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Category:Letter
MONTHYEARML24249A1362024-09-0404 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 IR 05000237/20230052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2024005) 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 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230112024-08-0707 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20200012024-08-0606 August 2024 Reissue - Dresden Nuclear Power Station, Units 2 and 3 - Integrated Inspection Report 05000237/2020001 and 05000249/2020001 ML24184A1712024-08-0202 August 2024 SLRA Schedule Letter RS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information ML24136A1322024-07-30030 July 2024 Transmittal Letter for Renewed License ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24193A0882024-07-24024 July 2024 Request for Withholding Information from Public Disclosure for Dresden Nuclear Power Station, Unit 1 Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations (Docket 50-10) ML24204A1862024-07-24024 July 2024 – Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2; TSTF-591, Revision 0; and 10 CFR 50.69 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 ML24138A0572024-06-26026 June 2024 – Issuance of Amendment Nos. 285 and 278 Application to Adopt TSTF-564, “Safety Limit Mcpr” ML24138A1812024-06-18018 June 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24156A2332024-06-11011 June 2024 Letter Supplemental Information for Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel RS-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24158A0012024-05-22022 May 2024 License Amendment Request to Adopt TSTF-564 (EPID L-2023-LLA-0120) Illinois State Concurrence ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24135A0722024-05-10010 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report ML24129A1352024-05-0808 May 2024 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-59 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 ML24092A3412024-05-0101 May 2024 SLRA - Receipt and Availability - Letter ML24127A0982024-04-30030 April 2024 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 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 ML24120A2032024-04-29029 April 2024 Operator Licensing Exam Approval - Dresden Nuclear Power Station, May 2024 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 ML24108A0082024-04-17017 April 2024 Application for Renewed Operating License RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. ML24083A0022024-03-22022 March 2024 IEMA-OHS Comment Dresden HI-STORM Exemption EA & Fonsi SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24061A1702024-03-0101 March 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000237/20230062024-02-28028 February 2024 Annual Assessment Letter for Dresden Nuclear Station, Units 2 and 3 (Report 05000237/2023006; 05000249/2023006) RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS 2024-09-04
[Table view] Category:Licensee 30-Day Written Event Report
MONTHYEARRS-11-124, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE142011-07-28028 July 2011 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14 SVPLTR 09-0044, Day Response on Inadvertent Control Rod Withdrawal2009-09-21021 September 2009 Day Response on Inadvertent Control Rod Withdrawal SVPLTR 09-0027, Written Follow Up Report on Release of Radionuclide2009-07-0606 July 2009 Written Follow Up Report on Release of Radionuclide RS-08-073, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima22008-05-23023 May 2008 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type SVEA-96 Optima2 ML0216407762002-06-0707 June 2002 Offsite Dose Calculation Manual (OCDM) Required Action Not Met During Units 2/3 Main Chimney Particulate, Iodine, and Noble Gas Sampling System Inoperability ML17252A3201977-11-23023 November 1977 LER 77-047/03L-0 for Dresden Unit 3 Regarding During Normal Unit 3 Operation, Surveillance Program Review Revealed Violation of T.S.1.0.CC.b Maximum Combined Interval Time by 3.5 Days for HPCI Monthly Valve and Pump Operability ML17252A2881977-05-0303 May 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-8 ML17252A2911977-04-22022 April 1977 License Event Report - Rod Withdrawal at Approx. 