|
---|
Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 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 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR 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 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 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 ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[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] |
Text
. .,fommori'4th Edison .
.:;;.cOresden Nuclear .Power Station.
N*R.R. #1 0 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 Specifications~ Section 6.6.B.
ens on Superintendent.
Dres"den Nuclear Power Station BBS:jo
cc:. Director of Inspection &.Enforcement Director of Management Information & Prog_ram Control .
File/NRC
. ' .. ~ : .
.REGULATORY.DOCKET FILE COPV
t
-- -_ LICENSEE EVENT REPORT -
.* : :~)"'... CONTRO~'.:BLOC1<'\
. ' 1.,. I I I J. . .. 'LEASE PRINT ALL REQUIRED INFORMATION)
'I>* _ , UcENSEE . < -- LICENSE EVENT
- NAME ' __ '_LICENSE NUMBER* TYPE - TYPE- -
@E] IIILl.Pl'RISl3 I 15 10101~10101010101-10101 IJ/*11It11111 101 f I
-- 7 -8 9 - : - ,;; *14 - - .,, - '25 -- - 26_ -- .. 30 .31 - 32 REPORT REPORT CATEGORY TYPE - SOURCE DOCKET NUMBER - EVENT DATE - REPORT DATE I I I tCJ IOl5l017IOl~l~f,I Io Ic:t I / I'6 17 I C74I _I75::-;-- 0 Iq 131 o -17 I lz.J 59<< . - lbJ
- :@E]coN'T 1 -_0 57 58 60 61 68 69 _-- 80 .
___ EVENT DESCRIPTiON 10'21.I AT 1'1l.5 -110URS ON t:tjt'lj7b 1 1)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 7 8 9 lc.o~DtNG- TO SEC-T10N 3.7. A. 5. 'B OF" Tl-4£ T£CHNIGAL. .S-PEC1F1c.11.rro/IJS ])Ry-
- _ _- _ _, BO I
____ . 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 (Sfi~ mt!Vni:f) .SHe::r)SD -
SYSTEM CAUSE COMPONENT COMPONENT
- . CODE . CODE COMPONENT CODE . SUFPUEtl - MANUFACTUF\ER - VIOlATXlN
- *~. [§0 ISIAI
-. - 7 8 9 *10 -- -
LE.J 11 IZ.IZlZIZIZIZI 12 - 17 -
-l£j 43 44 IZt91'1.dqJ _ lYJ 47 : - 48
-_ - ~ALISE DESCRiP,Tl0N _ _ _ _ _ _ __ _ __ _ _ _ _ _ _
~~I 1w ORDER io sltirsFy fYJ1N1muWJ, SY.sritM J...iYAD 'R.£QUtR£r1rc-N{S. UN1T~3 I.-
1 8 9 - - - -- - - - - -__ -- '-.*. - . - - - - - -. - y - - 80 -
. lol9Ll'w1ts *wor-*** SHUT' TJOWJJ WITHIN 14./-£:0..if,~ HOUR'- P.f1<10D-suBs-~Qui:NT To J)RYWEl..L J: -
. 7 . 8 9 - - -- - - - - .* - - 80 -
-.. /.[!:@*l*UE~.aNERTl.N.G-~ . SPtf"E'TY,.l.~Pl-ICA.TlotJS. ~,,WE;R£,.-}';J.04:::,ffiORE:E;$f.G:N;f:E:JGAN'T~::.m.:HAN.~~-JF:,... J-
.>-. --. ',:'<~.;
..-,Q- . 9. * -.-. FACILITY
- - . . - . - <METH*O--D-OF- - - -- (Sef; A-rtAC.!t£D*SHcutf) BO_*
-" *. - .. - ._ STATUS "' POWER OTHER STATUS 'DISCOVER';: - - DISCOVERY DESCRIPT:ON
[ill] (QJ Io 17 I 3 I I Nit I lAJ -1.._ _ __._M. . .fl...__. . . __ -_ -~..----.....-11 1 e s
-FORM- OF 10 12 13 44 45* 46 80
.' . *-:* . . ACTIVITY -- cmlTENT - -
__ :l:l -Rilz.sr~-: OF izf-~Er* _ _AMOUNT °JJ~CTIVITY ,, . ,
1 __ 1 -NALOCATION OF RELEASE 1-1-----~._,...,.,,,;::,...._:- - 4 4 -- *** 4~5_..,......---.--...........,..-....,....,.... . . . . ____,_.;.,,.--___---'001
- 11 1 -- a * ,~ --** 10 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 es 11 12 . . ": 00
_OFFSJTE CONSEQUENCES Elfil -Al11 - 80 -
. 7 - 89 LOSS 'O_R DAMAGE TO FACILITY
- DESCRIPTION Efil *IZ.J -.10 -
1 0* s -
NI/
80
- ./-
.PUBLiciTY (ill] NA 7 8 9 80 ADDITIONAL FACTORS
fl.~. . ~,
. * .. ' :~
EVENT DESCRIPT!ON (Continued) 2030 hour0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br />s~ 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% for.~ 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*..