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| {{#Wiki_filter:e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. /180-476 June 5, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operations -Region. III U.S. Nuclear Regulatory Commission* 799 Roosevelt Road Glen Ellyn, IL 60137 *** *Reportable Occurrence Report /180-17/031-0, Docket /1050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specific*ation 6.6.B.2.(b), conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation. BBS/nh Enclosure B. B. Station Superintendent Dresden Nuclear Power Station cc/ Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC LICENSEE EVENT REPORT I | | {{#Wiki_filter:e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. /180-476 June 5, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operations |
| * I 10 (PLEASE PRIN.T ORTYPAIL REQUIRED 1----.1....,_..1-__.....__._...._;;;._-'s\..!J .# ., CONTROL BLOCK: I I I L I D I R I s I 2 101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I -I 0 I 0 IQ)I 4 11 I 1 11 I 1 1 G)I I I.@ 9 LICENSEE. CODE . 14 15 | | -Region. III U.S. Nuclear Regulatory Commission* |
| * LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 . CON'T } o I 2 I j 0 13 I: l 0 14 I o I s 1 o I o I o I 2 13 11 101 o 1 s 1 1 1 2 I a 1 o I© 1 o I 6. 1 o I s I a I o 1 G) 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@ I *Following a uni"t scram, double* valve indication was observed on the HPCI-inboard isolation valve *. Upon trying to cycle. the valve, the valve failed to close (T.S.3.7.D.l). The health and safety of the public was not endangered because the ) 0 I sJ I HPCI steam line was isolable _ via the outboard isolation valve and other ECCS systems -0 Is I* were operable. 'J'his -is the first occurrence of* this type. l a ,,7 r I 1Cr'Tal". 9 80 SYSTEM CAUSE CAUSE COMP. CODE COiJE SUBCOOE COMPONENT.CODE SUB CODE ISIFI@ L!J@ w@ lvlAILlvlolPI@ L!J@) 9 . 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE AEPOP.T LEA/AO CV ENT YEAR. REPORT NO. CODE TYPE .REPORT I 8 I 0 I I l I 0 I l I 7 I I ........ , I 0 I 31 LEJ NUMBER . | | 799 Roosevelt Road Glen Ellyn, IL 60137 *** *Reportable Occurrence Report /180-17/031-0, Docket /1050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specific*ation 6.6.B.2.(b), |
| * _ 21 22 23 24 . 26 27 28 29 JO VALVE SUBCOOE w@ 20 1=J 31 REVISION. NO. ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPR0-4 TAKEN ACT.ION' ON PLANT METHOD . . HOURS' ''_SUBMITTED FORM :;us. PRIME COMP. SUPPLIER. COMPONENT MANUFACTURER ----**-* . L:J@ L.:J@ I 0 I 0 I 0 I I L!:J@ l:J<§ 33 . 34 ' . 35 . 35* . J-7 40. 41 . . 42 I L I 2 I 0 I 0 I@ . 44 . . . . 47 -.CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@ . 43 , , I 0 I r The failure was due to a packing leak on the valve' causing water to enter the valve ) 1 11 t .I _motor operator. The mo.tor dr:!,ed out and the valve was and. cycled 1-) 1 I 2 I successfully. N_o further action deemed necessary. ............... _,.. ..... _._ ................ ..,_...;.. ............... -.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.-....... _ 80* FACILITY 13Q\ STATUS % POWER OTHER STATUS re uu@ | | conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation. |
| * 1 0 I o_ I 0 l@).._I ..;,;,.N:..:.I 0* 9 10 12 n ACTIVITY CONTENT (.;;;'\ RELEASED OF RELEASE. AMOUNT OF ACTIVITY 7161 .. LU@ W(§ ..... 1 __ _,__ __ _.,....l 9 10 11 44 METHOD OF (:;':;\ DISCOVERY DISCOVERY OESCRIPTlON _ ......... ............................................................... ___.*I 45 46 80 LOCATION OF N/A 45. 80 ?ERSONNEL EXPOSURES * . *-Q_ NUMBER A TYPE . OESCRIPTlON m. ro 1 o 1 o ___ ...:..;N..:...;/ A:.:.... __ .....;_ ____ ._,.;.__ _____________ ----' 8 9 11 12 13 so PERSONNEL INJURIES* * (,;"";\ NUMBER OESCRIPTION6 :CW* I 0 I 0 I 0 __ * -*_N..;,._/ A ________________________ _,___, 8 9 11 12. | | BBS/nh Enclosure B. B. |
| * 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\ TYPE DESCRIPTION* ".:::::) 3TI: LU@ . 8-9 10 PUBLICITY (';;;\ 80. "' NR.C USE ONLY ISSUED/,;";;\ :IT£J;. l.::J'6 N /A 8. 9 IQ. K. Zirwas N A,'/i E CF PP. E P .t\ RE A 1,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l _ _.,.limiilll .. r'"*W;iiill'll 68 69 80*; 0 a. X-529}} | | Station Superintendent Dresden Nuclear Power Station cc/ Director of Inspection |
| | & Enforcement Director of Management Information |
| | & Program Control File/NRC LICENSEE EVENT REPORT I |
| | * I 10 (PLEASE PRIN.T ORTYPAIL REQUIRED 1----.1....,_..1-__.....__._...._;;;._-'s\..!J |
| | .# ., CONTROL BLOCK: I I I L I D I R I s I 2 101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I -I 0 I 0 IQ)I 4 11 I 1 11 I 1 1 G)I I I.@ 9 LICENSEE. |
