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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
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Commonwe4 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920
~gulatory Docket File BBS Ltr. #76-815 November 22, 1976 Mr. James G. Keppler, Regional Dlrector Djrectorate of Regulatory Operations - Region 111 U. S. Nuclear Regulatory Commission 799 Roosev~lt Road Glen Ellyn, 11 l inois 60137 Enclosed please find Reportable OccurreMce report number 50-249/1976-30.
This report is being submitted to your office in accordance with the Dresden Nuclear Power Station Technical Specifications, Section 6~6.B. *
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. Ste enson Station Superintendent
.Dresden Nuclear P6wer Siatfon BBS :jo Enclosure cc: Director of Inspection & Enforcement Directcir of Management Information & Program C6ntrol Fi 1e/NRC 12111
_,,
- LICENSEE EVENT REPORT e CONTROL BLO~K: I I~
1 I I I I 6
[PLEASE PRINT ALL REQUIRED INFORMATION)
LICENSEE LICENSE EVENT
__ NAME LICENSE NUMBER TYPE TYPE
--~~II IL ID IRIS 13 I 10101-IOIOIOI 010!-IOIQJ l-41 I I I I I I I I 10131 7 8 9 . 14 . 15 25 26 30 31 32 REPORT REFORT CATEGORY TYPE. SOURCE DOCKET NUMBER EVENT OA TE REPORT DATE
- @E]_coN'T I I I l!J L6J IOl5IOl~lbl21~191 II IOl~l~l7lbl l/lflf IWl7101
- 7. 8 57 58 59 60 61 68 . 69 74 75 BU EVENT DESCRIPTION
[Qlli) I DVRJAJG-- REFUE/..JN<;. OVTl-IG-£ }..J)C:ff L /...Elll<-RAT£ 7-Gst/)JG-., THE. Tl P PURGE .J 7 8 9 . . 80
@El I CHECK VALVE EXHIBITED A LEAK.AG-£ 'RATE OE I ~g- SCFH (T£CH SP£C Ltm1T: 19.3~11 7 8 9 . . 80 lol41 I SC£H). TH£ VALY£ WBS REMOVE:D FRom "TH£ SYsTE.M AND CLEANED WITH I 7 8 9
~: lcomPR£SSE]) litR .. FOLLDWJNG- R£1NSTAJ..J.,,flTJON OE rkt=. VA.l..VE, TESTING: YIELDED l
' 7 8 9 . .
.{filfil WELL E: l.J I ERfrt1SS1 f:. LlfYJ T THIS 15 TE FtRS 1 0 9 PHJMe (SEE ltTTflCH£.1) SNcE.T 00 SYSTEM CAUSE COMPONENT. COMPONENT CODE . CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION
~ II IF I l&J Iv I A IL Iv I£ Ix I lfil IX 1't I q I'! I LYJ 7 8 9 10 11 12 . 17 43 44 47 48 CAUSE DESCRIPTION (oj0j I TH£ VALY£ l..EAkAGE WAS APPARENTJ..Y CAUS£D BY PIRT ON TIIE BALl OB.. Ti-uzJ.
7 8 9 . . ' . . . : 80 7
lo191.8 9lscAl/NG--
ABEA. AS 5TATEJ) ABOVE, THE VALV£ wes CLEANED WITH CQfYIPRs.<"££D
'. . . 80 I
~ I AIR} w /TH SATISFACTORY. RE5:.Ul-T5.. PUF?ING- R£f\GTOR OPERATION, THE TI p . ' I METHOD o~
- 7. 8 9 FACILITY (SE.£ l!TTAGHED <;;ffE"ET) eo .
STATUS 'lli POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION fil] WJ IO IO lo I I NA lliJ _I___--'-M-~_-.*_ _ _ _ _ _ _ J 7 8 9 10 12 13 . 44 45 . 46 80
.FORM OF ACTIVITY *. CONTENT 7
rn 8 RELEASED
-lb.I 9
OF RELEASE LbJ I....._
10 11 AMOUNT OF ACTIVITY
__;M_l'l_ _ __.
44 AJA
. LOCATION OF* RELEASE 45 80 j
PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION (fill0* Io 1 9
._____.;.::.M:..:...:~--_..;..,;----------------~----~
13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION VE 1010101 7 .. 8 .9 11 12 Nit 80 O.FFSITE CONSEQUENCES
.[ill] ft 7 8 9 . BO LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION E@.lb.J M 7 8 9 . 10 80 PUBLICITY
(£0 7 B 9 80 ADDITIONAL FACTORS
~8 7 9 80
[iliJ 7 89 BC NAME: £[)WARD .l. [;ECK!NG"£"R PHONE: £ XT, d..(, 5
/
EVENT DESCRIPTION (Continued) time this valve has been local leak-rate tested since unit operations began.
(50-249/1976-30)
CAUSE DESCRIPTION (Continued) purge line is 'connected to the nitrogen makeup system, which is maintained at approximately 100 PSIG. Consequently, it is considered extremely improbable that any through-leakage would otcur, even with drywell pressure at the design limit of 48 PSIG. The safety significance of this event is further minim1zed by the physical size of the*purge 1 ine (1/4 - inch). To ensure the timely identification of a recurring problem, surveillance testing of the Tl.P* purge
~heck valves has been added to the refueling outage LLRT procedures for both Units 2 and 3. The valve is a 1/4 - inch ball check valve, model C400-10S,
- manufactured by Manetrol. . .
-~ ... . ::: ... . . ~