44% Power, Discovered Rod Block Monitor Channels 7 and 8 Automatically Bypassed ML17252A2901977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-10 ML17252A2711977-04-21021 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-9 ML17252A2721977-04-20020 April 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-7 ML17252A2751977-03-23023 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2821977-03-0202 March 1977 Transmittal of Reportable Occurrence Report No. 50-249/1977-4 ML17252A2581977-01-20020 January 1977 Transmittal of Reportable Occurrence Report No. 50-249/1976-36 ML17252A2701976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 IR 05000249/20190761976-12-0202 December 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-34 ML17252A2461976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-23 in Accordance with Technical Specifications, Section 6.6.B ML17252A2451976-11-0404 November 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-25 in Accordance with Technical Specifications, Section 6.6.B ML17252A2391976-10-22022 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-20 in Accordance with Technical Specifications, Section 6.6.B ML17252A2411976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-18 in Accordance with Technical Specifications, Section 6.6.B ML17252A2401976-10-21021 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-19 in Accordance with Technical Specifications, Section 6.6.B ML17252A2231976-10-12012 October 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-15 in Accordance with Technical Specifications, Section 6.6.B ML17252A2261976-09-30030 September 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-17 in Accordance with Technical Specifications, Section 6.6.B ML17252A2361976-07-0101 July 1976 Transmittal of Reportable Occurrence Report No. 50-249/1976-1 ML17252A2101976-02-0505 February 1976 Letter Submitting Reportable Occurrence Number 050-249/1976-3 in Accordance with Technical Specifications, Section 6.6.B IR 05000249/19750361975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1761975-09-0202 September 1975 Report of Abnormal Occurrence 50-249/75-36 Per Section 6.6.A of the Technical Specifications Re Reactor High Pressure Sensor Setpoint Drift ML17252A1711975-08-15015 August 1975 Report of A.O. Per Section 6.6.A of the Technical Specifications Isolation Condenser High Flow Sensor Setpoint Drift IR 05000249/19750321975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A1741975-07-31031 July 1975 Report of Abnormal Occurrence 50-249/75-32 Per Section 6.6.A of the Technical Specifications Failure of Restrainer Clamp Bolt Keeper on Jet Pumps ML17252A4471975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings IR 05000249/19750311975-07-0303 July 1975 Report of Abnormal Occurrence 50-249/75-31 for Dresden, Unit 3, Regarding Cracks in Control Rod Drive Collet Housings ML17252A7861975-03-27027 March 1975 Report of Abnormal Occurrence Per Section 6.6.a of the Technical Specification - Exceeding Set-point on Main Stream Line Hi Hi Rad ML17252A8271975-02-14014 February 1975 Report of Abnormal Occurrence Per Section 6.6.A of the Technical Specification - Reactor Feed Pump 3C Pump Casting Vent Line Weld Leak ML17252A8361975-01-14014 January 1975 Report of 4 Inch Recirculation Bypass Line Inspection 2011-07-28
[Table view] |
See also: IR 05000249/2019076
Text