| | CODE . 14 15 |
| | * LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 . CON'T } o I 2 I j 0 13 I: l 0 14 I o I s 1 o I o I o I 2 13 11 101 o 1 s 1 1 1 2 I a 1 o I© 1 o I 6. 1 o I s I a I o 1 G) 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@ |
| | I *Following a uni"t scram, double* valve indication was observed on the HPCI-inboard isolation valve *. Upon trying to cycle. the valve, the valve failed to close (T.S.3.7.D.l). |
| | The health and safety of the public was not endangered because the ) 0 I sJ I HPCI steam line was isolable |
| | _ via the outboard isolation valve and other ECCS systems -0 Is I* were operable. |
| | 'J'his -is the first occurrence of* this type. l a ,,7 r I 1Cr'Tal". 9 80 SYSTEM CAUSE CAUSE COMP. CODE COiJE SUBCOOE COMPONENT.CODE SUB CODE ISIFI@ L!J@ w@ lvlAILlvlolPI@ |
| | L!J@) 9 . 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE AEPOP.T LEA/AO CV ENT YEAR. REPORT NO. CODE TYPE .REPORT I 8 I 0 I I l I 0 I l I 7 I I ........ |
| | , I 0 I 31 LEJ NUMBER . |
| | * _ 21 22 23 24 . 26 27 28 29 JO VALVE SUBCOOE w@ 20 1=J 31 REVISION. |
| | NO. ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPR0-4 TAKEN ACT.ION' ON PLANT METHOD . . HOURS' ''_SUBMITTED FORM :;us. PRIME COMP. SUPPLIER. |
| | COMPONENT MANUFACTURER |
| | ----**-* . |
| | L:J@ L.:J@ I 0 I 0 I 0 I I L!:J@ l:J<§ 33 . 34 ' . 35 . 35* . J-7 40. 41 . . 42 I L I 2 I 0 I 0 I@ . 44 . . . . 47 -.CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@ |
| | . 43 , , I 0 I r The failure was due to a packing leak on the valve' causing water to enter the valve ) 1 11 t .I _motor operator. |
| | The mo.tor dr:!,ed out and the valve was and. cycled 1-) 1 I 2 I successfully. |
| | N_o further action deemed necessary. ............... |
| | _,.. ..... _._ ................ |
| | ..,_...;.. |
| | ............... |
| | -.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.- |
| | ....... _ 80* FACILITY 13Q\ STATUS % POWER OTHER STATUS re uu@ |
| | * 1 0 I o_ I 0 l@).._I ..;,;,.N:..:.I 0* 9 10 12 n ACTIVITY CONTENT (.;;;'\ RELEASED OF RELEASE. |
| | AMOUNT OF ACTIVITY 7161 .. LU@ W(§ ..... 1 |
| | __ _,__ __ _.,....l 9 10 11 44 METHOD OF (:;':;\ DISCOVERY DISCOVERY OESCRIPTlON _ |
| | ......... |
| | ............................................................... |
| | ___.*I 45 46 80 LOCATION OF N/A 45. 80 ?ERSONNEL EXPOSURES |
| | * . *-Q_ NUMBER A TYPE . OESCRIPTlON |
| | : m. ro 1 o 1 o |
| | ___ ...:..;N..:...;/ |
| | A:.:.... |
| | __ .....;_ ____ ._,.;.__ |
| | _____________ |
| | ----' 8 9 11 12 13 so PERSONNEL INJURIES* |
| | * (,;"";\ NUMBER OESCRIPTION6 |
| | :CW* I 0 I 0 I 0 |
| | __ * -*_N..;,._/ |
| | A ________________________ |
| | _,___, 8 9 11 12. |
| | * 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\ TYPE DESCRIPTION* |
| | ".:::::) |
| | 3TI: LU@ . 8-9 10 PUBLICITY |
| | (';;;\ 80. "' NR.C USE ONLY ISSUED/,;";;\ |
| | :IT£J;. l.::J'6 N /A |
| | : 8. 9 IQ. K. Zirwas N A,'/i E CF PP. E P .t\ RE A 1,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l |
| | _ _.,.limiilll |
| | .. r'"*W;iiill'll 68 69 80*; 0 a. X-529}} |
|
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Category:Letter
MONTHYEARML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson 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 ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman 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 ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, 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 RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, 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 ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, 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 ML24303A0552024-11-0101 November 2024 Letter to J. Keys, 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 ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson 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 ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman 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 ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman 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 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 ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, 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 ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman 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 ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, 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 RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) 