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Category:Letter
MONTHYEARML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0432024-11-0101 November 2024 Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0152024-11-0101 November 2024 Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24303A0552024-11-0101 November 2024 Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0472024-11-0101 November 2024 Letter to G. Cheatham, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) ML24291A0202024-10-31031 October 2024 NRC Letter to J. Loichinger Achp Request for Comments Concerning the Environmental Review of DNPS Units 2 and 3 Subsequent License Renewal Application ML24291A0272024-10-31031 October 2024 NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3 IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-102, Supplement to 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, and TSTF-5912024-10-21021 October 2024 Supplement to 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, and TSTF-591 RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24225A2132024-09-26026 September 2024 Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval ML24253A0942024-09-23023 September 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID L-2024-Sle-0002) (Docket Numbers: 50-237 and 50-249) SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24260A2152024-09-16016 September 2024 Confirmation of Initial License Examination ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation2024-01-19019 January 2024 HPCI Inoperable Due to Air Void Accumulation 05000237/LER-2022-001-01, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-10-28028 October 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000237/LER-2022-002-01, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-10-28028 October 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-002, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-09-27027 September 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-001, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-09-0909 September 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000249/LER-2021-001-01, Reactor Scram Due to Main Power Transformer Failure2022-06-14014 June 2022 Reactor Scram Due to Main Power Transformer Failure ML20135G7442020-05-14014 May 2020 Final ASP Analysis - Dresden 2 (LER 237-90-006) 05000249/LER-2017-0012017-12-27027 December 2017 Unit 3 Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak, LER 17-001-01 for Dresden Nuclear Power Station, Unit 3 Regarding Unit 3 Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak ML17252B5052017-11-0303 November 2017 LER 77-050/03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling ML17252A3262017-10-21021 October 2017 LER 77-040/03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position ML17252B4922017-08-28028 August 2017 LER 78-028/01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction 05000237/LER-2016-0032017-05-26026 May 2017 Control Room Emergency Ventilation System Charcoal Filter Bank Failure to meet the Methyl Iodide Penetration Acceptance Criteria, Dresden Nuclear Power Station, Units 2 and 3, Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to meet the Methyl Iodide Penetration Acceptance Criteria ML17153A0342017-05-26026 May 2017 Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000237/LER-2016-0042017-01-0909 January 2017 Reactor Building Differential Pressure Less than Technical Specification Requirement, LER 16-004-00 for Dresden Nuclear Power Station, Unit 2, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement 05000249/LER-2016-0012016-08-25025 August 2016 Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire, LER 16-001-00 for Dresden Nuclear Power Station Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire 05000237/LER-2016-0022016-07-15015 July 2016 Unit 2 HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability, LER 16-002-00 for Dresden Nuclear Power Station, Unit 2 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability 05000237/LER-2016-0012016-04-0808 April 2016 Secondary Containment Differential Pressure Transient, LER 16-001-00 for Dresden Nuclear Power Station, Unit 2 and 3 Regarding Secondary Containment Differential Pressure Transient 05000249/LER-2015-0012016-01-22022 January 2016 Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value, LER 15-001-01, Dresden, Unit 3 Main Steam Line Flow Switched Found Outside Tech Spec Allowed Value ML1015505692009-07-24024 July 2009 Letter LS-AA-1 25-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping for Dresden Units 2 and 3. ML0602404072004-05-0505 May 2004 Final Precursor Analysis - Dresden Unit 3 - Unit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3 ML0234501722002-12-0202 December 2002 LER 89-029-05, Dresden Unit 2, Elevated HPCI Discharge Piping Temperature Due to Reactor Feedwater System Back Leakage ML17252B5391981-06-10010 June 1981 LER 81-034/03L-0 for Dresden, Unit 2 Re J-3 CRD Was Tested for Overtravel. the Overtravel Alarm Came Up and Rod Position Indication Was Lost ML17252B5411981-06-0808 June 1981 LER 81-030/01T-0 for Dresden, Unit 2 Re Operator Noticed the HPCI Steam Line Was Cold and Filled with Water. the HPCI System Was Declared Inoperable ML17252B5401981-06-0505 June 1981 LER 81-024/03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue ML17252B5271981-06-0303 June 1981 LER 81-023/03L-0 for Dresden, Unit 2 Re While Running HPCI Pump Test, the Operator Observed Torus Wide Range Level Instrument Reading 0 Inches and Narrow Range Level Instrument Reading, About - 2 Inches and Oscillating ML17252B5281981-04-14014 April 1981 LER 81-015/03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1 ML17252B5291981-03-23023 March 