Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power PlantsML101270439 |
Person / Time |
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Site: |
Millstone, Hatch, Monticello, Dresden, Davis Besse, Peach Bottom, Salem, Oconee, Palisades, Palo Verde, Perry, Indian Point, Kewaunee, Catawba, Saint Lucie, Oyster Creek, Watts Bar, Braidwood, Susquehanna, Columbia, Seabrook, Brunswick, Surry, Turkey Point, River Bend, Vermont Yankee, Ginna, Callaway, Vogtle, Waterford, San Onofre, Quad Cities, Fort Calhoun, FitzPatrick |
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Issue date: |
05/05/2010 |
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From: |
Conatser R NRC/NRR/DIRS/IHPHPB |
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To: |
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Conatser, Richard 415-4039 |
References |
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FOIA/PA-2011-0115, Y020100187 |
Download: ML101270439 (4) |
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Similar Documents at Millstone, Hatch, Monticello, Dresden, Davis Besse, Peach Bottom, Salem, Oconee, Palisades, Palo Verde, Perry, Indian Point, Kewaunee, Catawba, Saint Lucie, Oyster Creek, Watts Bar, Braidwood, Susquehanna, Columbia, Seabrook, Brunswick, Surry, Turkey Point, River Bend, Vermont Yankee, Ginna, Callaway, Vogtle, Waterford, San Onofre, Quad Cities, Fort Calhoun, FitzPatrick |
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Category:Report
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[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Oconee]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Saint Lucie]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Ginna]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:San Onofre]] OR [[:Quad Cities]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] </code>. Category:Miscellaneous
MONTHYEARML24032A1112024-02-0101 February 2024 Owner'S Activity Report for North Anna, Unit 2, Refueling Outage N2R29 - First Period of the Fifth ISI Interval ML24018A0852024-01-31031 January 2024 Safety Determination of a Potential Structural Failure of the Full Basket During Accident Conditions for the HI-STORM 100 and HI-STORM Flood/Wind Dry Cask Storage Systems ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML23361A0322024-01-16016 January 2024 Summary and Preliminary Comments on Documents Provided by the United States Department of Energy in Support of the F-Tank Farm and H-Tank Farm Facility Performance Assessments NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) ML24005A2412024-01-0505 January 2024 Global Nuclear Fuel -Americas, L.L.C, 10 CFR 71 .95 - 60 Day Report - RAJ-II Certificate Condition of Approval Not Observed ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23356A0822023-12-22022 December 2023 Enclosure 2: Kairos Power, LLC, Changes to KP-TR-022 W3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23349A2062023-12-15015 December 2023 Missouri University of Science and Technology Reactor (Mstr), Follow-Up Report on EN-56878, Reportable Occurrence ML23338A2572023-12-14014 December 2023 Kairos Power LLC - Summary Record of Decision GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency 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) ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1432023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23324A4302023-11-20020 November 2023 Alloy 600 Aging Management Program Submittal Related to License Renewal Commitment 15 BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood ML23325A0382023-11-16016 November 2023 BWXT Nuclear Operations Group, Inc. - Lynchburg, Request for Exemption from Security Event Notification and Suspicious Activity Reporting Implementation in Accordance with 10 CFR 73.5 ML24012A0422023-11-16016 November 2023 FAQ 23-03 Turkey Point IE01 Proposed NRC Response ML23296A1132023-10-23023 October 2023 Greenhouse Gas Emissions Estimates for a Reference 1,000 Mwe Reactor and the Abliene Christian University Molten Salt Research Reactor ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23156A2412023-09-28028 September 2023 10 CFR Part 63- 60-day Supporting Statement 2023 L-2023-131, Subsequent License Renewal Application - Second Annual Update2023-09-28028 September 2023 Subsequent License Renewal Application - Second Annual Update ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23254A2302023-08-31031 August 2023 DOE, Isff ISFSI Biennial Update Report for 2023 ML23235A1722023-08-23023 August 2023 Re. Ginna Nuclear Power Plant, Transmittal of 2023 Owner'S Activity Report ML23209A6592023-08-23023 August 2023 Hermes Draft Construction Permit L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 ML23221A2412023-08-15015 August 2023 Penn State University - Evaluation in Support of the Pennsylvania State University Radiation Facilities, 2022 Financial Test for a Self Guarantee for Decommissioning Funding LG-23-059, Owner'S Activity Report (OAR-1) for Li2R 172023-08-10010 August 2023 Owner'S Activity Report (OAR-1) for Li2R 17 2024-02-01 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Oconee]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Saint Lucie]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Ginna]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:San Onofre]] OR [[:Quad Cities]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Oconee]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Saint Lucie]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Ginna]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:San Onofre]] OR [[:Quad Cities]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] </code>. |
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Rev 12, 4-Dec-13 List of Historical Leaks and Spills At U.S. Commercial Nuclear Power Plants Introduction This is a list of reactor sites that experienced a leak or spill to the environment at some time since initial startup. The list only includes those leaks or spills where tritium in the leak source or the groundwater sample was greater than 20,000 picocuries per liter (pCi/L). The term leaks and spills includes all types of non-routine releases in which tritium from reactor operation contacted the soil in an unintended fashion.