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-24-102, 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-24-103, 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-24-080, 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) ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual 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 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000237/LER-2023-001, HPCI Inoperable Due to Air Void Accumulation2024-01-19019 January 2024 HPCI Inoperable Due to Air Void Accumulation 05000237/LER-2022-001-01, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-10-28028 October 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000237/LER-2022-002-01, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-10-28028 October 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-002, Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation2022-09-27027 September 2022 Ultimate Heat Sink Declared Inoperable Due to River Grass Accumulation 05000237/LER-2022-001, Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure2022-09-0909 September 2022 Reactor Scram Due to Turbine Trip on High Reactor Water Level Caused by Feedwater Regulating Valve Failure 05000249/LER-2021-001-01, Reactor Scram Due to Main Power Transformer Failure2022-06-14014 June 2022 Reactor Scram Due to Main Power Transformer Failure ML20135G7442020-05-14014 May 2020 Final ASP Analysis - Dresden 2 (LER 237-90-006) 05000249/LER-2017-0012017-12-27027 December 2017 Unit 3 Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak, LER 17-001-01 for Dresden Nuclear Power Station, Unit 3 Regarding Unit 3 Standby Liquid Control System Inoperable Due to a Manufacturing Defect Causing a Piping Leak ML17252B5052017-11-0303 November 2017 LER 77-050/03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling ML17252A3262017-10-21021 October 2017 LER 77-040/03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position ML17252B4922017-08-28028 August 2017 LER 78-028/01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction 05000237/LER-2016-0032017-05-26026 May 2017 Control Room Emergency Ventilation System Charcoal Filter Bank Failure to meet the Methyl Iodide Penetration Acceptance Criteria, Dresden Nuclear Power Station, Units 2 and 3, Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to meet the Methyl Iodide Penetration Acceptance Criteria ML17153A0342017-05-26026 May 2017 Cancellation of Licensee Event Report 237/2016-003-00, Control Room Emergency Ventilation System Charcoal Filter Bank Failure to Meet the Methyl Iodide Penetration Acceptance Criteria 05000237/LER-2016-0042017-01-0909 January 2017 Reactor Building Differential Pressure Less than Technical Specification Requirement, LER 16-004-00 for Dresden Nuclear Power Station, Unit 2, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement 05000249/LER-2016-0012016-08-25025 August 2016 Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire, LER 16-001-00 for Dresden Nuclear Power Station Regarding Alert Declared from Unit 3 HPCI Auxiliary Oil Pump Motor Fire 05000237/LER-2016-0022016-07-15015 July 2016 Unit 2 HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability, LER 16-002-00 for Dresden Nuclear Power Station, Unit 2 Regarding HPCI Inlet Steam Drain Pot Piping Leak Resulting in HPCI Inoperability 05000237/LER-2016-0012016-04-0808 April 2016 Secondary Containment Differential Pressure Transient, LER 16-001-00 for Dresden Nuclear Power Station, Unit 2 and 3 Regarding Secondary Containment Differential Pressure Transient 05000249/LER-2015-0012016-01-22022 January 2016 Main Steam Line Flow Switches Found Outside Tech Spec Allowed Value, LER 15-001-01, Dresden, Unit 3 Main Steam Line Flow Switched Found Outside Tech Spec Allowed Value ML1015505692009-07-24024 July 2009 Letter LS-AA-1 25-1001, Elevated Tritium Values Identified in 2 Storm Drains Due to Through-Wall Leaks in Underground Piping for Dresden Units 2 and 3. ML0602404072004-05-0505 May 2004 Final Precursor Analysis - Dresden Unit 3 - Unit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3 ML0234501722002-12-0202 December 2002 LER 89-029-05, Dresden Unit 2, Elevated HPCI Discharge Piping Temperature Due to Reactor Feedwater System Back Leakage ML17252B5391981-06-10010 June 1981 LER 81-034/03L-0 for Dresden, Unit 2 Re J-3 CRD Was Tested for Overtravel. the Overtravel Alarm Came Up and Rod Position Indication Was Lost ML17252B5411981-06-0808 June 1981 LER 81-030/01T-0 for Dresden, Unit 2 Re Operator Noticed the HPCI Steam Line Was Cold and Filled with Water. the HPCI System Was Declared Inoperable