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| {{#Wiki_filter:Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS LTR. /180-507 June 13, 1980 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s | | {{#Wiki_filter:Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 |
| -Region III Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 | | * WN l 8 1980 June 13, 1980 BBS LTR. /180-507 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s - Region III U~S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q- ~Dock.e.t JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification 6.6~B.2(a), reactor protection system or engineered safety feature instrument settings which are found to be less conservative:::: |
| * WN l 8 1980 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q-JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification reactor protection system or engineered safety feature instrument settings which are found to be less conservative::::
| | than those established by the Technical Specifications but which do not pre':'<;~-..t vent the fulfillment of the functional requirements of.affected systems. |
| than those established by the Technical Specifications but which do not vent the fulfillment of the functional requirements of.affected systems. BBS: | | ~~\=)~Ji-- |
| B.B. Stephenson . Station Superintendent .presden Nuclear Power Station Enclosure cc: Director of Inspection | | B.B. Stephenson . |
| & E.nfor.cement Director of Management Information | | Station Superintendent |
| & Program Control File/NRC 11.n1 ***--,. LICENSEE EVENT REPORT ?._. :*'C\J"TROL BLOCK: .___,._l_.....___.. | | .presden Nuclear Power Station BBS: |
| _ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I -I 0 I 0 I O: I 0 I 0 1-. I 0 I 0 1(2)1 4 1 1 1 1 1 1 1 1 101 I I © 9 . LICENSEE. | | Enclosure cc: Director of Inspection & E.nfor.cement Director of Management Information & Program Control File/NRC |
| CODE, | | |
| * 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B J --** | | 11.n1 LICENSEE EVENT REPORT |
| L.U©I 01 5 Io I o I o I 41 9 IGI o* 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o I G) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\ I During normal operation,* | | ?._. :*'C\J"TROL BLOCK: .___,._l_.....___.._ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I - I 0 I 0 I O: I 0 I 0 I0 I 0 1(2)1 4 11 11 11 11 I I© 1-. 101 |
| with reactor'-ievel instrument surveillance in progress, level ; 0 1 3 I I switch LIS 3-263-58B tripped at less than the* Tech. | | ~ 9 . LICENSEE. CODE, |
| limit (Table 3.2.1) of 84 I 0 1 4 1. I inches. The safety significance of this event was minimal since channel "A" and the )a Is I I redundant Channel "B" instruments were operable. | | * 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B CON~T |
| There was no effect on public health J 0 lo I I or safety. Previous occurrences.: | | ;~rl J :;~~~; L.U©I 01 5 Io I o I o 1~2 I 41 9 IGI o* I~ 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o IG) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\ |
| R.O. 76-57/031-0,. | | I During normal operation,* with reactor'-ievel instrument surveillance in progress, level 0 |
| Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249. 80. SYSTEM CODE I I IB I@ 9 10 G\ LEA/RO YEAR "V REPORT I 8 I 0 I NUMBER 21 . 22 ACTION . FUTURE TAKEN ACTION EFFECT ON PLANT CAUSE CAUSE COMP. VALVE CODE SUBCODE COMPONENT CODE SUBCODE | | 1 3 |
| * SUSCODE 11IN1s1T IR 1u I@ L:J@} L:J@ 11 12 13 L=J 23 SHUTDOWN METHOD SEQUENTIAL* | | I I switch LIS 3-263-58B tripped at less than the* Tech. Spec~ limit (Table 3.2.1) of 84 I0 14 1. I inches. The safety significance of this event was minimal since channel "A" and the |
| REPORT NO. I 0 I 2 I 4 I 24" 26. HOURS 18 OCCURRENCE CODE 1.......-1 10 13 27 28 29 19 20 REPORT TYPE 30 31 NPRD-4 FORM ::;us. PRIME COMP: SUPPLIER | | )a Is I I redundant Channel "B" instruments were operable. There was no effect on public health J |
| * REVISION NO. 32 COMPONENT MANUFACTUR.E L:J@ L!J I o I o. I o ATTACHMENT SUBMITTED I Ll@ ll:l y 0 1 .o 33 34 . 35 36 3 7 40 41 42 43 44 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @ j 1 lo I I The cause of this event is.unknown at this time. The was immediately re-: , I 1 I : 1 I 2 I tested, with satisfactory results. Subsequent tests were performed, and each time the results were satisfactory. | | 0 lo I I or safety. Previous occurrences.: R.O. 76-57/031-0,. Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249. |
| DIS* 500-2 will continue to* be done monthly. 47 I I :=IIIJ *---------------------------------------------------8 9 FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS . DISCOVERY DISCOVERY DESCRIPTION | | 80. |
| @ , Instrument Mechanic Surveillance so 1° 1 8 1 4 l@I NtA | | SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE |
| * I L!J@I *a 9 10 12 45 "" 46-* | | * SUSCODE I I IB I@ ~@~@ 11IN1s1T IR 1u I@ L:J@} L:J@ |
| ACTIVITY CONTENT OF RELEASC: ..>.MOUNT OF ACTIVITY L2J@ N/A ' . I 8. 9 10 11 . 44 PERSONNEL EXPOSURES | | 9 10 11 12 13 18 19 20 SEQUENTIAL* OCCURRENCE REPORT REVISION G\ LEA/RO c~VENT YEAR REPORT NO. CODE TYPE NO. |
