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Category:Environmental Monitoring Report
MONTHYEARML23160A0052023-06-0909 June 2023 Annual Radioactive Effluent Release Report ML23135A0412023-05-15015 May 2023 2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report NMP1L3522, Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report2023-04-30030 April 2023 Independent Spent Fuel Storage Installation (ISFSI) - 2022 Radioactive Effluent Release Report ML22192A0042022-07-11011 July 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report ML22133A0092022-05-13013 May 2022 Independent Spent Fuel Storage Installation (Isfsi), 2021 Annual Radioactive Effluent Release Report and 2021 Annual Radiological Environmental Operating Report ML22133A2222022-05-13013 May 2022 Independent Spent Fuel Storage Installation, Annual Radiological Environmental Operating Report NMP1L3459, 2021 Annual Radiological Environmental Operating Report2022-05-0808 May 2022 2021 Annual Radiological Environmental Operating Report NMP1L3457, 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22022-04-30030 April 2022 2021 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 NMP2L2805, Annual Environmental Operating Report2022-04-23023 April 2022 Annual Environmental Operating Report ML21195A0332021-07-14014 July 2021 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML21133A1402021-05-11011 May 2021 and Independent Spent Fuel Storage Installation (ISFSI) - 2020 Annual Radioactive Effluent Release Report and 2020 Annual Radiological Environmental Operating Report NMP1L3388, 2020 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22021-04-30030 April 2021 2020 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 NMP2L2765, Submittal of 2020 Annual Environmental Operating Report2021-04-23023 April 2021 Submittal of 2020 Annual Environmental Operating Report ML20206K9532020-07-15015 July 2020 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML20136A4392020-05-15015 May 2020 2019 Annual Radioactive Effluent Release Report and 2019 Annual Radiological Environmental Operating Report NMP1L3336, Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 2019 Radioactive Effluent Release Report2020-04-30030 April 2020 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 2019 Radioactive Effluent Release Report NMP2L2727, Submittal of 2019 Annual Environmental Operating Report2020-04-27027 April 2020 Submittal of 2019 Annual Environmental Operating Report ML19198A1072019-07-15015 July 2019 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report ML19137A0922019-05-15015 May 2019 Annual Radioactive Effluent Release Report, January 1, 2018 - December 31, 2018. ML19137A0952019-05-15015 May 2019 Annual Radiological Environmental Operating Report, January 1, 2018 - December 31, 2018. NMP1L3273, 2018 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 22019-04-23023 April 2019 2018 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 ML18193A4572018-07-10010 July 2018 Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report for 2017 ML18136A5512018-05-14014 May 2018 Independent Spent Fuel Storage Installation - Submittal of Annual Radiological Environmental Operating Report ML18137A2132018-05-11011 May 2018 and Independent Spent Fuel Storage Installation - Submittal of 2017 Annual Radioactive Effluent Release Report and 2017 Annual Radiological Environmental Operating Report NMP1L3212, Submittal of 2017 Annual Radiological Environmental Operating Report2018-05-10010 May 2018 Submittal of 2017 Annual Radiological Environmental Operating Report NMP1L3211, Independent Spent Fuel Storage Installation - 2017 Radioactive Effluent Release Report2018-04-19019 April 2018 Independent Spent Fuel Storage Installation - 2017 Radioactive Effluent Release Report NMP2L2671, Submittal of 2017 Annual Environmental Operating Report2018-04-19019 April 2018 Submittal of 2017 Annual Environmental Operating Report ML18137A2142017-12-31031 December 2017 Appendix a - R.E. Ginna Nuclear Power Plant - Annual Report on the Meteorological Monitoring Program ML17198A0192017-07-12012 July 2017 Independent Spent Fuel Storage Installation(Isfsi) Annual Radioactive Effluent Release Report for 2016 and June 2016 to May 2017 for ISFSI ML17143A0122017-05-31031 May 2017 Attachment 2 - Annual Radiological Environmental Operating Report: January 1, 2016 - December 31, 2016 ML17143A0112017-05-31031 May 2017 Attachment 1 - Annual Radioactive Effluent Release Report: January 1, 2016 - December 31, 2016 NMP1L3151, Submittal of 2016 Annual Radiological Environmental Operating Report2017-05-12012 May 2017 Submittal of 2016 Annual Radiological