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Category:Letter
MONTHYEARNMP1L3570, 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 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations 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)) 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 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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 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 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 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 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 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARML16319A0982016-11-0808 November 2016 Special Report: Inoperable Drywell Pressure Monitor/Suppression Chamber Water Level Instrumentation ML15174A1282015-06-19019 June 2015 Special Report: Containment High Range Radiation Monitor Instrumentation Channel #12 Inoperable NMP1L2980, 10 CFR 50.46 30-Day Report2014-12-12012 December 2014 10 CFR 50.46 30-Day Report ML12268A0492012-09-12012 September 2012 Discovery of Tritium in Groundwater In-Leakage - 30-Day Report in Accordance with the Industry Ground Water Protection Initiative ML11165A2212011-06-0606 June 2011 Day Report Pursuant to 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors ML1109701512011-04-0101 April 2011 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML0919505792009-07-0808 July 2009 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable ML0913904002009-05-11011 May 2009 Submittal of Containment High Range Radiation Monitor Instrumentation Channel 11 Inoperable ML0802305112008-01-11011 January 2008 Special Report: Inoperable Suppression Chamber Water Level Instrument ML0701704682007-01-11011 January 2007 Report of Changes or Errors Discovered in the Current Acceptable Emergency Core Cooling System Evaluation Models ML0618703962006-06-19019 June 2006 Special Report; Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Unplanned Maintenance ML0526401672005-09-12012 September 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0525004162005-08-29029 August 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0522402502005-08-0303 August 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0506901722005-03-0101 March 2005 Special Report, Channel No. 11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0502501452005-01-17017 January 2005 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0420403002004-07-12012 July 2004 Special Report, Channel #12 of the Containment Hydrogen Monitoring System Inoperable for Nine Mile Point Unit 1 ML0407607562004-03-0505 March 2004 Special Report, Channel #11 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0406409232004-02-20020 February 2004 Special Report, Channel #12 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0236101942002-12-13013 December 2002 Special Report, Channel #12 Accident Monitoring Instrumentation Inoperable Due to Loss of Power ML0233304002002-10-31031 October 2002 Special Report, Channel #11 Containment High Range Radiation Monitor Declared Inoperable to Repair Failed Chart Recorder ML0207905522002-03-0404 March 2002 Special Report Re Channel 12 Chamber Water Level Indicator Inoperable ML0208404412002-02-25025 February 2002 Special Report, Channel #11 Containment High Range Radiation Monitor Inoperable ML0206502942002-02-20020 February 2002 Special Report Re Channel #12 Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0205801952002-02-0808 February 2002 Special Report, Channel #12 Suppression Chamber Water Level Indicator Inoperable ML0205002372002-01-21021 January 2002 Special Report Re Channel 11 Containment Hydrogen Monitoring System Inoperable for Scheduled Elective Maintenance ML18094A0311977-09-0707 September 1977 Telecopy Message from Niagara Mohawk Power Corp Re Event on 9/7/1977 Re August 1977 Liquid Waste Monthly Chemical Composite Analysis ML17037C1301972-08-0101 August 1972 Letter Reporting an Orderly Shutdown on July 27, 1972 Due to Increasing Recirculation System Valve Packing Leakage within the Drywell ML17037C1011972-04-19019 April 1972 Letter Reporting Findings on Incident That Occurred on 12/31/1971 in Which Unit 1 Tripped Off Line as Result of Surveillance Testing ML17037C1021972-04-18018 April 1972 Letter Reporting an Incident Tripped Off-Line as a Result of a Malfunction in a Continuous Power Supply on 02/28/72 ML17037C1371971-09-25025 September 1971 Letter Regarding a Maintenance Item Occurring During the Outage of Unit 1 in April-May 1971 ML17037C1421970-03-10010 March 1970 Letter Reporting an Incident, During Radiography and Ultrasonic Testing, That Disclosed a Series of Cracks Extending Around the Upper 180 Degrees of the Inside Diameter, Exist in the Stainless Steel Safe-End of the Core Spray.. ML17037C1431970-03-0606 March 1970 Letter Notifying the Commission of a Situation in Which Waste Discharge in Excess of Technical Specifications Has Taken Place on February 26, 1970 ML17037C1441969-12-0606 December 1969 Letter Reporting That the Nine Mile Point Reactor Was Scrammed from 25 Percent Power on November 20, 1969 and Advising That the Reactor Will Be Brought Critical and the Turbo-Generator Set Placed on the Line on December 8, 1969 ML17037C1451969-11-18018 November 1969 Letter Reporting an Incident on November 8, 1969 Where the Reactor Scrammed on Momentary Upscale Trips from Intermediate Range Monitoring Channels 2016-11-08
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-,en Lartalcn P.O.Bt 33 Vice President-Mine 'ile Point Lycoming, Nlew Yorht 13093 31 5.34912 F--a;,
CENG.
a joint venture of Constellation Jrf'n Energy* , eDF NINE MILE POINT NUCLEAR STATION September 12, 2012 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Discovery of Tritium in Groundwater In-Leakage 30-Day Report in Accordance with the Industry Ground Water Protection Initiative Nine Mile Point Nuclear Station, LLC (NMPNS) hereby submits the attached 30-day report in accordance with Nuclear Energy Institute (NEI) 07-07, "Industry Ground Water Protection Initiative -
Final Guidance Document," dated August 2007. Samples taken from groundwater in-leakage to the Nine Mile Point Unit 1 Screenhouse building were found to contain tritium in concentrations that exceeded the threshold value for voluntary reporting in accordance with the guidance in NEI 07-07. The initial NRC notification of this condition was completed on August 14, 2012 (Event Number 48187).
