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Category:Letter
MONTHYEARIR 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 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 ML24128A2742024-06-14014 June 2024 Notice of Acceptance and Opportunity for Hearing - Letter 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 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 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 ML24179A2232024-02-12012 February 2024 ILT 23-1 (2024-301) SVP Letter - 24-007 ILT Exam Submittal IR 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 2024-08-09
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Text
CommonvAlth Edison
'oc' 0 Dresden Nucll!l'Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. #414-76 May 27' 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 Occurre:mce number 50-249/ 1976-9.
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6.6.B.
~lY}~
~: B. Stephenson .
V ~tation Superintendent*
Dresden Nuclear Powet~Station BBS:smp Enclosure*
- cc: Director of Inspection & Enforcement Director of Management Information & Program Co.ntrol File/NRC 5804 ~ ....
e LICENpEE EVENT REP OR-
-* CONTROL BLOCK:L I I I I I I 1..__.___._~.__.......__.___,6
[PLEASE PRINT ALL REQUIRED INFORMATION)
LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE
-@El II ILI Pl R.JS~1=31. 10101-10101010101-10101 k41tltl/1(1 10131 7 8 9 . 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE. SOURCE DOCKET NUMBER EVENT DATE REPORT DATE
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- I I LlJ lhJ 101510t~IOl~l41ql 101s1** lo 17lt, I 10 IS 12- IJt 17 ll> I 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION (filg) I J)VgtNG- A StH~VE.1UAl'JC- ltST OIJ 1"HE coRE s-P~AY VALVf:'>>, VA.L..V MD 3-1406--'J.58 IR1PPc:DI 7 8 9 . . . . ,-, ~ . . 80 lol31 1'0011~11L. Q\)~~~V--A~ -IT \Jfis-Q'f-;:;;JG-CLPstp J?~i '-f1~E SWi,;;*Tl~t.~HE 1\1E:li;;,;AL-OV~-LDA~_- wee?:-.1mtr1oiAT1:iyl 7 8 9 - ..,_, - - 80 lol41 -rw1c AT~ Tl~G" . ALV~ )'Y)O"n>R, C.l.IR tJT5 7 8 9 80 lol51 lwER~ Y\')'EAsu12.ED ou12.11..1G- oei;Rr-mo.!V, Af\IO m-c ToR.Qv¢: swcrcH .S-E:-r:-1.v<.,,> itJER-4: C..H-cc.Kro. NO -I 7 8 9 80 lfilID (J,~nJ"su7n. . CH"ARACTt--i?.1 Ti ~ L'PCI AND IHC R£iNl'Jt>AIJI 7 8 9 PRIME (SE'C: A1'!l'lc. i+D ':)l+tET', 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION
, @El IS IF I ~ IC I K ITIB IR I Kl lAJ IG IO I g Io I lt{J 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
- lo Isl I11~ i::: WI 1-vr: moToR... TR.1 PP<=:D rAs- *p: kE.s u L-r oi=:- AN IJ\Jf\DG::Q\JAT£ Of< UN0'Q.SI ZG[) OV~ HOl"'T'CR. I 7 8 9 80
@El h-4~ E°XISliNG- 0V£BLOJ\0 I 7 8 9 IT@ Vll.1....ve: i'YloToR. 's J./i.fO V A(. HOW 7 8 9 FACILITY METHOD OF STATUS % 'P0\11/ER OTHER STATUS DISCOVERY OISCOYERY DESCRIPTION EEJ8 L~J I0.171~ I -..._I_ _ /IJA_ ____. lg_] NA 7 9 FORM OF 10 12 13 44 45 46 80 ACTIVITY CONTENT rn.
7 8 RELEASED 9
lbJ OF RELEASE
~
10
.._I _
11 AMOUNT OF ACTIVITY
_ ....:....;N_,,;,.A_ ___,
44 45 Nii LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION DE 1010101 -~ --~_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___
7 8 9 11 12 13 80 PERS'ONNEL INJURIES NUMBER DESCRIPTION EE89101010111 7.
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12_ 80 OFFSITE CONSEQUENCES
~ 'A
- 7. 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Efil8 9lbJ 7 10 80 PUBLICITY E08 9 7
Nit 80 ADDITIONAL FACTORS
~ NA 7 8 9 80 IT1fil '
7 89~~~~~~~~~~~~.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~8~0 NAME: £. /,., * . ~t-(1<:.t NG-CR.., PHONE: Ex/~ .?. ~ S""
GPO 881
EVENT DESCRi"P.TION (continued) core spray loop would have been available and operable had the valve tripped in the closed position following a LOCA. Thermal overload tripping occurs on this valve only after multiple actuations .
. Additionally, valve 1402-25B is a nomally closed valve whi'ch opens. for
- system operation. Although this is the first failure of this type on valve 1402-25B, other similar valves have experienced thermal overload trips at Dresden.
(50-249/1976-9)
CAUSE DESCRIPTION (continued) 480 V AC .system. With the resultant. increase in current, frequent operation of the valve causes . . the overload *heater to trip.
- 0. . ..*, : . . . '... .
A modific~'tion has *been. initiated to. replace the present* overload heaters of
- this tyP.e with ).arger:. GE model.IJCRl?~K7 ..91A. overload heaters. Installation of the~'e*~hlgher'-'cap'ii.tity:,; unfts ;~whi~h,. are"pre~en:py *ori '*ai~er) *should prevent future ~thei;tiial. ,overload~ failures;- on: siriiilarlj°* eq_uill-e.4 iµotor-6perated valves.
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