Source of Information This information was compiled by NRC staff and is based on available records including Annual Effluent Reports, Annual Environmental Reports, Groundwater Questionnaires, Preliminary Notifications, Event Notifications, Licensee Event Reports, NRC Inspection Reports, Special Reports, and other documents submitted by the licensees to the NRC. Although the records search was extensive, extending back to the 1970s, the search was not all inclusive.
Purpose The NRC has received many questions from the public, the news media, and politicians concerning spills and leaks at power reactor sites. Although most of these questions were similarly focused on groundwater contamination, the questions were different enough to produce significant variations in the responses. This list is intended to be the best single response to those questions involving numbers such as:
- How many sites have had leaks or spills of radioactive material?
- What concentrations of tritium were involved?
- What are the current tritium concentrations at each of the sites?
Contents The tritium concentrations listed include (1) the approximate historical maximums and (2) the current concentrations. The values shown provide a reasonable indication of the magnitude and extent of the historical leaks and spills as well at the current conditions at these sites.
The approximate historical maximum concentration reflects the result of a single leak or spill at a site. In this way, it is a snapshot of the maximum concentration on the date listed. Although a particular value may remain on this list, in reality it is not stagnant. The maximum concentration begins to decrease immediately, and continues to decrease over time. Additionally, the maximum concentration decreases as the material travels through the soil due to dilution and dispersion. As a result, this report also includes the current concentration of tritium to provide some perspective on how the tritium concentrations decrease over time.
The value listed as the current concentration lists the highest tritium concentration found in the environment, on facility property, at the current time or within approximately the last year. The values listed do not necessarily credit any remediation - such as soil removal - that may have occurred following a leak or spill. This is because the analysis results prior to remediation are typically broadly communicated, whereas the analysis results after remediation may not be
readily available or as broadly communicated. As a result, for some sites the actual current tritium concentration will be less than the value indicated. Even so, the current concentration listed below provides a reasonable approximation of the plume concentration currently on each site. If a value has not been updated within the past year, it indicates the value listed is a good approximation of the current site conditions. The current status of these sites reflects the most recently available information as of the date shown at the top of this page. This list will be revised as new information becomes available.
Samples are collected from onsite and offsite locations. Samples are collected from both drinking water wells and non-drinking water sample points (e.g., storm drains, man holes, bore holes, piezometer tubes, monitoring wells, surface water, puddles, and rain water). All of these samples are evaluated for inclusion in this list. Although some values in the list exceed 20,000 pCi/L, none of those samples were from a drinking water well or from a municipal drinking water system. In fact, although samples are collected from drinking water wells and municipal drinking water systems, none of those samples have ever exceeded 20,000 pCi/L. As a result, a value of 20,000 pCi/L in this list does not imply the drinking water standard in EPAs Safe Drinking Water Act has been exceeded.
After a radioactive spill or leak, tritium is generally the first radionuclide to be identified in groundwater. This is because tritium travels through the soil faster than other radionuclides.
Leaks and spills at some sites (e.g., Indian Point, Braidwood) involved nuclides other than tritium (e.g., Cobalt-60, Cobalt-58, Cesium-134, Cesium-137, Strontium-90, Nickel-63), but those radionuclides are not included in this list.
Significant Changes in this Version
- The current status of several sites were reviewed and updated accordingly.
Summary There are 65 locations in the United States where commercial nuclear power plants are operating. Records indicate 45 of these sites have had leaks or spills that involved tritium in excess of 20,000 pCi/L at some time during their operating history. Eighteen sites are currently reporting tritium, from a leak or spill, in excess of 20,000 pCi/L. Although many sites have had leaks or spills involving tritium, no site is currently detecting tritium in the offsite environment, or in drinking water, in excess of 20,000 pCi/L.
Tritium rapidly disperses and dissipates in the environment, and as a result, tritium from leaks and spills is typically not detected outside the facility boundary. The historical data indicates in only one instance, at Braidwood, was tritium from a leak or spill found in the offsite environment in excess of 20,000 pCi/L. All samples from Braidwood since 2008 indicate tritium is no longer present in excess of 20,000 pCi/L in either the onsite or the offsite environment.