Environmental Operating Report ML17135A3332017-05-11011 May 2017 Annual Radiological Environmental Operating Report ML17143A0102017-05-10010 May 2017 Submittal of the Annual Radioactive Effluent Release Report and Annual Radiological Environmental Operating Report for 2016 and Independent Spent Fuel Storage Installation (ISFSI) NMP1L3150, Independent Spent Fuel Storage Installation, Submittal of 2016 Radioactive Effluent Release Report2017-04-28028 April 2017 Independent Spent Fuel Storage Installation, Submittal of 2016 Radioactive Effluent Release Report NMP2L2645, Annual Environmental Operating Report2017-04-19019 April 2017 Annual Environmental Operating Report ML16246A0072016-08-31031 August 2016 National Pollution Discharge Elimination System Permit Issuance ML16188A1282016-06-29029 June 2016 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2015 ML16147A6092016-05-23023 May 2016 and Independent Spent Fuel Storage Installation (ISFSI) Submittal of Annual ISFSI Radioactive Effluent Release Report for 2015 ML16139A5592016-05-13013 May 2016 Transmittal of 2015 Annual Radiological Environmental Operating Report ML16145A5062016-05-12012 May 2016 Annual Radioactive Effluent Release Report and Annual Radiological Environment Operating Report ML16131A6722016-05-0505 May 2016 Annual Radiological Environmental Operating Report for 2015 NMP1L3082, Radioactive Effluent Release Report for 20152016-05-0202 May 2016 Radioactive Effluent Release Report for 2015 NMP2L2617, Transmittal of 2015 Annual Environmental Operating Report2016-04-15015 April 2016 Transmittal of 2015 Annual Environmental Operating Report ML15198A0352015-07-14014 July 2015 ISFSI - Annual Radioactive Effluent Release Report for 2014 ML15146A1732015-05-14014 May 2015 Annual Radiological Environmental Operating Report, January 1, 2014 - December 31, 2014 ML15146A1702015-05-14014 May 2015 Annual Radioactive Effluent Release Report, January 1, 2014 - December 31, 2014 ML15138A1332015-05-13013 May 2015 2014 Annual Radiological Environmental Operating Report ML15133A1672015-05-0808 May 2015 ISFSI - Annual Radiological Environmental Operating Report, January 1 - December 31, 2014 ML15133A3212015-05-0101 May 2015 2014 Radioactive Effluent Release Report 2023-06-09
[Table view] Category:Letter
MONTHYEARIR 05000244/20230042024-02-0505 February 2024 LLC - Integrated Inspection Report 05000244/2023004 IR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24026A0112024-01-26026 January 2024 R. E. Ginna Nuclear Power Plant, Relief Request Associated with Inservice Testing of B Auxiliary Feedwater Pump NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program IR 05000244/20230102023-12-19019 December 2023 LLC - Age-Related Degradation Inspection Report 05000244/2023010 ML23348A0992023-12-15015 December 2023 R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23347A0092023-12-13013 December 2023 Annual Commitment Change Notification ML23346A0142023-12-12012 December 2023 LLC - Senior Reactor and Reactor Operator Initial License Examinations ML23341A1252023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23321A1392023-11-17017 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information and Request for Additional Information ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 IR 05000244/20230032023-10-25025 October 2023 LLC - Integrated Inspection Report 05000244/2023003 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 ML23292A0282023-10-19019 October 2023 LLC - Notification of Conduct of a Fire Protection Team Inspection IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 2024-02-05
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J. M. Heffley Constellation Generation Group Chief Nuclear Officer 1997 Annapolis Exchange Parkway Suite 310 Annapolis, MD 21401 410-897-5020 Generation Group Energy Constellation July 31, 2006 Division of Inspection and Regional Support Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Mr. Stuart A. Richards, Deputy Director, NRR/ADRO/DIRS
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Nine Mile Point Nuclear Station Unit Nos. 1 & 2; Docket Nos. 50-220 & 50-410 R.E. Ginna Nuclear Power Plant Docket No. 50-244 Groundwater Protection - Data Collection Questionnaire The nuclear industry, in conjunction with the Nuclear Energy Institute, has developed a questionnaire to facilitate the collection of groundwater data at commercial nuclear reactor sites. The objective of the questionnaire is to compile baseline information about the current status of site programs for monitoring and protecting groundwater, and to share that information with the Nuclear Regulatory Commission.
