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| | issue date = 06/05/1980 | | | issue date = 06/05/1980 |
| | title = 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 | | | title = 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 |
| | 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 | | | docket = 05000237 |
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| =Text= | | =Text= |
| {{#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 | | {{#Wiki_filter:*** |
| -Region. III U.S. Nuclear Regulatory Commission* | | e Commonwec9 Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 June 5, 1980 BBS Ltr. /180-476 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. | | 799 Roosevelt Road Glen Ellyn, IL 60137 |
| BBS/nh Enclosure B. B.
| | *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. |
| Station Superintendent Dresden Nuclear Power Station cc/ Director of Inspection | | ,~~?~. |
| & Enforcement Director of Management Information | | B. B. Stephenson~ |
| & Program Control File/NRC LICENSEE EVENT REPORT I | | Station Superintendent Dresden Nuclear Power Station BBS/nh Enclosure cc/ Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC |
| * 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. | | LICENSEE EVENT REPORT |
| CODE . 14 15 | | ., CONTROL BLOCK: I* |
| * LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 . CON'T } o I 2 I j 0 13 I: l 0 1 4 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@ | | 1----.1....,_..1-__.....__._...._;;;._-'s\..!J I10 (PLEASE PRIN.T ORTYPAIL REQUIRED INFORMATIO~J |
| 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). | | ~ I II 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 1G)I I I.@ |
| 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. | | ~ 9 LICENSEE. CODE . 14 15 |
| '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@ | | * LlCENSE NUMBER 25 26. LICENSE TYPE. JO 57 CAT 58 . |
| 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 .
| | CON'T |
| * _ 21 22 23 24 . 26 27 28 29 JO VALVE SUBCOOE w@ 20 1=J 31 REVISION.
| | ~ :;~~~; ~©I o I s 1o I o I o I 2 13 11 101 o1 s 1 1 12 I a 1o I© 1 o I 6. 1 o I s I a I o 1G) |
| NO. ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPR0-4 TAKEN ACT.ION' ON PLANT METHOD . . HOURS' ''_SUBMITTED FORM :;us. PRIME COMP. SUPPLIER.
| | ~ 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@ |
| COMPONENT MANUFACTURER
| | }o I 2 I I *Following a uni"t scram, double* valve indication was observed on the HPCI-inboard j 0 13 I: 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 l0 14 I |
| ----**-* .
| | ) 0 I sJ I HPCI steam line was isolable _ via the outboard isolation valve and other ECCS systems |
| 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 1 1 t .I _motor operator.
| | - 0 Is I* were operable. 'J'his - is the first occurrence of* this type. |
| The mo.tor dr:!,ed out and the valve was and. cycled 1-) 1 I 2 I successfully.
| | I l a ,,7 r 1Cr'Tal". L,___;_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,__,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_..,_-,---,-..,_-,-..,_..,_...:.._..,_..,_..,_..,_..,_..,_..,_..,_~ |
| N_o further action deemed necessary. ...............
| | ~ 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE COiJE SUBCOOE COMPONENT.CODE SUB CODE SUBCOOE ISIFI@ L!J@ w@ lvlAILlvlolPI@ L!J@) |
| _,.. ..... _._ ................ | | 9 . 10 11 12 13 18 19 w@ |
| ..,_...;.. | | 20 SEQUENTIAL OCCURRENCE AEPOP.T REVISION. |
| ............... | | ~ LEA/AO CV ENT YEAR. REPORT NO. CODE TYPE NO. |
| -.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.-
| | ~ .REPORT NUMBER I 8 I.0 I* I l I 0 I l I 7I I ........ , I 0 I 31 LEJ 1=J ~ |
| ....... _ 80* FACILITY 13Q\ STATUS % POWER OTHER STATUS re uu@ | | _ 21 22 23 24 . 26 27 28 29 JO 31 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPR0-4 PRIME COMP. COMPONENT TAKEN ACT.ION' ON PLANT METHOD . . HOURS' ''_SUBMITTED FORM :;us. SUPPLIER. MANUFACTURER - ---**-* |
| * 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
| | . 33~@~@* . 34 ' . 35 L:J@. L.:J@ |
| __ _,__ __ _.,....l 9 10 11 44 METHOD OF (:;':;\ DISCOVERY DISCOVERY OESCRIPTlON _
| | 35* . |
| ......... | | I J-7 0 |
| ............................................................... | | I 0 I 0 I 40.I L!:J@ 41 . . |
| ___.*I 45 46 80 LOCATION OF N/A 45. 80 ?ERSONNEL EXPOSURES
| | l:J<§ 42 |
| * . *-Q_ NUMBER A TYPE . OESCRIPTlON
| | -~. I L I 2 I 0 I 0 I@ . |
| : m. ro 1 o 1 o
| | 44 . . .. 47 - -~- |
| ___ ...:..;N..:...;/
| | 43 |
| A:.:.... __ .....;_ ____ ._,.;.__ _____________
| | .CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@ . |
| ----' 8 9 11 12 13 so PERSONNEL INJURIES*
| | , , I0 I r The failure was due to a packing leak on the valve' causing water to enter the valve |
| * (,;"";\ NUMBER OESCRIPTION6
| | ) 1 11 t .I _motor operator. The mo.tor dr:!,ed out and the valve was rep~cked and. cycled 1-successfully. N_o further action deemed necessary. |
| :CW* I 0 I 0 I 0
| | ) 1 I2 I |
| __ * -*_N..;,._/
| | ::IJJ]*'L,_;._;_-.,--.,--.,--.,-_;__-.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,--.,-~-.,--.,-~-.,--.,--.,--.,--.,------.,-~~~~~ |
| A ________________________
| | ~8-9~..............._,......._._..................,_...;.................-.--.--.--.--.---'-.-..--.--.--.--.--.--..,..-.--,---,---,---,---,---,---,---,---,---,---.,..-,---,--..--,---.--.-....... _ |
| _,___, 8 9 11 12.