. ' .. : . .. ,fommori'4th Edison . . :;;.cOresden Nuclear .Power Station. N*R.R.0#1 . ' .* Morris, Illinois 60450 Telephone 815/942-2920 *.*.* BBS Ltr. '#76-702 September 30, 1976* Mr. James G .. Keppler, Regional Director Directorate of Regulatory Operations -Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road * * Glen Ellyn, Illinois 60137 Enclosed please find Reportable Occurrence*report number 50-249/1976-17. *This report is being'submitted to your office in. accordance with the Dresden .Nuclear Power Station Technical Section 6.6.B. BBS:jo ens on Superintendent. Dres"den Nuclear Power Station * cc:. Director of Inspection & .Enforcement Director of Management Information & Prog_ram Control . File/NRC . .*.; . REGULATORY.DOCKET FILE COPV '
.-_ . t ---_ LICENSEE EVENT REPORT -. * : . ' 1.,. I I I J. . . . 'LEASE PRINT ALL REQUIRED INFORMATION) 'I>* _ , UcENSEE . < --LICENSE EVENT -NAME ' __ '_LICENSE NUMBER* TYPE -TYPE--@E] IIILl.Pl'RISl3 I IJ/*11It11111 101 f I --7 -8 9 -: -,;; *14 15 --.,, -'25 ---26_ --.. 30 .31 -32 REPORT REPORT CATEGORY TYPE -SOURCE DOCKET NUMBER -:@E]coN'T I I I tCJ lbJ -EVENT DATE -REPORT DATE Io I c:t I / I '6 17 I C I _ I 0 I q 131 o 17 I lz.J 69 _--74 75::-;---80 . 1 -_0 57 58 59<< .. --60 61 68 ___ EVENT DESCRIPTiON 10'21.I AT 1'1l.5 -110URS ON t:tjt'lj7b11)E-IN£RTrNG-OF" THE:"DR'IWEU-WAS-BEGUN IN I 7 8 9 -----------80 10'31 I AA/TtCIPffflOJV OF THE SCH£DULE:D IJNIT SHUTDOWN FOR 1<EFU£).JNG-. AC -I 7 -_ *-0 "9 -* . -* --_ 00 -lo141 TO SEC-T10N 3.7. A. 5. 'B OF" Tl-4£ T£CHNIGAL. .S-PEC1F1c.11.rro/IJS ])Ry-I 7 8 9 -_ _ -_ _, BO ____ . lol51 !WELL '])£*JN£"R::rtNG-fVIAY CfJ'i>1M£NG£ J.,4 HOURS PRIOR. TO A SHUTl>OWN. I *_ -7 8 *9 ---------80 I Tf-lc. 'D1<.'IW£LL 0'1.VGEN. C:O.iVC.£NTRATION E)(CEEDED .I./ Ofo AT APPROX.I MATELV f 7 -8 9 > -* * --PRIME mt!Vni:f) .SHe::r)SD -SYSTEM CAUSE COMPONENT COMPONENT --. CODE . CODE COMPONENT CODE . SUFPUEtl -MANUFACTUF\ER --VIOlATXlN -[§0 ISIAI LE.J IZ.IZlZIZIZIZI -l£j IZt91'1.dqJ _ lYJ -. -7 8 9 *10 ---11 12 -17 -43 44 47 : -48 -_ -DESCRiP,Tl0N _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ 1w ORDER io sltirsFy fYJ1N1muWJ, SY.sritM J...iYAD 'R.£QUtR£r1rc-N{S. I.-1 8 9 ----------__ --'-.*. -. -------. -y --80 --. lol9Ll'w1ts *wor-*** SHUT' TJOWJJ WITHIN HOUR'-To J)RYWEl .. L J: -. 7 . 8 9 --------.* --80 --.. .. .. ... J -.> .. . .-,Q .. 9. *: -. . -. -<METH*O--D-OF-----(Sef; A-rtAC.!t£D*SHcutf) BO_* -. --*-**** -.. -* -.-. FACILITY ----" *. -.. -._ STATUS "' POWER OTHER STATUS 'DISCOVER';: --DISCOVERY DESCRIPT:ON [ill] (QJ Io 17 I 3 I I Nit I lAJ -1.._ __ _._M ......... fl...__. __ -_ 1 e s 10 12 13 44 45* 46 -FORM-OF ACTIVITY --cmlTENT --_ _ 11:l:l -OF _ _AMOUNT ,, .. , 1 ___ 1 -NALOCATION OF RELEASE 1 1 --a * --** 10 1-1 --44 --*** .......... __ __,_.;.,,.--___ ---'00 * 80 .' . *-:* . . PERSONNEL.E)(POSURES * -* --NUMBER -TYPE 0El3CRIP.TION . (!21 :j'OlD.10 I .. .'l6J I NA -..... -I . .. . _ 1 _ e s 11 12 13 80 -. PERS.ONNEL INJURIES NUMBER DESCRIPTION ff8 IOI OIOll _-___ M_'A __ __ ____, _________ __,I 1 e s 11 12 00 *_,...... .. .. ": _ OFFSJTE CONSEQUENCES Elfil -Al 11 -. 7 -89 80 -LOSS 'O_R DAMAGE TO FACILITY * TYPE * DESCRIPTION Efil *IZ.J -. NI/ 1 0* s -10 -80 .PUBLiciTY . ,-_ -./-(ill] NA 7 8 9 80 ADDITIONAL FACTORS
.. . .. . * .. ' EVENT DESCRIPT!ON (Continued) 2030 At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on 9-19-76, the unit load drop was halted at the direction of the Chicago load dispatcher because of a system emergency. . .* Dr)'Weil. inerting *was begun at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />; *by 0600 ,-the dr-iwell oxygen con-* * centrad.on had d:ropped below 4%. A similar event occurred on Unit-2 in .J:une, 1975. (50-249/1976-17) CAUSE DESCRIPTION (Continued) the unit.had been actually shut down, since the drywell oxygen concentration exceeded 4% less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. As stated above, an acceptable drywell oxygen concentration was achieved by 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on 9-19-76. No further action was considered appropriate. *-* .* ** *:< b* ..