Attachments I through 3, provided for your information, are the completed questionnaires for Calvert Cliffs Nuclear Power Plant, Nine Mile Point Nuclear Station, and R.E. Ginna Nuclear Power Plant.
This submittal contains no regulatory commitments.
Should you have any questions regarding the information in this submittal, please contact Dr. F.J. Mis at (410) 897-5028 or Frederic.Mis(@constellation.com.
Very truly yours, Join M. Heffley ief Nuclear Officer JMH/IEMT/jmp
Mr. Stuart A. Richards July 31, 2006 Page 2 Attachments: (1) Calvert Cliffs Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire (2) Nine Mile Point Nuclear Station Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire (3) R.E. Ginria Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire cc: Document Control Desk Resident Inspector, NRC (NMPNS)
P. D. Milano, NRC T. G. Colbum, NRC S. J. Collins, NRC R. I. McLean, Maryland DNR Resident Inspector, NRC (Ginna) J. P. Spath, NYSERD Resident Inspector, NRC (Calvert Cliffs) P. Eddy, NYS Dept. of Public Services Ralph Anderson, NEI
ATTACHMENT (1)
Calvert Cliffs Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Constellation Generation Group, LLC July 31, 2006
Calvert Cliffs Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire
- 1. Briefly describe the programand/ormethods usedfor detection of leakage or spillsfrom plant systems, structures,and components that have a potentialfor an inadvertentrelease of radioactivityfrom plant operationsinto groundwater.
The condition of structures, systems, and components is constantly monitored in the normal course of plant operation. In addition, the system engineering group does a walkdown of plant components (e.g., the refueling water tank) and inspects the area for visual indication of liquid leakage (e.g., boric acid buildup, wetted areas). Shallow monitoring wells (water table is approximately 38 feet below grade) are monitored for gamma and tritium activity as required by plant procedures. Any unusual conditions are captured in the plant corrective action program.
- 2. Briefly describe the program and/ormethodsfor monitoringonsite groundwaterfor the presence of radioactivityreleasedfromplant operations.
There are five shallow monitoring wells (piezometer tubes) onsite. All of these piezometer tubes are sampled quarterly as required by approved plant procedures. The shallow monitoring wells are monitored for gamma and tritium activity as required by plant procedures. Samples can also be taken from the deep-water aquifers, if required.
- 3. If applicable,briefly summarize any occurrencesof inadvertentreleasesof radioactiveliquidsthat had the potentialto reach groundwaterand have been documented in accordancewith 10 CFR 50.75(g).
