60E+OO 2.44E+OO
- 3. Percent of TS Limit % 4.22E-01 3.11E-01 3.243-01 3.883-01 7.23E-01 Gross Alwha Radioactivitv II 2.
- 1. Average Total Release Release Rate uCi/sec Ci 2.243-10 1.743-09 O.OOE+OO O.OOE+OO 2.033-09 1.61E-08 5.663-10 1.783-08 II
TABLE IB ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2001 (Not Applicable - GGNS Releases Are Considered Ground-Level)
TABLE 1 C ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2001 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR
_____------------- ----- ------- e-v----- _------- -------- -------- --------
Fission and Activation Gases AR-41 Ci 5.673-03 5.863-02 1.67E-01 O.OOE+OO 2.323-01 RR-85M Ci O.OOE+OO 1.01E-03 O.OOE+OO O.OOE+OO l.OlE-03 KR-87 Ci O.OOE+OO 4.293-03 O.OOE+OO O.OOE+OO 4.293-03 RR-88 Ci 1.33E-01 1.88E-01 3.883-01 2.06E-01 9.16E-01 XE-133 Ci 3.133+00 4.40E+OO 9.1OE+OO 4.843+00 2.15E+Ol m-135 Ci 2.993+00 4.21E+OO 8.71E+OO 4.633+00 2.05E+Ol XE-135M Ci 3.533-01 5.01E-01 1.033+00 5.463-01 2.433+00 XE-138 Totals for Period.....
Ci Ci 8.01E-02 6.693+00 Iodines 1.50E-01 9.51E+OO 3.773-01 1.98E+Ol 1.24E-01 l.O3E+Ol 7.323-01 4.633+01 1
I-131 Ci O.OOE+OO 3.923-05 4.303-05 O.OOE+OO 8.223-05 I-132 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 Ci 5.08E-06 1.733-05 9.39E-06 O.OOE+OO 3.183-05 I-135 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period..... Ci 5.083-06 5.65E-05 5.24E-05 O.OOE+OO l.l4E-04 Particulates Half Life >= 8 days CO-58 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-60 Ci O.OOE+OO 1.333-06 8.193-07 O.OOE+OO 2.143-06 CR-51 Ci 1.493-05 4.123-06 5.383-06 1.293-06 2.573-05 cs-137 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-59 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 Ci O.OOE+OO 1.493-06 2.30E-06 O.OOE+OO 3.793-06 RU-106 Ci 9.133-07 4.503-07 O.OOE+OO O.OOE+OO 1.363-06 Totals for Period..... Ci 1.583-05 7.39E-06 8.503-06 1.293-06 3.303-05 Tritium H-3 Ci 2.24E-k01 1.65E+Ol 1.72E+Ol 2.063+01 7.683+01 Totals for Period..... Ci 2.243+01 1.65E+Ol 1.72E+Ol 2.06E+Ol 7.683+01 Gross Alpha Radioactivity ALPHA Ci 1.743-09 O.OOE+OO O.OOE+OO 1.61E-08 1.783-08 Totals for Period..... Ci 1.743-09 U.UOE+OO O.OOE+00 1.61E-08 1.7832-08 I
TABLE 1 D ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY-DECEMBER 2001 Lower Limit Sampling Minimum Analysis Type of Activity of Detection Gaseous Release Type Frequency Frequency Analysis
( j%l, 9
- 4. (1) Radwaste Building 31 Days 31 Days Principal Gamma Ventilation Exhaust Grab Sample (f) Emitters (b,e) 1x104 H-3 1X10 (2) Fuel Handling Area Continuous 7 Days (c) l-l 31 1x1 O-l2 Ventilation Exhaust NW-I Charcoal Sample l-l 33 1xlo-o (3) Containment Continuous 7 Days (c) Principal Gamma 1x10-Ventilation Exhaust W)(f) Particulate Emitters (e) (l-l 31, Sample Others)
(4) Turbine Building Continuous 31 Days Gross Alpha 1x10-Ventilation Exhaust WQ Composite Particulate Sample Continuous 92 Days Sr-89, Sr-90 1x10-W)(f) Composite Particulate Sample Continuous (f) Noble Gas Noble Gases Gross 1xl o-6 Monitor Beta or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma lx104 Treatment Exhaust, Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma lx104 Treatment A Sample (f) Emitters(e)
Exhaust, whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10 Treatment B Sample (f) Emitters(e)
Exhaust, whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-I
TABLE 2A ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2001 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR
______----------- ------ ------- -m-w---- __------ -------- -------- --------
Fission and Activation Products II 1. Total Release Ci 1.283-03 8.453-03 1.383-02 1.20E-02 3.553-02 1
- 3. Avg.