ML17252B5401981-06-0505 June 1981 LER 81-024/03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue ML17252B5271981-06-0303 June 1981 LER 81-023/03L-0 for Dresden, Unit 2 Re While Running HPCI Pump Test, the Operator Observed Torus Wide Range Level Instrument Reading 0 Inches and Narrow Range Level Instrument Reading, About - 2 Inches and Oscillating ML17252B5281981-04-14014 April 1981 LER 81-015/03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1 ML17252B5291981-03-23023 March 1981 LER 81-011-03L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered Safe ML17252B5301981-02-20020 February 1981 LER 81-080/031-0 for Dresden, Unit 2 Re Abnormal Degradation of Systems Other than Those Specified in Item B.1.e Above Designed to Contain Radioactive Material Resulting from the Fission Process ML17252B5321981-02-17017 February 1981 LER 81-070/03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip ML17252B5331981-02-0202 February 1981 LER 81-020/03L-0 for Dresden, Unit 2 Re During Refueling Outage LPCI Test Spray Valve Failed to Shut Electrically, One Set of Thermal Contacts Would Not Reset ML17252B5351981-01-23023 January 1981 LER 80-050/03L-0 for Dresden, Unit 2 Re the 1501-62D Pressure Switch Actuated at 44.2 Inches of Water Increasing, Tech. Spec. Limit Is Less than or Equal to 41.6 Inches of Water Increasing ML17252B5341981-01-23023 January 1981 LER 80-049/03L-0 for Dresden, Unit 2 Re at Completion of Secondary Containment Leak Rate Test the Reactor Building Ventilation Isolation Valve 2A-5742 Would Not Open ML17252B5371980-12-30030 December 1980 LER 80-046-00 for Dresden 2 Regarding a Failure to Receive CRD Volume During a Reactor Scram ML17252B5361980-12-29029 December 1980 LER 80-046/03L-0 for Dresden, Unit 2 Re Conditions Leading to on Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation ML17252B5381980-12-0303 December 1980 LER 80-043/03L-0 for Dresden, Unit 2 Re Surveillance Testing of the Condenser Low Vacuum Switches, Pressure Switch 2-503D Was Found to Have a Trip Point of 22.85 Inches Hg ML17252B5431980-11-12012 November 1980 LER 80-041/03L-0 for Dresden, Unit 2 Re Reactor Building Vent and Refueling Floor Rad Monitor Surveillance (DCP 2007-12) Was Performed ML17252B5421980-11-12012 November 1980 LER 80-042/03L-0 for Dresden, Units 2 and 3 Re That Technical Staff Personnel Revealed That the Ultrasonic Testing of the Scram Discharge Volume Was Not Performed During the 1500-2300 Shift ML17252B1841980-10-31031 October 1980 LER 80-40/01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open ML17252B5441980-10-29029 October 1980 LER 80-039/03X-1 for Dresden, Unit 2 Re HPCI Inboard Steam Supply Valve Opened and Had a Dual Light Indication ML17252B5451980-10-23023 October 1980 LER 79-017-01X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety ML17252B5461980-10-0808 October 1980 LER 80-016/01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line ML17252B5471980-10-0707 October 1980 LER 80-036/03L-0 for Dresden, Unit 2 Re Discovery That the Six Month Functional Test Required by Tech. Spec. 4.12.A.1 of the Cardox System Heat Detectors Was Not Performed within the Allowable Surveillance Interval ML17252B5481980-10-0101 October 1980 LER 80-033/03L-0 for Dresden, Unit 2 Re the Frequency of Water Addition to the Torus Increased. Leak Rate Tests Indicated a Leak in the 2B LPCI Heat Exchanger ML17252B1861980-08-22022 August 1980 LER 80-032/03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block ML17252B5501980-08-19019 August 1980 LER 80-027/03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator ML17252B5161980-08-14014 August 1980 LER 80-024/03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d ML17252B1881980-08-0404 August 1980 LER 80-030/03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds ML17252B1901980-06-13013 June 1980 LER 80-023/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches ML17252B1911980-06-13013 June 1980 LER 80-024/03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58AB Tripped at Less than Tech. Spec. Limit of 84 Inches ML17252B1921980-06-10010 June 1980 LER 80-025/03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 2024-01-19
[Table view] |
Text
e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS Ltr. /180-476 June 5, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operations
-Region. III U.S. Nuclear Regulatory Commission*
799 Roosevelt Road Glen Ellyn, IL 60137 *** *Reportable Occurrence Report /180-17/031-0, Docket /1050-237, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specific*ation 6.6.B.2.(b),
conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.