On December 3, 2005, tritium was discovered in a shallow monitoring well. The contamination was due to an eroded pipe in a sub-surface drainage system connected to the plant circulating water system, which is a normal discharge pathway for permitted releases. During an annual surveillance of piezometer tubes (i.e., shallow monitoring wells), low levels of tritium (1,800 pCi/l +/- 960 pCi/l) were found in piezometer tube # 11. No gamma activity was detected. The piezometer tubes are 2-inch diameter, partially slotted, PVC pipe buried in the soil to a depth of about 49 feet. The piezometer tubes were installed during original plant construction to measure the depth of the water table and are not used for drinking water. The tritium contamination is contained within the protected area on site. Piezometer tube # 11 is located approximately 40 feet from the turbine building and is approximately 273 feet from the nearest location to the Chesapeake Bay. Additionally, Piezometer tube #11 is approximately 3,400 feet from the nearest land based site boundary. No tritium contamination associated with Piezometer tube #11 is known to have migrated off site. Tritium is currently below detection limits for Calvert Cliff's instruments; however, analysis by a vendor laboratory indicates tritium in this Piezometer tube is approximately 88 pCi/l.
- 4. If applicable,briefly summarize the circumstancesassociatedwith any onsite or osite groundwatermonitoringresult indicatinga concentrationin groundwaterof radioactivityreleased from plant operationsthat exceeds the maximum contaminantlevel (MCL) establishedby the USEPA for drinking water.
Calvert Cliffs has not had any onsite or offsite groundwater monitoring results exceeding the maximum contaminant level for drinking water.
- 5. Briefly describe any remediation efforts undertaken orplannedto reduce or eliminate levels of radioactivityresultingfrom plant operationsin soil orgroundwater onsite or offsite.
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Calvert Cliffs Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Sampling as described will be continued. The spill prevention program is also supported by the walkdown described in Question 1. No remediation efforts have been undertaken for the tritium discussed in Question 3. The source of the contamination has been repaired. The well and surrounding wells will continue to be monitored.
In general, when a spill or leak is discovered, some form of remediation is generally undertaken immediately to minimize any potential for the spread of contamination and to minimize the efforts that may later be required at decommissioning. This remediation may be as simple as excavating small amounts of soil or using absorbents or mops to remove contamination. Alternatively, remediation may involve removing larger sections of asphalt or rocks. Additional details for each spill or leak are contained in the 50.75(g) file maintained on site.
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ATTACHMENT (2)
Nine Mile Point Nuclear Station Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Constellation Generation Group, LLC July 31, 2006
Nine Mile Point Nuclear Station Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire
- 1. Briefly describe the program and/ormethods usedfor detection of leakage or spillsfrom plant systems, structures,and components that have a potentialfor an inadvertentrelease of radioactivityfrom plant operationsinto groundwater.
The condition of structures, systems, and components is constantly monitored in the normal course of plant operation. In addition, the operations group does a walkdown of plant components (e.g., discharge piping) and inspects the area for visual indication of liquid leakage (e.g., wetted areas). Groundwater is monitored in shallow wells (10-20 feet below grade) for gamma and tritium activity as required by plant procedures. Any unusual conditions are captured in the plant corrective action program.
- 2. Briefly describe the programand/ormethods fJor monitoringonsite groundwaterfor the presence of radioactivityreleasedfrom plant operations.
There are two up-gradient shallow wells and several shallow wells down-gradient that are used for monitoring purposes. These are not drinking water wells. Storm drains for NMP-2 include depression cone water (groundwater) and building sumps in NMP-1 and -2 serve to collect water with possible contamination. The wells are monitored for tritium on a semi-annual basis. Gamma spectroscopy is performed weekly and tritium analysis is performed quarterly on the storm drains, which include building sumps.
- 3. If applicable,briefly summarize any occurrencesof inadvertentreleasesof radioactiveliquids that had the potentialto reach groundwaterand have been documented in accordancewith 10 CFR 50.75(g).
Nine Mile Point has not had any inadvertent releases that had the potential to reach the groundwater.
- 4. If applicable,briefly summarize the circumstances associatedwith any onsie or offsite groundwatermonitoringresult indicatinga concentrationin groundwaterof radioactivityreleased fromplant operationsthatexceeds the maximum contaminantlevel (MCL) establishedby the USEPA for drinking water.
