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| {{#Wiki_filter: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 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 50-249/1977-7. This report is being submitted to your office in accordance with the bresden Nuc 1 ec;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 & Program Control Fil e/NRC APR 2 5 1977 | | {{#Wiki_filter:Commonwec9 |
| LICENSEE EVENT REPORT CONTROL BLOCK: Lj_** 1 L . , I . I c&sE PRINT ALL,REQUIRED INFORMATION) LICENSEE NAME *@El I I I LI DI RI s I 31 1 0*s 14 REPORT CATEGORY TYPE. 6 LICENSE NUMBER 15 25 REPORT SOURCE DOCKET NUMBER LICENSE . TYPE 41 1 p 11 11 I 26. . 3P EVENT DATE EVENT TYPE I o I 31 31 32 REPORT DATE @E]coN'.T I I I LJ L':J I 01 51 12 14 19 I I o I 3 I 2 I .2 I 7 I 7 I 1014121117171 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 7 8 9 lol3r I started,.but*the generator field failed to flash. The generator field flashed 7 . 8 9 lol41'1 during a secon.d start-up of the diesel. The diesel was started a third time, 7 . 8**9 IPl51 J . and again the field did not flash. The Unit-3 diesel generator was then shut 7 0*s lolsl I , down and dee 1 a red i noperab 1 e. A subsequent attempt to start the Unit-2/3 diesel 1 *0 s .SYSTEM CAUSE PRIME i nued) * COMPONENT CoMPONENT CODE . CODE COMPONENT CODE SUPPUER MANUFACTURER VDLATION [§E] IE IE I* w I El NI GI II NI El I WI 019 17 I * l!U 7 8 9 10 11 12 . : .* .*. 17 43 44 47 48 CAUSE DESCRIPTION . < I The failure was 'caused by an intermittent capacitor short in the generator field 7 8 9 flashing circuitry. The defective capaci_tor' was replaced, and the Unit-3 diesel 1* 0* 9 IT1§J I generator was satisfact_orily tested and returned to service. 7 8 9 FACIUTY STATUS Em L:J 7.; 8 .9 FORM OF ACTIVITY 'll. POWER I 01 913 10 CONTENT I 12 13 OTHER STATUS NA {continued) DISCOVERY DESCRIPTION I 80 I 80 I 80 I 80 I 80 k 80 l eo I 80 80 rn RELEASED OF RELEASE AMOUNT OF ACTIVITY w LlJ : I . NA 11 LOCATION OF RELEASE .__------'---------.....JI ., 80 7 8 9 10 PERSONNEL EXPOSURES . NUMBER TYPE. * DESCRIPTION II§] J 0 I 0 I 0 I .. .__ __ NA __________ _;. ___ _;.__;. ______ __, 7 8 9 . 11* . 12 13 80 PERS'ONNEL INJURIES . NUMBER 'DESCRIPTION l1E1 I 0 I 0 I 0 I ':--__ N_A ___________ __ ""'=" 7 8 9* 11 12 80 * * OFFSITE .. CONSEQUENCES NA 7 8 9 LOSS OR DAMAGE . TO FACILITY TYPE [!El DESCRIPTION NA 7 8 9 10 PUBLICITY NA ADDITIONAL FACTORS *Elfil I NA . 7 8 9 80 80 80 7 B. 9 &O J. B. Martin Ext. 265 ....... -----------------------PHONE:_.-... _ _.._ __ _...;_ GPO 881*087 | | Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois |
| -. * EVENT DESCR1PTION (continued) -generator was-;:::unsuccessful (R. 0. report no. This event was of little safety significance, since the redundant Unit-2/3 di ese 1 .generator was demonstrated to be operab 1 e short 1 y thereafter (within minutes), and off-site power remained available this interval. ihe -Unit-2 diesel generator experienced a similar field flashing failure in April, 1975. (50-249/1977-7) CAUSE DESCRIPTION (continued) As a long-term action, the diesel generator maintenance procedure will be revised to include a check of the generator field flashing capacitors. The failed capacitot is an 8-microfarad, 150-volt electrolytic unit manufactured by Aerovox: ; *--l : *4: -* ...... : ., ' ... , -. -... ,'J.,J ::::1 | | 60450 Telephone |
| | 815/942-2920 |
| | BBS Ltr. # 333 April 20, Mr. James G. Keppler, |
| | Regional |
| | 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 |
| | 50-249/1977-7. |
| | This report is being submitted |
| | to your office in accordance |
| | with the bresden Nuc 1 ec;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 |
