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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 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 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 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 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 2024-01-19
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- EVE.NT'DESCRIPTION*ANO PROBABLE.CONSEQUENCES@ '.. . . .
..:. ,. o....l"""2""'j'.'IDuring *a* reactor'*s*cram, failed *to receive CRD volume : HI,;_Hi Ievei: alarm*.* The' saf'ety* L
. I . . . . . . . . . *. . . . . . . . ..
- nIJ. lsignifiCance* of this event~ was:m~nimal' since 'it did. n_ot affect* the scram' function. and
0 j r jthe scram* d~t~charge' instrument* volume~ level switches . wete opetab*le<. Public health* and 4-. F' 0 ! s.r. 1'safety were Jlot: affected*~. :This *iS* the. first. occurrence of' this :type at Dresden~ L' o 1s1,~*---------*~i-*---------------------------------------------------------------'
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. SYSTEM'. CAUSE:. 1
CODE:* CODE' ' ' SUBCOOE COMPONENT'COOE. SUBCOOE: *suecooE' 9
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ACTION FUTURE. <, EFFECT SHUTOOWN . . .. , ~- . ATIACHMENT'*.* NPRQ.4: PRIME COMP:. 'COMPONENT *
. TAKEN" ACTION ; ONPl:ANT .:*:'._.METHOD-,.*: . . . . *., _HO.URS'.\~/**. SUBMIT.TEO~* : *FO.RM:>UB. *... SUPPLIER': , MANUFACTURER':'
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33.' 34 . ' 35 . J6.,, ' ' ' *.J'] ' . 40,.. 41 ' ' ' 42 43,. 44' ' ' 47 CAUSE'DESCRIPTION.ANO:CORRECTIVE:ACTIONS*@* * *
} 1 Io fr TI1e cause was. attributed to cable* length* and* routing*:;* transducer placement and mounting,1 *.
- 1 ! 1 1 land redundant transducer signal interference .. *The cables . were shortened- an& rerouted L
- 1 I2 I I transducer placement-. optimized* mounting mod-ified, and. transducer synchronize'd to the.
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- IJJJ. ,. saine 'internal clock~ The: syste~ was. *then satisfactorily-tes.ted. The *same* improvementsl
- Im I will be mad.e on Dresden' Unit: 3. I
- 8 9'. 80 Ffr~~'V % POWER ' .* o;.~R*S~~TUSc' @ ~I~~~~~ DISCOVERY DESCRIPTION @)
- ITIJ' l.x..J@: I 0 I 0 8 9 -10* .
12:* 1'.l N/A. 1.
44..
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45 AS l_O.._p_er_a_t_or_:._O_b_se_rv_at_i_o_n_ _ _ _ _ _____.L 80 ACTIVITY CONTENT ' . C\ .~
~ELEASEO OF RELEASE. .
- AMOUNT OF ACTIVITY ~ LOCATION OF* RELEASE:~ .
l-1--"i~@ ~~t. N/A .
44 ts. N/A 80:
PERSONNEl:.*EXP.OSURES: . 'r.:;;:;\ .
' NUMBER ' ; ' TYPE DESCRIPTION\~;
- II!l 1o Io Io l@Ll.J@ __._ _ _ _ N/_.A._ _ _ _ _ _ _ ___,.,.______________,
8 3. 11 12; 13 80 .
PERSONNEL INJURIES. . : /;;;\*.
DESCRIPTION\~/*:,*
- IE. 8, 9 j'
'NUMBER ol. ol ol@) :. . . .
11 N/A.
- . _ i 2 - : * - - - . - - - - - - - - - - - - - - - - - - - - -........- - - - - - - - - - - - - - - - - a ' " ' o . *.
LOSS OF-OR DAMAGE 1TO*FAC1LITY:*f.G\* *
~ TYPE DESCRIPTlpN * . . . *. ~ **
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- . .* DEVIATION* REPORT * . *
' JJVR:.-No.*. . .
- * :* * . STA':. UNIT.' YEAR?. NO:.
It'-* !2 - 2. -
PART. ll*Jl Tl£. OF- DEVtl ATl'ON:: * ...... OCCU.RREO . .
DATE TIME. ~
SYSTEM**AFFECTEO> .
. ' 300
, ..* PLANT CONDITIONS,*
..o*
TESTING .
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Control Rod* Dr.ive: System*.*. . MODE' Run* PWR'(MWT) . l:OAC(M~)-_'
368 YES'" NO:*
DESCRIPTION OF EVENT.
- During**a: reactor scram*,, .. failed to-get.ala~. 902:-4~- F-21. "SDV*Hi Hi".<-
DESCRIPTION OF CAUSE.
Unknown *at this* *t iiiie* *..
. OTHER APPL I C~BLE *I NFORMAT.I ON N/A.
EQUIPMENT CiJ.Yes* DR' NO.~ WR: NO; ..,-
12-3-80.
- D*. McDowell FAILU.RE. . Q:No., " N/A Dl0353 . *RESPONSIBLE SUPERVISOR* DATE PART 2. I OPERATING ENGi NEERS COMMENTS
- Complet.ed SDV air test,. instrument. volum~ level. swit.ch test .and: ihdepend.ent UT verification.
Initiated ind'ependent*. manual UT yeri*fication of SDV once' per< shift .on' Units* 2 and 3.
. . SAFE.TY-TYPE'. OF DEVIATION EVENT OF* POTENT! AL.
- TE:CH: SP'EC' ,, NC°N._ REPORTABLE" .. ANNUAL RELATED "0: .o*.
REPORTABLE OCCURRENCE::
- PUBL:lC: I NTERE:sr: ..* . .. VIOLATION-0.,.
OCCURRENCE REPORT I NG.
YES:
~
. WR ISSUED YES GI.
14 DAY o.
1?CFR2.F
- * [!]* 3 ~. DAY: NOTI F:t*CATlON 6.6.B.2.b D' . No .. o* NO D
.. REPOR~t~~~k:CCCUR~ENcE* *ACT! ON ITEM NO*. PROMPT* ON-.. S I TE NOTIFICATION .
- R. M. Ras~ui 12-9-80' -* ..
m, 80-A6 I 03L-O" Tl TL£ DATE TIME Tl TLE
- . 24-HOUR NRC NOTJ.F:l CAT:J ON . PROMPT OFF-SI TE NOTI FICATl'ON i
DT?H NRC..;ENS Ehone* 12/2/80 2300 hrs. F. A~ Palmer 12-10-80 *9*:03 AM REG l*ON,
- I* I I DATE Tl.ME** Tl TLE. DATE'. TIME DTGM .. ., .
REGION,! I ! &. DOL* CATE TIME. Tl TLE: . DATE TI ME RESPONSl.BLE COMP:ANY'.OFF:lCER *INFORMED OF CONDI Tl ONS AND THEIR REPORT TO* NRC
... TITLE DATE TIME c I . .
REVIEW* AN.D .COMPLETED' - John W. Wuj ciga 12-8-80 OPERATING. ENGINEER DATE D.ATF.:
\
RESOlUT I ON APPROVED. ANO' 12/s.}Pc AUTHOR i ZED~ FOR. 0 I' STR i SU Ti ON
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