This letter contains no regulatory commitments. Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.
Very truly yours, KL/KES
-T--e r7
Document Control Desk September 12, 2012 Page 2
Attachment:
Nine Mile Point Unit 1, Discovery of Tritium in Groundwater In-Leakage, 30-Day Report in Accordance with the Industry Ground Water Protection Initiative cc: Regional Administrator, Region I, NRC Project Manager, NRC Resident Inspector, NRC A. L. Peterson, NYSERDA B. Frymire, NYPSC T. Rice, NYS DEC C. Costello, NYSDOH T. Murakami, NYSDEC M. Anderson, ANI R. Andersen, NEI P. Egan, Oswego County K. Burdick, Scriba Town Supervisor
g ATTACHMENT NINE MILE POINT UNIT 1 DISCOVERY OF TRITIUM IN GROUNDWATER IN-LEAKAGE 30-DAY REPORT IN ACCORDANCE WITH THE INDUSTRY GROUND WATER PROTECTION INITIATIVE Nine Mile Point Nuclear Station, LLC September 12, 2012
ATTACHMENT NINE MILE POINT UNIT 1 DISCOVERY OF TRITIUM IN GROUNDWATER IN-LEAKAGE, 30-DAY REPORT IN ACCORDANCE WITH THE INDUSTRY GROUND WATER PROTECTION INITIATIVE This report is being submitted in accordance with the Nuclear Energy Institute (NEI) 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. The report was generated as a result of the Nine Mile Point Nuclear Station (NMPNS) Groundwater Monitoring Program tritium result for building in-leakage which triggered the communication protocol as required by the NEI 07-07.
On August 13, 2012, analyses of samples taken from groundwater in-leakage to the Nine Mile Point Unit 1 (NMP1) Screenhouse building confirmed the presence of tritium at a concentration of approximately 33,000 to 44,000 picocuries per liter (pCi/1). The discovery was made during the conduct of the site's ongoing groundwater monitoring program. The concentration was above the 30,000 pCi/l threshold for voluntarily reporting for a non-drinking water pathway, as indicated in NEI 07-07. On August 14, 2012, NMPNS voluntarily notified the following agencies: New York State (NYS) Department of Environmental Conservation, NYS Department of Health, NYS Public Service Commission, local officials, NEI, Institute of Nuclear Power Operations (INPO) and American Nuclear Insurers (ANI). A 10CFR50.72(b)(2)(xi) report was made to the Nuclear Regulatory Commission (NRC) as a result of the State and Local notifications.
NMPNS established a cross-functional Issue Response Team (IRT) to investigate possible sources of tritium in the groundwater in-leakage. The IRT reviewed the hydrogeologic models prepared in accordance with the NEI 07-07 guidance and the location of groundwater monitoring wells in the area.
Based on this review, six (6) additional wells are being installed to better define the potential tritium plume and verify groundwater flows in the area. The IRT identified twenty five (25) potential failure modes that could be the source of the tritium. Twenty one (21) of these failure modes have been refuted and the remaining four (4) are currently being investigated.
NMPNS is currently collecting the building groundwater in-leakage in storage tanks, determining tritium levels and then discharging the water in accordance with the NMPI Offsite Dose Calculation Manual (ODCM) and discharge procedures. The potential or bounding annual dose to a member of the public from the discharge water is calculated in accordance with the NMP1 ODCM. Currently, NMP1 has discharged approximately 84,000 gallons of water with a calculated projected annual dose of 5.58E-6 millirem (mrem). The current projected annual dose is well below the Environmental Protection Agency's 40 CFR 190.10 Subpart B dose for the uranium fuel cycle of 25 mrem/year to the total body.
Monitoring wells located at the site boundary indicate that tritium in the groundwater has not migrated off the plant property. Accordingly, there is no public exposure pathway in groundwater and no estimated annual dose to any member of the public via a groundwater pathway.
Since there is no estimated annual dose increase to a member of the public from the groundwater pathway and discharges from the collection tanks are managed in accordance with the NMP ODCM, no corrective actions are necessary to reduce the. projected annual dose to a member of the public to less than the limits of 10 CFR 50, Appendix I of 5 mrem to the total body or any organ. NMPNS will continue to monitor the event and will initiate corrective actions as needed.
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