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Category:Letter
MONTHYEARML24352A2072024-12-17017 December 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24323A0792024-11-15015 November 2024 Transmittal of Dresden, Units 2 and 3, Core Operating Limits Report Cycle 29 ML24317A1432024-11-0404 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 ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson 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 ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman 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 ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, 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 ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, 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 ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief 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 RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President 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 ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, 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 ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman 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 ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman 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 ML24303A0552024-11-0101 November 2024 Letter to J. Keys, 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 ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson 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 ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman 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 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 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) 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-24-102, 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-24-103, 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-24-080, 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) ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24299A1922024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual 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 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-2019-001, Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications2019-11-19019 November 2019 Degraded Differential Pressure Indicating Switch in the LPCI Loop Select Logic Caused by Water Damage Results in a Condition Prohibited by Technical Specifications 05000237/LER-2019-002, Scram Due to Main Turbine Low Oil Pressure Trip2019-07-0202 July 2019 Scram Due to Main Turbine Low Oil Pressure Trip 05000237/LER-2019-001, Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow2019-03-29029 March 2019 Secondary Containment Differential Pressure Exceeded Technical Specification Due to Excess Ventilation Supply Flow 05000237/LER-2017-002-01, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage2018-02-15015 February 2018 Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage 05000237/LER-1917-002, Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits2018-01-0202 January 2018 Regarding Primary Containment Inboard and Outboard Feedwater Isolation Valves Exceed Leakage Limits 05000249/LER-1917-001, Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak2017-11-10010 November 2017 Regarding Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak 05000237/LER-1977-050, /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling2017-11-0303 November 2017 /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling 05000249/LER-1977-040, /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position2017-10-21021 October 2017 /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-1978-028, /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 Suct2017-08-28028 August 2017 /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 Valves 05000237/LER-1916-003, 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 Criteria2017-05-26026 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-2016-004, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement2017-01-0909 January 2017 Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement 05000237/LER-2016-003, Regarding Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria2016-11-18018 November 2016 Regarding Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000249/LER-2016-001, Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire2016-08-25025 August 2016 Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire 05000237/LER-2016-002, Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability2016-07-15015 July 2016 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability 05000237/LER-2016-001, Regarding Secondary Containment Differential Pressure Transient2016-04-0808 April 2016 Regarding Secondary Containment Differential Pressure Transient 05000237/LER-2015-005-02, Regarding Unit 2 HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2016-03-31031 March 2016 Regarding Unit 2 HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-005-01, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2016-02-25025 February 2016 Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-005, Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing2015-10-30030 October 2015 Regarding HPCI Motor Gear Unit Would Not Return to Full Flow During Testing 05000237/LER-2015-003, Regarding Turbine Building to Reactor Building Interlock Doors Open Simultaneously2015-10-30030 October 2015 Regarding Turbine Building to Reactor Building Interlock Doors Open Simultaneously 05000249/LER-2015-001, Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value2015-10-29029 October 2015 Regarding Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value 05000237/LER-2015-002, Regarding 2C ERV Failed to Actuate During Extent of Condition Testing2015-04-0303 April 2015 Regarding 2C ERV Failed to Actuate During Extent of Condition Testing 