| | & Program Control Fil e/NRC APR 2 5 1977 |
| | LICENSEE |
| | EVENT REPORT CONTROL BLOCK: Lj_** 1 L . , I . I c&sE PRINT ALL,REQUIRED |
| | INFORMATION) |
| | LICENSEE |
| | NAME *@El I I I LI DI RI s I 31 1 0*s 14 REPORT CATEGORY |
| | TYPE. 6 LICENSE NUMBER |
| | 15 25 REPORT SOURCE DOCKET NUMBER LICENSE . TYPE 41 1 p 11 11 I 26. . 3P EVENT DATE EVENT TYPE I o I 31 31 32 REPORT DATE @E]coN'.T |
| | I I I LJ L':J I 01 51 |
| | 12 14 19 I I o I 3 I 2 I .2 I 7 I 7 I 1014121117171 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 7 8 9 lol3r I started,.but*the |
| | generator |
| | field failed to flash. The generator |
| | field flashed 7 . 8 9 lol41'1 during a secon.d start-up |
| | of the diesel. The diesel was started a third time, 7 . 8**9 IPl51 J . and again the field did not flash. The Unit-3 diesel generator |
| | was then shut 7 0*s lolsl I , down and dee 1 a red i noperab 1 e. A subsequent |
| | attempt to start the Unit-2/3 |
| | diesel 1 *0 s .SYSTEM CAUSE PRIME |
| | i nued) * COMPONENT |
| | CoMPONENT |
| | CODE . CODE COMPONENT |
| | CODE SUPPUER MANUFACTURER |
| | VDLATION |
| | [§E] IE IE I* w I El NI GI II NI El I WI 019 17 I * l!U 7 8 9 10 11 12 . : .* .*. 17 43 44 47 48 CAUSE DESCRIPTION |
| | . < I The failure was 'caused by an intermittent |
| | capacitor |
| | short in the generator |
| | field 7 8 9 flashing |
| | circuitry. |
| | The defective |
| | capaci_tor' |
| | was replaced, |
| | and the Unit-3 diesel 1* 0* 9 IT1§J I generator |
| | was satisfact_orily |
| | tested and returned |
| | to service. 7 8 9 FACIUTY STATUS Em L:J 7.; 8 .9 FORM OF ACTIVITY |
| | 'll. POWER I 01 913 10 CONTENT I 12 13 OTHER STATUS NA {continued) |
| | DISCOVERY |
| | DESCRIPTION |
| | I 80 I 80 I 80 I 80 I 80 k 80 l eo I 80 80 rn RELEASED |
| | OF RELEASE AMOUNT OF ACTIVITY |
| | w LlJ : I . NA 11 LOCATION |
| | OF RELEASE .__------'---------.....JI |
| | ., 80 7 8 9 10 PERSONNEL |
| | EXPOSURES |
| | . NUMBER TYPE. * DESCRIPTION |
| | II§] J 0 I 0 I 0 I .. .__ __ NA __________ |
| | _;. ___ _;.__;. ______ __, 7 8 9 . 11* . 12 13 80 PERS'ONNEL |
| | INJURIES |
| | . NUMBER 'DESCRIPTION |
| | l1E1 I 0 I 0 I 0 I ':--__ N_A ___________ |
| | __ ""'=" 7 8 9* 11 12 80 * * OFFSITE .. CONSEQUENCES NA 7 8 9 LOSS OR DAMAGE . TO FACILITY |
| | TYPE [!El DESCRIPTION |
| | NA 7 8 9 10 PUBLICITY |
| | NA ADDITIONAL |
| | FACTORS *Elfil I NA . 7 8 9 80 80 80 |
| | 7 B. 9 &O J. B. Martin Ext. 265 |
| | ....... ----------------------- |
| | PHONE:_.-... |
| | _ _.._ __ _...;_ GPO 881*087 |
| | -. * EVENT DESCR1PTION |
| | (continued) |
| | -generator |
| | was-;:::unsuccessful |
| | (R. 0. report no. |
| | This event was of little safety significance, |
| | since the redundant |
| | Unit-2/3 |
| | di ese 1 .generator |
| | was demonstrated |
| | to be operab 1 e short 1 y thereafter |
| | (within minutes), |
| | and off-site |
| | power remained |
| | available |
| | this interval. |
| | ihe -Unit-2 diesel generator |
| | experienced |
| | a similar |
| | field flashing |
| | failure in April, 1975. (50-249/1977-7) |
| | CAUSE DESCRIPTION |
| | (continued) |
| | As a long-term |
| | action, the |
| | diesel generator |
| | maintenance |
| | procedure |
| | will be revised to include a check of the generator |
| | field flashing |
| | capacitors. |
| | The failed capacitot |
| | is an 8-microfarad, |
| | 150-volt |
| | electrolytic |
| | unit manufactured |
| | by Aerovox: |
| | ; *--l : *4: -* ...... : ., ' ... , -. -... ,'J.,J ::::1 |
| }} | | }} |
|
---|
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] |
See also: IR 05000249/2019077
Text
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
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
50-249/1977-7.