| *(.;";;\ NUMBER DESCRIPTION m 1° 1° 1° 1021L:J 8 9 11 12 | | "V REPORT NUMBER I 8 I. 0 I L=J I 0 I2 I4 I 1.......-1 10 13 ~ ~ |
| ?ERSONNEL INJURIES f,;:;\ N/A LOCATION*OF RELEASE @. 45 80 N/A NUMBER DESCRIPTIONa | | 21 22 23 24" 26. 27 28 29 30 31 32 ACTION . FUTURE EFFECT I o I o. I o ~ |
| / 10 10 jO l@I NA a 9 11 LOSS OF OR DAMAGE TO FACILITY t4J\ TYPE. DESCRIPTION I v::::J zw* L:J@ . . N A 8 9 10 PUBLICITY f:::'\ ISSUEDf,;":;\
| | SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP: COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM ::;us. SUPPLIER |
| :IITJ* LJLl6 N A 8 9 10 . P. Holland 80 NRC USE ONLY *Q I "' I I I I I I I I I I I I 68 69 30.;; X-523}} | | * MANUFACTUR.E l!J@L~J@ |
| | 33 34 . |
| | L:J@ |
| | 35 L!J 36 37 I 40I~@ 41 Ll@ ll:l y 0 1 .o 42 43 44 47 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @ |
| | j 1 lo I I The cause of this event is.unknown at this time. The inst~ument was immediately re-tested, with satisfactory results. Subsequent tests were performed, and each time the |
| | : , I1 I I |
| | ~ |
| | results were satisfactory. DIS* 500-2 will continue to* be done monthly. |
| | : 1 I2 I I |
| | :=IIIJ *--------------------------------------------------- |
| | ~8 9 so FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS ~ . DISCOVERY DISCOVERY DESCRIPTION @ , |
| | ~ ~@ 1° 1 8 14 l@I~n---------44_. NtA |
| | * I L!J@I Instrument Mechanic Surveillance |
| | *a 9 10 12 45 ""-*.----'------------------~so 46 ACTIVITY CONTENT ~ |
| | ~RELEASED OF RELEASC: ..>.MOUNT OF ACTIVITY ~ LOCATION*OF RELEASE @. |
| | ~ L2J@ ~I N/A ' . I N/A |
| | : 8. 9 10 11 . 44 45 80 PERSONNEL EXPOSURES *(.;";;\ |
| | m 8 1° 9 |
| | NUMBER ~TYPE 12 DESCRIPTION ~ |
| | 1° 1° 111021L:J1~3---------------------~-~-------------8--'0 |
| | ?ERSONNEL INJURIES f,;:;\ |
| | N/A NUMBER DESCRIPTIONa |
| | ~ 10 10 jO l@I NA / ~ |
| | a 9 11 .~12:-------------------------~------------~---~ |
| | t4J\ |
| | zw* L:J@ . |
| | LOSS OF OR DAMAGE TO FACILITY TYPE. DESCRIPTION I v::::J |
| | . N A 8 9 10 80 PUBLICITY f:::'\ NRC USE ONLY ISSUEDf,;":;\ DESCRIPTION~* *Q |
| | :IITJ* LJLl6 8 9 10 N A 68 I I I I I I I I I I I I I "'~ |
| | 69 30.;; |
| | . P. Holland X-523}} |
|
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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 ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, 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 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 ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 ML24303A0552024-11-0101 November 2024 Letter to J. Keys, 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 ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman 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 ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson 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 ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief 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 ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman 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 ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman 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 ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief 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 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 ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson 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 ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman 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 ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman 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) 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 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 IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 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-24-102, 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-24-080, 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) SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report ML24270A0332024-09-20020 September 2024 Independent Spent Fuel Storage Installation Annual Radioactive 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 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 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
Commonwe.Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920
- WN l 8 1980 June 13, 1980 BBS LTR. /180-507 James G. Keppler, Regional Director Directorate of Regulatory Operatfop.s - Region III U~S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report iJ 8Q..:.24/03L..:.Q- ~Dock.e.t JI 050-249 , is being submitted to your office in acco:r;dance with Dresden Nuclear Power Station Technical Specification 6.6~B.2(a), reactor protection system or engineered safety feature instrument settings which are found to be less conservative::::
than those established by the Technical Specifications but which do not pre':'<;~-..t vent the fulfillment of the functional requirements of.affected systems.