| | ~ 80* |
| * 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\ TYPE DESCRIPTION*
| | FACILITY 13Q\ METHOD OF (:;':;\ |
| ".:::::) 3TI: LU@ . 8-9 10 PUBLICITY
| | re uu@ *1 I 0* |
| (';;;\ 80. "' NR.C USE ONLY ISSUED/,;";;\
| | STATUS 9 |
| :IT£J;. l.::J'6 N /A
| | ACTIVITY 10 0 |
| : 8. 9 IQ. K. Zirwas N A,'/i E CF PP. E P .t\ RE A 1 ,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l
| | CONTENT |
| _ _.,.limiilll
| | % POWER o_ |
| .. r'"*W;iiill'll 68 69 80*; 0 a. X-529}} | | 12 n OTHER STATUS I 0 l@).._I..;,;,.N:..:.IA=--------~ |
| | ~ |
| | (.;;;'\ |
| | DISCOVERY 45 46 DISCOVERY OESCRIPTlON ~ _ |
| | ll.JQ2)~1.........~O~p~e~r~a~t~or-=-O~b~s~e~rv;;;...;..;a~t~1~*o~n-=-...............................................................___.*I 80 RELEASED OF RELEASE. AMOUNT OF ACTIVITY ~ LOCATION OF RELEA~E@ |
| | 7161.. LU@ W(§ 1. . ._..;N~/-=A_ __,___ __.,....l N/A |
| | ~ 9 10 11 44 45. 80 |
| | ?ERSONNEL EXPOSURES * . *-Q_ |
| | : m. ro 8 9 NUMBER 1 o 1o 11 A |
| | 'l2J@~ |
| | TYPE 12 |
| | . OESCRIPTlON 13 |
| | ...:..;N..:...;/A:.:...._ _.....;__ _ _ _._,.;.___ _ _ _ _ _ _ _ _ _ _ _ _- - - - ' |
| | so PERSONNEL INJURIES* * (,;"";\ |
| | :CW* 8 9 NUMBER I0 I 0 I0 11 I@~--- |
| | OESCRIPTION6 12. |
| | __* -*_N..;,._/A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __,___, |
| | * 00 LOSS OF OR DAMAGE TO FACl.LJTY f'43\ |
| | TYPE DESCRIPTION* ".:::::) |
| | 3TI: LU@ |
| | 8- 9 10 |
| | . ~/A 80. |
| | PUBLICITY (';;;\ |
| | NR.C USE ONLY ISSUED/,;";;\ DESCRIPTION~ |
| | :IT£J;. l.::J'6 N /A 1111111111111~ |
| | : 8. 9 IQ. 68 69 80*; |
| | K. Zirwas X-529 0 a. |
| | N A,'/i E CF PP. E P.t\ RE A 1,....,_,_,....':;miiimi--t"-"llAilliiiii_ii!l__.,.limiilll. .r'"*W;iiill'll}} |
|
|---|
Category:Letter
MONTHYEARML24317A1432024-11-0404 November 2024
Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums
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Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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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
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Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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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
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Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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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
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Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station
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Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station
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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
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NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3
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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
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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
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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
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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 June 5, 1980 BBS Ltr. /180-476 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.
,~~?~.
B. B. Stephenson~
Station Superintendent Dresden Nuclear Power Station BBS/nh Enclosure cc/ Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC
LICENSEE EVENT REPORT
., CONTROL BLOCK: I*
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~ 60 61 DOCKET NUMBER 68 69 . EVENT DATE 74 75 REPORT DATE ao EVENT DESCRIPTION A":'D PROBABLE_CONSEQUENCES@
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- 0 Is I* were operable. 'J'his - is the first occurrence of* this type.
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