05000237/LER-2015-001, Regarding Unit 2 Scram Due to Feedwater Level Control Issues2015-03-0606 March 2015 Regarding Unit 2 Scram Due to Feedwater Level Control Issues 05000249/LER-2014-001, Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing2015-01-0505 January 2015 Regarding Electromatic Relief Valve Failing to Actuate During Surveillance Testing 05000237/LER-2014-003, Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer2014-06-0606 June 2014 Regarding Reactor Scram During Automatic Voltage Regulator Channel Transfer 05000237/LER-2014-002, Regarding Reactor Scram Due to Main Power Transformer Failure2014-06-0606 June 2014 Regarding Reactor Scram Due to Main Power Transformer Failure 05000237/LER-2014-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-05-27027 May 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-009, Regarding HPCI Failed to Achieve Rated Flow Due to Failure of Stop Valve to Open2014-01-29029 January 2014 Regarding HPCI Failed to Achieve Rated Flow Due to Failure of Stop Valve to Open 05000249/LER-2013-001, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-27027 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-008, Regarding Leak Identified on a Relief Valve During Pressure Test Resulting in a Degraded Principal Safety Barrier2014-01-24024 January 2014 Regarding Leak Identified on a Relief Valve During Pressure Test Resulting in a Degraded Principal Safety Barrier 05000237/LER-2013-007, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-15015 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-005, Regarding Primary Containment Inboard and Outboard Feed Water Isolation Valves Exceed Leakage Limits2014-01-13013 January 2014 Regarding Primary Containment Inboard and Outboard Feed Water Isolation Valves Exceed Leakage Limits 05000237/LER-2013-006, Dressden Nuclear Power Station, Unit 2, Regarding LPCI Swing Bus Auto Transfer Did Not Transfer as Expected2014-01-13013 January 2014 Dressden Nuclear Power Station, Unit 2, Regarding LPCI Swing Bus Auto Transfer Did Not Transfer as Expected 05000237/LER-2013-004, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2014-01-0606 January 2014 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-003, Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2013-11-22022 November 2013 Regarding Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2013-002, Movement of Control Rods with Control Rod Block Monitor Inoperable2013-09-27027 September 2013 Movement of Control Rods with Control Rod Block Monitor Inoperable 05000237/LER-2013-001, Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously2013-08-23023 August 2013 Secondary Containment Inoperable Due to Two Interlock Doors Being Open Simultaneously 05000237/LER-2011-005-01, For Dresden, Unit 2, Regarding Standby Liquid Control Explosive Valve Failure2012-12-18018 December 2012 For Dresden, Unit 2, Regarding Standby Liquid Control Explosive Valve Failure 05000237/LER-2012-001, Regarding One Division of APRM Neutron Flux-High Channels Inoperable as a Result of Power Maneuver2012-12-0606 December 2012 Regarding One Division of APRM Neutron Flux-High Channels Inoperable as a Result of Power Maneuver 05000249/LER-2012-001, Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure2012-09-10010 September 2012 Regarding Unexpected Isolation of the Isolation Condenser Due to Test Switch Failure 05000237/LER-2012-002, Regarding Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities2012-07-23023 July 2012 Regarding Inlet Steam Drain Pot Drain Line Leaks Result in HPCI Inoperabilities 05000249/LER-2010-002-01, For Dresden, Unit 3, Regarding MSIV Leakage Exceeds Technical Specifications Allowable Limits2011-12-16016 December 2011 For Dresden, Unit 3, Regarding MSIV Leakage Exceeds Technical Specifications Allowable Limits 05000237/LER-2011-004, Personnel Error Results in Control Room Emergency Ventilation Air Conditioning System Inoperability2011-12-16016 December 2011 Personnel Error Results in Control Room Emergency Ventilation Air Conditioning System Inoperability 2024-01-19
[Table view] |
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- REGUlf\TORY on&KU tUl con Morris; Illinois 60450 Telephone 815/942-2920
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James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Com_mission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report #78-035/0lT-O, Docket #050-237 is hereby submitted to your office in accordance with.Dresden Nuclear Power Station Technical Specification 6.6~B.l.(i), performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases: or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition, tep son Station Superintendent Dresden Nuclear Power Station BBS/deb Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC
..... 11*;0027 7 C.1 -
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 17-77)
CONTROL BLOCK: .____,__........__.___.__...._-:!6\..'.)
eI I LICENSEE EVENT REPORT Ir,'\ e (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI
~ 1*r I LI DI RI s I 2101 0 I 0 I - I 0 I 0 I 0 I 0 I 0 I~ I 0 I 0 IG)l 4 11 11 11 I 1 101 I 10 7 B 9 LICENSEE COD.E 14 15 LICENSE NUMBER 25 26 LICENSE TYPE :JO 57 CAT 5B CON'T
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.7 B 60 61 DOCKET NUMBER. 68 69 EVENT DATE i"- 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I . During pre-installation corrosion inspection of recently purchased spent fuel storage!
[ill] racks, cracks through weld metal in aluminum channel to base plate fillet welds were I
-~ found in 8 of !B racks. Eight other racks from same shipment were previously installfad
[TI[] before last ILDRS-3 refueling outage. The *s installed racks were not specifically
~ inspected for cracks but did pass similar pre-instaliatiOn inspection that found thesr
- [£]2] I cracks. Minimal safety significance evident since fuel was not stored in any racks . I
[Ill I known to have weld cracks. This event _is not repetitive.