- 2. PercentDiluted of Limit Cont. %
uCi/ml 2.843-02 3.673-08 5.993-01 3.623-08 3.643-01 7.043-08 4.933-01 2.243-07 5.99E-01 6.863-08 II Tritium
- 1. Total Release Ci 6.233+00 3.09E+Ol 1.70E+Ol 6.353+00 6.043+01
- 2. Avg. Diluted Cont. uCi/ml 1.793-04 1.323-04 8.683-05 l.l8E-04 1.17E-04
- 3. Percent of Limit % 1.79E+OO 1.32E+OO 8.683-01 1.18E+OO l.l7E+OO Dissolved and Entrained Gases
- 1. Total Release Ci O.OOE+OO 2.393-05 O.OOE+OO l.O7E-05 3.463-05
- 2. Avg. Diluted Cont. uCi/ml O.OOE+OO l.O2E-10 O.OOE+OO 1.99E-10 6.683-11
- 3. Percent of Limit % O.OOE+OO 5.10E-05 O.OOE+OO 9.953-05 3.343-05 Gross Alpha Radioactivity
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO volume of liquid waste liters 3.913+05 2.393+06 1.753+06 6.203+05 5.15E+06 Volume of dil. water liters 3.453+07 2.313+08 1.943+08 5.313+07 5.123+08
TABLE 2B ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 2001 units QTR I. QTR 2 QTR 3 QTR 4 YEAR
________--------~~~~~~~ ------- -------- -------- -------- __------ _-------
Fission and Activation Products AS-76 Ci O.OOE+OO 6.203-06 O.OOE+OO O.OOE+OO 6.203-06 CO-58 Ci O.OOE+OO 7.463-05 7.00E-05 1.423-04 2.873-04 CO-60 Ci 4.513-05 2.693-03 6.703-04 1.86E-03 5.273-03 CR-51 Ci 2.673-04 2.433-03 9.76$-03 3.193-03 1.563-02 cs-137 Ci O.OOE+OO 1.883-05 4.983-05 O.OOE+OO 6.863-05 cu-64 Ci O.OOE+OO 1.51E-05 O.OOE+OO O.OOE+OO 1.51E-05 FE-55 Ci 9.693-04 6.223-04 2.863-03 2.913-03 7.363-03 FE-59 Ci O.OOE+OO l.l8E-03 4.163-05 5.203-04 1.743-03 I-131 Ci O.OOE+OO 4.253-06 O.OOE+OO O.OOE+OO 4.253-06 MN-54 Ci O.OOE+OO 8.543-04 2.243-04 3.203-03 4.273-03 NH-95 Ci O.OOE+OO O.OOE+OO O.OOE+OO l.l5E-05 l.l5E-05 SB-124 Ci O.OOE+OO O.OOEtOO O.OOEtOO 9.021-06 9.023-06 ZN-65 Ci O.OOE+OO 5.483-04 7.803-05 1.543-04 7.803-04 ZN-69M Ci O.OOE+OO 8.903-06 8.653-06 2.11E-05 3.873-05 Totals for Period..... Ci 1.283-03 8.453-03 1.383-02 1.20E-02 3.553-02 Tritium H-3 Ci 6.233+00 3.09E+Ol 1.70E+Ol 6.353+00 6.04E+Ol Totals for Period..... Ci 6.23E+OO 3.09E+Ol 1.70E+Ol 6.353+00 6.04E+Ol Dissolved and Entrained Gases Totals for Period.....
Gross Alpha Radioactivity
- No Nuclide Activities** O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
TABLE 2C ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY-DECEMBER 2001 Lower Limit Sampling Minimum Analysis Type of Activity of Detection Llquld Release Type Frequency Frequency Analysis W-D)
( @i/ml)(a)
A. Batch Waste Release Prior to Release Prior to Release Principal Gamma Tanks (c) Each Batch Each Batch Emitters (d) 5x1 o-7 I-1 31 1X10" Prior to 31 Days Dissolved and 1xl O!j Release One Entrained Gases Batch IM (Gamma Emitters)
Prior to 31 Days ji-zJ 1xlo5 Release Each Composite (b) Gross Alpha 1 xl o-7 Batch Prior to 92 Days Sr-89. Sr-90 5x10" Release Each Composite (b) Fe-55 1xl o-"
Batch B. SSW Basin (Before Blowdown) Prior to Prior to Release Principal Gamma Release Each Each Batch Emitters (d) 5x1 o-7 Blowdown l-l 31 1x10~
NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-I.