1981 LER 81-011-03L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered Safe ML17252B5301981-02-20020 February 1981 LER 81-080/031-0 for Dresden, Unit 2 Re Abnormal Degradation of Systems Other than Those Specified in Item B.1.e Above Designed to Contain Radioactive Material Resulting from the Fission Process ML17252B5321981-02-17017 February 1981 LER 81-070/03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip ML17252B5331981-02-0202 February 1981 LER 81-020/03L-0 for Dresden, Unit 2 Re During Refueling Outage LPCI Test Spray Valve Failed to Shut Electrically, One Set of Thermal Contacts Would Not Reset ML17252B5351981-01-23023 January 1981 LER 80-050/03L-0 for Dresden, Unit 2 Re the 1501-62D Pressure Switch Actuated at 44.2 Inches of Water Increasing, Tech. Spec. Limit Is Less than or Equal to 41.6 Inches of Water Increasing ML17252B5341981-01-23023 January 1981 LER 80-049/03L-0 for Dresden, Unit 2 Re at Completion of Secondary Containment Leak Rate Test the Reactor Building Ventilation Isolation Valve 2A-5742 Would Not Open ML17252B5371980-12-30030 December 1980 LER 80-046-00 for Dresden 2 Regarding a Failure to Receive CRD Volume During a Reactor Scram ML17252B5361980-12-29029 December 1980 LER 80-046/03L-0 for Dresden, Unit 2 Re Conditions Leading to on Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation ML17252B5381980-12-0303 December 1980 LER 80-043/03L-0 for Dresden, Unit 2 Re Surveillance Testing of the Condenser Low Vacuum Switches, Pressure Switch 2-503D Was Found to Have a Trip Point of 22.85 Inches Hg ML17252B5431980-11-12012 November 1980 LER 80-041/03L-0 for Dresden, Unit 2 Re Reactor Building Vent and Refueling Floor Rad Monitor Surveillance (DCP 2007-12) Was Performed ML17252B5421980-11-12012 November 1980 LER 80-042/03L-0 for Dresden, Units 2 and 3 Re That Technical Staff Personnel Revealed That the Ultrasonic Testing of the Scram Discharge Volume Was Not Performed During the 1500-2300 Shift ML17252B1841980-10-31031 October 1980 LER 80-40/01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open ML17252B5441980-10-29029 October 1980 LER 80-039/03X-1 for Dresden, Unit 2 Re HPCI Inboard Steam Supply Valve Opened and Had a Dual Light Indication ML17252B5451980-10-23023 October 1980 LER 79-017-01X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety ML17252B5461980-10-0808 October 1980 LER 80-016/01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line ML17252B5471980-10-0707 October 1980 LER 80-036/03L-0 for Dresden, Unit 2 Re Discovery That the Six Month Functional Test Required by Tech. Spec. 4.12.A.1 of the Cardox System Heat Detectors Was Not Performed within the Allowable Surveillance Interval ML17252B5481980-10-0101 October 1980 LER 80-033/03L-0 for Dresden, Unit 2 Re the Frequency of Water Addition to the Torus Increased. Leak Rate Tests Indicated a Leak in the 2B LPCI Heat Exchanger ML17252B1861980-08-22022 August 1980 LER 80-032/03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block ML17252B5501980-08-19019 August 1980 LER 80-027/03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator ML17252B5161980-08-14014 August 1980 LER 80-024/03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d ML17252B1881980-08-0404 August 1980 LER 80-030/03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds ML17252B1901980-06-13013 June 1980 LER 80-023/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches ML17252B1911980-06-13013 June 1980 LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches ML17252B1921980-06-10010 June 1980 LER 80-025/03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 2024-01-19
[Table view] |
Text
Commonwe. Edison Dresden Nuclear Power Station R.R. #1
- ~ WN *1 8 19BO Morris, Illinois 60450 Telephone 815/942-2920 June 13, 1,980
".. '!BBS LTR,. /180-508 James G. Kepp],er, Regional Di.rect;oi; Directorate of* Regulatory :. Operatt.ons - R,eg:;i.on I.U:
U.S. Nuclear Regulatory Commissi01;1 799 Roos*evelt Road Glen Ellyn, IL 6'0137 Reportabl,e Occurrence R,e.po:rt ii* 8Q.,:.23/03L-0 ,Dock.et I! 050-249 , is being submitted to your office i:n. acGord;:tn.ce w:tt;h D.resden N:uclear Power Station Technical Specificat;ion *6~6.B.2. (a), react.or protect;ion system or engineered safety feature instrument settings* whi.ch. aTe found to be less conservative than those established by the technica.l specifications but which do not pre-vent the fulfillment of the func!'ional requi.rement;s 0f affected systems.
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l3 ,B .. Ste.pheAso:n St;;at.t.on Superintendent
- Dresden Nuclear Power Station BBS:
Enclosure.
cc: Director of. In.spei::.t:;i.on.. & En.f<?rGemen.t Di.rector of Management. I:n.fonnat:;i.~on & Progi;~ Control File/N*RC Aoo~
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- 69 EVENT DATE 74. 75 REPORT DA TC:
10 80 I© EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES {iQ) . . .
I During nomal operation with reactor ~vel instrument surveillance in progress, level
[]JI)' I switch LIS 3-263-58A tripped at less than the Tech. Spec. limit (Table. 3.2.1) of 144 CQ:ill inches. The safety significance of this event was minimal since channel "B" and the C2:IrJ I redundant channel "A"* ins-truments were operable. There was no effect on public health
[)))) or safety. Previous occurrences: R. 0. 76-5 7 /031-0, Do.cket 50-237 and 77-51/031-0, I
((ill' Docket 50-249.
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CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS {27)
I The cause of this event* was a mis~igned Yarway switch assembly, model number 4418C, serial number 44180. The switch was adjusted and satisfactorily tested. DIS 500-2 will continue to be* performed monthly.
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