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| | issue date = 06/13/1980 | | | issue date = 06/13/1980 |
| | title = 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 | | | title = 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 |
| | author name = Stephenson B B | | | author name = Stephenson B |
| | author affiliation = Commonwealth Edison Co | | | author affiliation = Commonwealth Edison Co |
| | addressee name = Keppler J G | | | addressee name = Keppler J |
| | addressee affiliation = NRC/RGN-III | | | addressee affiliation = NRC/RGN-III |
| | docket = 05000237, 05000249 | | | docket = 05000237, 05000249 |
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| =Text= | | =Text= |
| {{#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}} |
|
|---|
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
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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 Event Report (LER)
MONTHYEARML20135G7442020-05-14014 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
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
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
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
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
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
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
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
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
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
ML17252B5521980-06-0505 June 1980
LER 80-017/03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close
ML17252B1931980-06-0303 June 1980
LER 80-002/03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close
ML17252B5531980-05-27027 May 1980
LER 80-015/03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance
ML17252B1941980-05-27027 May 1980
LER 80-022/03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125
ML17252B1951980-05-0808 May 1980
LER 80-021/01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operability
ML17252B1961980-04-29029 April 1980
LER 80-017/03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start
2020-05-14
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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