~~\=)~Ji--
B.B. Stephenson .
Station Superintendent
.presden Nuclear Power Station BBS:
Enclosure cc: Director of Inspection & E.nfor.cement Director of Management Information & Program Control File/NRC
11.n1 LICENSEE EVENT REPORT
?._. :*'C\J"TROL BLOCK: .___,._l_.....___.._ _.1_!_...._-'J 0 !PLEASE PRINT OR TYPE'L REQUIREO lNFORMATIONI ro-rna I I I L I D IR Is I 3 IG)I 0 I 0 I - I 0 I 0 I O: I 0 I 0 I0 I 0 1(2)1 4 11 11 11 11 I I© 1-. 101
~ 9 . LICENSEE. CODE,
- 14 . 15 LICENSE NUMBER 25 26 . LICENSE. TYPE JO. 57 CAT 5B CON~T
- ~rl J
- ;~~~; L.U©I 01 5 Io I o I o 1~2 I 41 9 IGI o* I~ 11 J 9_ 18 Io IG)I or 6 I 1 I o I 8 I o IG) 60 61 DOCKET NUMBER 08 69 EVENT DATE 74 75 . REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (iQ\
I During normal operation,* with reactor'-ievel instrument surveillance in progress, level 0
1 3
I I switch LIS 3-263-58B tripped at less than the* Tech. Spec~ limit (Table 3.2.1) of 84 I0 14 1. I inches. The safety significance of this event was minimal since channel "A" and the
)a Is I I redundant Channel "B" instruments were operable. There was no effect on public health J
0 lo I I or safety. Previous occurrences.: R.O. 76-57/031-0,. Docket 50-237; 77....,51/031-0 and 80-23/031-0, Docket 50-249.
80.
SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE
- SUSCODE I I IB I@ ~@~@ 11IN1s1T IR 1u I@ L:J@} L:J@
9 10 11 12 13 18 19 20 SEQUENTIAL* OCCURRENCE REPORT REVISION G\ LEA/RO c~VENT YEAR REPORT NO. CODE TYPE NO.
"V REPORT NUMBER I 8 I. 0 I L=J I 0 I2 I4 I 1.......-1 10 13 ~ ~
21 22 23 24" 26. 27 28 29 30 31 32 ACTION . FUTURE EFFECT I o I o. I o ~
SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP: COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM ::;us. SUPPLIER
33 34 .
L:J@
35 L!J 36 37 I 40I~@ 41 Ll@ ll:l y 0 1 .o 42 43 44 47 CAUSE DESCRIPTION AND.CORRECTIVE ACTIONS @
j 1 lo I I The cause of this event is.unknown at this time. The inst~ument was immediately re-tested, with satisfactory results. Subsequent tests were performed, and each time the
- , I1 I I
~
results were satisfactory. DIS* 500-2 will continue to* be done monthly.
- 1 I2 I I
- =IIIJ *---------------------------------------------------
~8 9 so FACILITY f:i(j\ METHOD OF STATUS % POWER OTHFR STATUS ~ . DISCOVERY DISCOVERY DESCRIPTION @ ,
~ ~@ 1° 1 8 14 l@I~n---------44_. NtA
- I L!J@I Instrument Mechanic Surveillance
- a 9 10 12 45 ""-*.----'------------------~so 46 ACTIVITY CONTENT ~
~RELEASED OF RELEASC: ..>.MOUNT OF ACTIVITY ~ LOCATION*OF RELEASE @.
~ L2J@ ~I N/A ' . I N/A
- 8. 9 10 11 . 44 45 80 PERSONNEL EXPOSURES *(.;";;\
m 8 1° 9
NUMBER ~TYPE 12 DESCRIPTION ~
1° 1° 111021L:J1~3---------------------~-~-------------8--'0
?ERSONNEL INJURIES f,;:;\
N/A NUMBER DESCRIPTIONa
~ 10 10 jO l@I NA / ~
a 9 11 .~12:-------------------------~------------~---~
t4J\
zw* L:J@ .
LOSS OF OR DAMAGE TO FACILITY TYPE. DESCRIPTION I v::::J
. N A 8 9 10 80 PUBLICITY f:::'\ NRC USE ONLY ISSUEDf,;":;\ DESCRIPTION~* *Q
- IITJ* LJLl6 8 9 10 N A 68 I I I I I I I I I I I I I "'~
69 30.;;
. P. Holland X-523