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Category:Letter
MONTHYEARML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, 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 ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman 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 ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief 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 ML24303A0272024-11-0101 November 2024 Letter to D. Rios, 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 IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24303A0172024-11-0101 November 2024 Letter to B. Peters, 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 ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, 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 ML24303A1172024-11-0101 November 2024 Letter to R. Yob, 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 ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman 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 ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, 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 ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair 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 ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief 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 ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, 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 ML24303A0552024-11-0101 November 2024 Letter to J. Keys, 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 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 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 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 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 ML24215A2912024-08-14014 August 2024 Request for Withholding Information from Public Disclosure Alternative Schedule to Complete Decommissioning Beyond 60-Years of Permanent Cessation of Operations 2024-09-06
[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
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Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. # 333 April 20, Mr. James G. Keppler, Regional Directo~
Directorate of Regulatory Operation - Region I I I U. s: "Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, 111 inois 60137 REGULATORY DDCKEI RLE COPY Enclosed please find Reportable Occurrence rep~rt nu~ber 50-249/1977-7.
This report is being submitted to your office in accordance with the bresden Nuc 1ec;ir Power Station Techn i ca,1 Specif i cat..i ons,. Section 6. 6. B..
BBS: skm
- Enclosure cc: Director of Inspection & Enforcement Director of Management lnf~rmation & Program Control Fil e/NRC APR 2 5 1977
LICENSEE EVENT REPORT CONTROL BLOCK:
LICENSEE Lj_**
1 L ., I . I 6
c&sE PRINT ALL,REQUIRED INFORMATION)
LICENSE EVENT NAME LICENSE NUMBER . TYPE TYPE
- @El I I I LI DI RI sI 31 1°1°1~1°1°1°1°1°1-1°1°1 ~ 41 1 p 11 11 I I o I 31 1 0*s 14 15 25 26. . 3P 31 32 REPORT REPORT CATEGORY TYPE. SOURCE DOCKET NUMBER EVENT DATE REPORT DATE
@E]coN'.T I I I LJ L':J I 01 51 01~10 12 14 19 I I o I 3 I 2 I .2 I 7 I 7 I 10141 2 1117171 7 .8 57. 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION ffilfil. I During testing of the Unit-3 d)esel generator following maintenance, the engine I lol 3 r I started,.but*the generator field failed to flash. The generator field flashed 7 8 9 80 7 . 8 9 I
80 lol41'1 during a secon.d start-up of the diesel. The diesel was started a third time, I 7 . 8**9 80 IPl51 J . and again the field did not flash. The Unit-3 diesel generator was then shut I 7 0*s 80 lolsl I , down and dee 1a red i noperab 1e. A subsequent attempt to start the Unit-2/3 diesel I
1 *0 s PRIME ~foont i nued)
.SYSTEM CAUSE COMPONENT CoMPONENT
[§E] IE IE I*
7 8 9 10 CODE w
. CODE 11 I El COMPONENT CODE NI GI 12 . : .* .*.
II NI El 17 SUPPUER
~
43 I
44 MANUFACTURER WI 019 17 I 47 VDLATION
- l!U 48 CAUSE DESCRIPTION . <
~ I The failure was 'caused by an intermittent capacitor short in the generator field k
7 8 9 The defective capaci_tor' was replaced, and the Unit-3 diesel 80
~ll flashing circuitry.
l IT1§J0* 9I 1*
generator was satisfact_orily tested and returned to service. eo I
7 8 9 80 FACIUTY {continued)
STATUS 'll. POWER OTHER STATUS DISCOVERY DESCRIPTION Em8 7.;
L:J I 01 913 I NA
.9 10 12 13 80 FORM OF ACTIVITY CONTENT AMOUNT OF ACTIVITY LOCATION OF RELEASE rn w RELEASED OF RELEASE 7 8 9 LlJ 10
- 11I . NA
.__------'---------.....JI 80 PERSONNEL EXPOSURES
. NUMBER TYPE.
- DESCRIPTION II§] J 0 I 0 I 0I .~ . .____NA_ _ _ _ _ _ _ _ _ __;.____;.__;._ _ _ _ _ ___,
7 8 9 . 11* . 12 13 80 PERS'ONNEL INJURIES
. NUMBER 'DESCRIPTION l1E1 I 0 I 0 I 0I ':--__N_A_ _ _ _ _ _ _ _ _ _ _.......:..---...~....-...__;..-__;..__;.._;._ _""'="
7 8 9* 11 12 80
~. NA 7 8 9 80 LOSS OR DAMAGE . TO FACILITY TYPE DESCRIPTION
[!El ~J NA 80 7 8 9 10 PUBLICITY NA ADDITIONAL FACTORS
. 7
~.L-~~--------------------~--'-~--------~~
7 B. 9 &O J. B. Martin Ext. 265
~E:= .......- - - - - - - - - - - - - - - - - - - - - - - PHONE:_.-..._ _..__ __...;_
GPO 881*087
EVENT DESCR1PTION (continued)
-generator was-;:::unsuccessful (R. 0. report no. 50~237/1977-11).
This event was of little safety significance, since the redundant Unit-2/3 di ese 1 .generator was demonstrated to be operab 1e short 1y thereafter (within
~5 minutes), and off-site power remained available durin~ this interval. ihe
- Unit-2 diesel generator experienced a similar gen~rator field flashing failure in April, 1975.
(50-249/1977-7)
CAUSE DESCRIPTION (continued)
As a long-term corr~ctive action, the annu~l diesel generator maintenance procedure will be revised to include a check of the generator field flashing circ~it capacitors. The failed capacitot is an 8-microfarad, 150-volt electrolytic unit manufactured by Aerovox:
- ~-
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- 1