This report is being submitted
to your office in accordance
with the bresden Nuc 1 ec;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
& Program Control Fil e/NRC APR 2 5 1977
LICENSEE
EVENT REPORT CONTROL BLOCK: Lj_** 1 L . , I . I c&sE PRINT ALL,REQUIRED
INFORMATION)
LICENSEE
NAME *@El I I I LI DI RI s I 31 1 0*s 14 REPORT CATEGORY
TYPE. 6 LICENSE NUMBER
15 25 REPORT SOURCE DOCKET NUMBER LICENSE . TYPE 41 1 p 11 11 I 26. . 3P EVENT DATE EVENT TYPE I o I 31 31 32 REPORT DATE @E]coN'.T
I I I LJ L':J I 01 51
12 14 19 I I o I 3 I 2 I .2 I 7 I 7 I 1014121117171 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 7 8 9 lol3r I started,.but*the
generator
field failed to flash. The generator
field flashed 7 . 8 9 lol41'1 during a secon.d start-up
of the diesel. The diesel was started a third time, 7 . 8**9 IPl51 J . and again the field did not flash. The Unit-3 diesel generator
was then shut 7 0*s lolsl I , down and dee 1 a red i noperab 1 e. A subsequent
attempt to start the Unit-2/3
diesel 1 *0 s .SYSTEM CAUSE PRIME
i nued) * COMPONENT
CoMPONENT
CODE . CODE COMPONENT
CODE SUPPUER MANUFACTURER
VDLATION
[§E] IE IE I* w I El NI GI II NI El I WI 019 17 I * l!U 7 8 9 10 11 12 . : .* .*. 17 43 44 47 48 CAUSE DESCRIPTION
. < I The failure was 'caused by an intermittent
capacitor
short in the generator
field 7 8 9 flashing
circuitry.
The defective
capaci_tor'
was replaced,
and the Unit-3 diesel 1* 0* 9 IT1§J I generator
was satisfact_orily
tested and returned
to service. 7 8 9 FACIUTY STATUS Em L:J 7.; 8 .9 FORM OF ACTIVITY
'll. POWER I 01 913 10 CONTENT I 12 13 OTHER STATUS NA {continued)
DISCOVERY
DESCRIPTION
I 80 I 80 I 80 I 80 I 80 k 80 l eo I 80 80 rn RELEASED
OF RELEASE AMOUNT OF ACTIVITY
w LlJ : I . NA 11 LOCATION
OF RELEASE .__------'---------.....JI
., 80 7 8 9 10 PERSONNEL
EXPOSURES
. NUMBER TYPE. * DESCRIPTION
II§] J 0 I 0 I 0 I .. .__ __ NA __________
_;. ___ _;.__;. ______ __, 7 8 9 . 11* . 12 13 80 PERS'ONNEL
INJURIES
. NUMBER 'DESCRIPTION
l1E1 I 0 I 0 I 0 I ':--__ N_A ___________
__ ""'=" 7 8 9* 11 12 80 * * OFFSITE .. CONSEQUENCES NA 7 8 9 LOSS OR DAMAGE . TO FACILITY
TYPE [!El DESCRIPTION
NA 7 8 9 10 PUBLICITY
NA ADDITIONAL
FACTORS *Elfil I NA . 7 8 9 80 80 80
7 B. 9 &O J. B. Martin Ext. 265
....... -----------------------
PHONE:_.-...
_ _.._ __ _...;_ GPO 881*087
-. * EVENT DESCR1PTION
(continued)
-generator
was-;:::unsuccessful
(R. 0. report no.
This event was of little safety significance,
since the redundant
Unit-2/3
di ese 1 .generator
was demonstrated
to be operab 1 e short 1 y thereafter
(within minutes),
and off-site
power remained
available
this interval.
ihe -Unit-2 diesel generator
experienced
a similar
field flashing
failure in April, 1975. (50-249/1977-7)
CAUSE DESCRIPTION
(continued)
As a long-term
action, the
diesel generator
maintenance
procedure
will be revised to include a check of the generator
field flashing
capacitors.
The failed capacitot
is an 8-microfarad,
150-volt
electrolytic
unit manufactured
by Aerovox:
- *--l
- *4: -* ...... : ., ' ... , -. -... ,'J.,J ::::1