7 B 9 BO SYSTEM CAUSE* CAUSE COMP. .VALVE CODE COL>E.-. SUB CODE COMPONENT CODE SUBCODE . SUBCOOE
[ill] LE.L~@. UJ@ L!@ Ix Ix Ix I xi xi xl8 UJ@) UJ@
7 B 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION
@ LERiRO CVENT YEAR REPORT NUMBER I7 I8 I l=:J REPORT NO.
Io I 3 Is I ,,.,.., CODE I 01 11 TYPE L:!J l=1 NO.
l.QJ 21 22 23 24 26 27 28 29 JO 31 32 ACTION FUTURE EFFECT. SHUTDOWN (.;::;\ ATTACHMENT NPR0-4 PRIME.COMP. COMPONENT TAKEr~ ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :::.UB. SUPPLIER MANUFACTURER
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36 I o I o I o I o I W@ IJLJ(§ ll!J@ I cl o Is lo I 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
I Cause unknown. - all fuel removed from 8 installed racks in ILDRS-3. An investigation; is being conducted by G.E. to determine the cause of the weld cracks, formulate a repair program for the welds and an inspection program for the 8 installed racks and IITIJ
.[JJJ] I remaining welds on the 18 racks not installed. - Results of this investigation. will
~ I be submitted in a supplemental report upon receipt.
7 B 9 80 FACILITY METHOD OF A STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION ~
[QI] UJ@ I o I 9 I* 4 l@_I_N_A_ _ _~ LQJ@I..._N_o_t_1_*f_i_c_a_t_i_o_n_f_r~o_m_G_._E_.- - - - - - - -
B 9 10 12 n 44 45 46 80 ACTIVITY CONTENT . t::;\
RELEASED OF RELEASE . AMOUNT O.F ACTIVITY\~.V LOCATION OF RELEASE@
~8 LzJ@ 9 W@
10 I.....-=NA=----------
. 11 45 NA I 44 BO PERSONNEL EXPOSURES ~
NUMBER ~TYPE OESCRl?T'ON ~.
GI?]8. lo 9 Io lo 11lLJ@ 12 .
NA 1-3---~~---------------------------------~80.
PERSONNEL INJURIES . Q NUMBER OESCRIPTION~
~ B 9 oI 0*1 ol@'.":--.-,--*--'-.-*--=-*IA.._*--~---------------~---~
' 11 12 . . . so LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION *
@3 * .
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a 9 10
- NRC tJSF. ONLY ISSUE DC\ UESCRIPTION ~
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8 9 10 68 69 so.-;;.
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NAME OF PRE PARER _ _ _ _ J_._B_r_u_n....n.;;..e'-r___,*- - - - - - - - - - - - PHONE:_X_-_4_7_2_ _ _ _ _ _ _ __ a. .
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ATTACHMENT TO LICENSEE EVENT REPORT 78-035/0lT-0 COMMONWEALTH EDISON COMPANY (CWE)
DRESDEN UNIT-2 (ILDRS-2)
DOCKET 11050-237 During a G.E. pre-installation corrosion inspection of the spent fuel storage racks cracks, l" to l~" long through the weld metal in the aluminum*
chan:iel to base plate fillet welds, were found in 8 out of 18 racks. During D-3 outage~ 8 other racks have been installed that came from the same.
shipment as the above 18*racks mentioned. These 8 racks were not inspected by G.E. _specifically for cracks in welds but did *pass same type of inspection tha~ found cracks in 8 out of 18 pre-installed storage racks. The cracks found in the pre-installed racks pose no safety question at this time
- since there has been no fuel placed in the racks. This is the first time -:.racks have been found in any of the welds and thus should not be a repetitive occurrence .
. Upon finding*that 8 out of 18 pre-installed spent fuel storage racks had cracks in the welds, all f,uel was removed from the 8 racks now installed in the D-'-3 spent fuel pool 'therefore eliminating any chance of an accident with spent ~uel. An int.ensive study program is being performed by G.E.
on the cause of the cracks, repair program for the welds, inspection required for 8 racks currently installed in D-3 spent fuel pool and inspection for remaining.welds on the 18 racks not installed. A supplemental repo+t will be submitted detailing the results of the investigations by G.E.