TABLE 3 ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY-DECEMBER 2001 A. Solid Waste Shipped Offsite for Burial or Disposal
- 1. TYPE OF WASTE 2NDQTR 3RDQTR 4THQTR TOTAL ERROR (%)
- a. RESIN M3 1.75E+Ol 1.42E+Ol 7.23E+Ol 155E+Ol
\ _\ *Ci 592E+Ol 542E+Ol 4.44E+Ol 2.71 E+Ol 7.2E+Ol hu. I-iAW Y#-B..
M3 w..
- 4. ..,.v-c;8F+nn -- 7 7fIF+OO
-.--- 6.43E+OO 8.1 OE+OO I
1 *Ci 1 6.40E-02 1 1.21E +oo 1.27E+OO 1.94E+OO 6.9E+Ol
- c. IRR
..\I..
CY-WID VVI.I. .
I I
M3 I.,
I I
NtWlfA
. ..r. ..s I
I NAtlc?
I Nnnn I
None I *Ci None I None I None I None I N/A II I: I II a-l
-. nTUFR
-...-*. I I
M3
..* I I
Nntl0
.--..- I NfWW
._-..- I NntlG!
.-..- I None
- Ci None I None I None I None I N/A
- Total curie quantity determined by measurement. Total volume used is burial container volume. Resin and DAW solid waste was Class A as defined by 1 OCFR Part 61.
- 2. Estimate of major nuclide composition (by type of waste as identified above) 8 12 12 12 65 75 68 70 5 4 12 15
<I 3 3 1 4 3 1 :I 12 3 2 1 ALL OTHERS Ill <I cl <I Nuclide 1 StQTR 2nd QTR 3rd QTR 4 QTR Co-60 10 10 11 11 H-3 3 4 4 <I Fe-55 83 84 84 84 Mn-54 4 4 4 4 I All nthnrr c-l 3 1 1
- c. IRR. CCMP.
II Nuclide
. ---..-- I _...
1 StQTR I 2nd QTR I 3rd QTR Co-60 N/A N/A N/A N/A Ni-63 N/A N/A N/A NIA Fe-55 N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A All Others N/A N/A N/A N/A
- d. OTHER Nuclide 1 st QTR 2nd QTR 3rd QTR 4th QTR N/A N/A NIA N/A NIA
TABLE 3 ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS (CONTD)
JANUARY-DECEMBER 2001 A. Solid Waste Shipped Off Site for Burial or Disposal
- 3. Solid Waste Disposition
- a. Some resins were dewatered in High Integrity Containers aooording to the requirements of the GGNS Process Control Program and shipped to Barnwell, South Carolina, for burial. Most resin was shipped to Allied Technologies Group (ATG) of Oak Ridge, Tennessee or Studsvik, LLC. of Erwin, Tennessee for volume reduction prior to burial.
ATG and Studsvik shipped waste to Barnwell, South Carolina or Envirocare of Utah. Resin was dewatered and shipped in steel liners and High Integrity Containers. No solidification agents or absorbents were used.
- b. Dry Active Waste (DAW) was packaged in 20 sealand containers or metal B-25 boxes and shipped to Duratek of Oak Ridge, Tennessee for volume reduction. Duratek shipped reduced waste to Barnwell, South Carolina or Envirocare of Uta h. Reduced volume was used in providing information given in A.1 .b.
C. No waste in this category.
- d. No waste in this category.
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 25 Truck Barnwell, SC 68 Truck Envirocare, UT B. Irradiated Fuel Shipments (Disposition)
/
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None N/A N/A
- c. Annual Sewage Sludge Summary No sewage sludqe was shipped during the reporting period.
/
NUMBER OF AVERAGE Co-60 AVERAGE Mn-54 AVERAGE Cs-137 SHIPMENTS TOTAL GALLONS ACTIVITY (pCi/kg) ACTIVITY (pCi/kg) ACTIVITY (pCi/kg)
None N/A N/A N/A N/A em-tec/ARERROf - 24
ATTACHMENT I OFFSITE DOSE CALCULATION MANUAL REVISION 23
OFFSITE DOSE CALCULATION MANUAL GRAND GULF NUCLEAR STATION GRANDGULF, UNIT I. Revision 23 - 03/01