BBS/nh Enclosure B. B.
Station Superintendent Dresden Nuclear Power Station cc/ Director of Inspection
& Enforcement Director of Management Information
& Program Control File/NRC LICENSEE EVENT REPORT I
- I 10 (PLEASE PRIN.T ORTYPAIL REQUIRED 1----.1....,_..1-__.....__._...._;;;._-'s\..!J
.# ., CONTROL BLOCK: I I I L I D I R I s I 2 101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I -I 0 I 0 IQ)I 4 11 I 1 11 I 1 1 G)I I I.@ 9 LICENSEE.
CODE . 14 15
- LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 . CON'T } o I 2 I j 0 13 I: l 0 14 I o I s 1 o I o I o I 2 13 11 101 o 1 s 1 1 1 2 I a 1 o I© 1 o I 6. 1 o I s I a I o 1 G) 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@
I *Following a uni"t scram, double* valve indication was observed on the HPCI-inboard isolation valve *. Upon trying to cycle. the valve, the valve failed to close (T.S.3.7.D.l).
The health and safety of the public was not endangered because the ) 0 I sJ I HPCI steam line was isolable
_ via the outboard isolation valve and other ECCS systems -0 Is I* were operable.
'J'his -is the first occurrence of* this type. l a ,,7 r I 1Cr'Tal". 9 80 SYSTEM CAUSE CAUSE COMP. CODE COiJE SUBCOOE COMPONENT.CODE SUB CODE ISIFI@ L!J@ w@ lvlAILlvlolPI@
L!J@) 9 . 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE AEPOP.T LEA/AO CV ENT YEAR. REPORT NO. CODE TYPE .REPORT I 8 I 0 I I l I 0 I l I 7 I I ........
, I 0 I 31 LEJ NUMBER .
- _ 21 22 23 24 . 26 27 28 29 JO VALVE SUBCOOE w@ 20 1=J 31 REVISION.
NO. ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPR0-4 TAKEN ACT.ION' ON PLANT METHOD . . HOURS' _SUBMITTED FORM :;us. PRIME COMP. SUPPLIER.
COMPONENT MANUFACTURER
**-* .
L:J@ L.:J@ I 0 I 0 I 0 I I L!:J@ l:J<§ 33 . 34 ' . 35 . 35* . J-7 40. 41 . . 42 I L I 2 I 0 I 0 I@ . 44 . . . . 47 -.CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@
. 43 , , I 0 I r The failure was due to a packing leak on the valve' causing water to enter the valve ) 1 11 t .I _motor operator.
The mo.tor dr:!,ed out and the valve was and. cycled 1-) 1 I 2 I successfully.
N_o further action deemed necessary. ...............
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....... _ 80* FACILITY 13Q\ STATUS % POWER OTHER STATUS re uu@
- 1 0 I o_ I 0 l@).._I ..;,;,.N:..:.I 0* 9 10 12 n ACTIVITY CONTENT (.;;;'\ RELEASED OF RELEASE.
AMOUNT OF ACTIVITY 7161 .. LU@ W(§ ..... 1
__ _,__ __ _.,....l 9 10 11 44 METHOD OF (:;':;\ DISCOVERY DISCOVERY OESCRIPTlON _
.........
...............................................................
___.*I 45 46 80 LOCATION OF N/A 45. 80 ?ERSONNEL EXPOSURES
- . *-Q_ NUMBER A TYPE . OESCRIPTlON
- m. ro 1 o 1 o
___ ...:..;N..:...;/
A:.:....
__ .....;_ ____ ._,.;.__
_____________
' 8 9 11 12 13 so PERSONNEL INJURIES*
- (,;"";\ NUMBER OESCRIPTION6
- CW* I 0 I 0 I 0
__ * -*_N..;,._/
A ________________________
_,___, 8 9 11 12.
- 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\ TYPE DESCRIPTION*
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3TI: LU@ . 8-9 10 PUBLICITY
(';;;\ 80. "' NR.C USE ONLY ISSUED/,;";;\
- IT£J;. l.::J'6 N /A
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.. r'"*W;iiill'll 68 69 80*; 0 a. X-529