Nine Mile Point has not had any onsite or offsite groundwater monitoring results exceeding the maximum contaminant level for drinking water.
- 5. Briefly describe any remediation efforts undertaken orplanned to reduce or eliminate levels of radioactivityresultingfrom plant operationsin soil or groundwateronsite or offsite.
Nine Mile Point has not had any unmonitored releases or spills that required remediation efforts.
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ATTACHMENT (3)
R.E. Ginna Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire Constellation Generation Group, LLC July 31, 2006
R.E. Ginna Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire
- 1. Briefly describe the programand/or methods usedfor detection of leakage or spillsfrom plant systems, structures,and components that have a potentialfor an inadvertentrelease of radioactivityfrom plant operationsinto groundwater.
The condition of structures, systems, and components is constantly monitored in the normal course of plant operation. In addition, the system engineering group does a walkdown of plant components (e.g., the refueling water tank) and inspects the area for visual indication of liquid leakage (e.g., boric acid buildup, wetted areas). Shallow monitoring wells (approximately 17 feet below grade) are monitored for gamma and tritium activity as required by plant procedures. Any unusual conditions are captured in the plant corrective action program.
- 2. Briefly describe the programand/or methods for monitoringonsite groundwaterfor the presence of radioactivityreleasedfromplantoperations.
Ginna has four total groundwater wells and one bedrock well. The down-gradient well is screened at three depths in order to catch any radionuclides in any form. Another well is in the generally down-gradient direction between the Retention Tank and the lake, and is adjacent to the bedrock well.
Another well is between the Contaminated Storage Building and the onsite creek in a generally up-gradient direction. These are not drinking water wells. The shallow monitoring wells are monitored for gamma and tritium activity as required by plant procedures.
Soil sampling is conducted in association with moving dirt from onsite or for excavation activities where dirt is to be relocated out of the protected area. Soil sampling is also conducted in accordance with the Radiological Environmental Monitoring Program for selected areas onsite, and those samples are analyzed for gamma activity.
- 3. If applicable, briefly summarize any occurrences of inadvertent releases of radioactiveliquids that had the potentialto reach groundwaterand have been documented in accordancewith 10 CFR SO. 7s(g).
In 1982, a steam generator tube rupture released activity into the ground. This incident is documented in NUREG-0909, NRC Report on the January 25, 1982 Steam Generator Tube Rupture at R.E. Ginna Nuclear Power Plant.
In 1995 the Steam Generator overboard blowdown piping was discovered to have degraded and secondary coolant was in contact with groundwater. Ginna had significant (50 cc/min) primary-to-secondary leakage at that time. A spike of 20,000 pCi/L of tritium, with no other radionuclides, was detected in down-gradient sample wells. This unmonitored release was discussed with the NRC Region I office under Information Notice 80-10 criteria. The blowdown piping was repaired, the steam generators have since been replaced, and subsequent groundwater monitoring has detected no further tritium releases
- 4. If applicable,briefly summarize the circumstancesassociatedwith any onsite or offsite groundwatermonitoringresult indicatinga concentrationin groundwaterofradioactivityreleased from plant operationsthat exceeds the maximum contaminantlevel (MCL) establishedby the USEPAfor drinking water.
Ginna has not had any offsite groundwater monitoring results exceeding the maximum contaminant level for drinking water.
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R.E. Ginna Nuclear Power Plant Industry Groundwater Protection Initiative Voluntary Data Collection Questionnaire The 1995 steam generator overboard blowdown piping resulted in an unmonitored release from operations that met the MCL established by the USEPA for drinking water.
- 5. Briefly describe any remediation efforts undertaken orplanned to reduce or eliminate levels of radioactivityresultingfrom plant operationsin soil or groundwateronsite or offsite.
Sampling as described will be continued. The spill prevention program is also supported by the walkdown described in Question 1. The contamination resulting from the steam generator events was monitored and did not result in continued contamination.
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