Conclusion The existing complement of 104 power reactors, each operating for approximately 20-40 years, represents approximately 3,000 reactor years of operation. During that time, leaks and spills involving tritium have occurred at many commercial power reactors in the United States. This list demonstrates that in all of that time, and with all the leaks and spills that have occurred, no drinking water supply has exceeded the allowable level for tritium specified in EPAs Safe Drinking Water Act.
Rev 12, 4-Dec-13
List of Historical Leaks and Spills At U.S. Commercial Nuclear Power Plants It is imperative that the preceding paragraphs accompany any reproduction of this list so that the information is communicated in the proper context.
Approximate Historical Approx Plant Date of Status Maximum Date of Current Concentration of Update Tritium Historical Tritium (or highest concentration Concentration, Maximum in approximately the last year),
- pCi/l Tritium pCi/l 1 Beaver Valley 25,583 30-Sep-10 19,200 30-Sep-12 2 Braidwood 247,000 1998 3,800 11-Jun-12 3 Browns Ferry 2,050,000 7-Apr-10 1,013 31-Dec-11 4 Brunswick 19,000,000 Dec-2010 3,539,000 17-May-11 5 Byron 82,000 13-Feb-06 1,150 July-2011 6 Callaway 200,000 June 2006 9,654 18-Mar-11 7 Catawba 47,500 8-Oct-07 11,300 20-Mar-12 8 Columbia 270,000 13-Mar-93 1,300 7-Nov-12 9 Crystal River 360,000 21-Apr-98 50,000 Jan-11 10 Davis-Besse 37,500 23-Oct-08 707 31-Dec-12 11 Dresden 10,312,000 31-Jul-04 85,000 28-Nov-11 12 Duane Arnold 2,150,000 12-Oct-12 2,150,000 12-Oct-12 13 Fitzpatrick, J.A. 105,000 Apr-2011 34,000 Jun-2011 14 Ginna, R.E. 20,000 1995 Not detectable from 1995 event 31-Dec-11 15 Hatch, E.I. 6,840,000 29-Sep-11 5,000,000 31-Dec-12 16 Indian Point 600,000 2005 137,000 31-Dec-11 17 Kewaunee >20,000 2006 1,257 24-Oct-11 18 Limerick 3,950,000 13-Feb-09 345 Oct-2012 19 LaSalle 715,000 30-Jun-10 290,000 16-Nov-11 20 Millstone 4,000,000 28-Nov-07 10,600 5-Dec-11 21 Monticello 21,300 12-Sep-09 2,317 31-Dec-11 22 Nine Mile Point 44,000 14-Aug-12 Not detectable Nov-2012 23 North Anna 53,300 22-Dec-11 53,300 22-Dec-11 24 Oconee 35,600 Feb-10 45,000 31-Dec-11 25 Oyster Creek 10,800,000 24-Aug-09 218,000 11-Oct-11 26 Palisades 217,351 31-Dec-09 8,952 28-Feb-12 27 Palo Verde 4,200,000 19-Mar-93 None detectable 31-Dec-12 28 Peach Bottom 196,000 8-Mar-10 31,900 21-Nov-11 29 Perry 59,900 2006 200 31-Dec-12 Approximate Approx Current Concentration of Date of Status Historical Date of Tritium (or highest concentration
- Plant Update Maximum Historical in approximately the last year),
Tritium Maximum pCi/l Concentration, Tritium pCi/l 30 Pilgrim 25,552 7-Jul-10 1,290 1-Nov-11 31 Quad Cities 7,500,000 2008 375,000 1-Jan-11 32 River Bend 1,135,000 25-Feb-13 1,135,000 25-Feb-13 33 Salem 15,000,000 Apr-2003 36,200 Sep-2012 34 San Onofre 330,000 7-Aug-06 3,700 19-Dec-12 35 Seabrook 750,000 1999 2,051 16-Nov-11 36 St. Lucie 161,000 2000 6,270 31-Jan-10 37 Summer 23,000 7-Jul-11 23,000 7-Jul-11 38 Surry 31,900 2007 13,400 15-Feb-11 39 Susquehanna >20,000 1995 Not detected 31-Dec-10 40 Three Mile 900,000 1981 5,400 22-Nov-12 Island 41 Turkey Point >20,000 1979 5,320 31-Dec-10 42 Vermont 2,500,000 8-Feb-10 76,200 30-Apr-12 Yankee 43 Vogtle >20,000 1990s 1,100 31-Dec-11 44 Waterford >20,000 1997 Not detected 31-Dec-11 45 Watts Bar 550,000 8-Feb-05 13,363 9-Nov-11