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Category:Licensee Event Report (LER)
MONTHYEAR05000316/LER-2017-0012017-05-19019 May 2017 1 OF 5, LER 17-001-00 for Cook, Unit 2 re Containment Hydrogen Skimmer Ventilation Fan #1 Inoperable Longer than Allowed by Technical Specifications 05000316/LER-2016-0022017-02-0909 February 2017 Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue, LER 16-002-00 for Donald C. Cook Nuclear Plant Unit 2 Regarding Emergency Diesel Generators Declared Inoperable Due to a Manufacturing Design Issue 05000316/LER-2016-0012016-08-31031 August 2016 Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure, LER 16-001-00 for Donald C. Cook Nuclear Plant, Unit 2 Regarding Manual Reactor Trip Due To Moisture Separator Heater Expansion Joint Failure ML16193A3902016-07-15015 July 2016 Donald C. Cook Nuclear Plant Unit 2 - A Loss of Main Condenser Event Occurred Due to a Storm-Induced Debris Damage of the Circulating Water System Pumps in the Forebay (LER-316-2014-003-00) 05000315/LER-2015-0022016-01-18018 January 2016 -Technical Specification Violation due to Inoperable Residual. Heat Removal Pump, LER 15-002-01 for D.C. Cook, Unit 1, Regarding Technical Specification Violation Due to Inoperable Residual Heat Removal Pump 05000316/LER-2015-0012016-01-15015 January 2016 Manual Reactor Trip Due To A Secondary Plant Transient, LER 15-001-01 for D.C. Cook, Unit 2, Regarding Manual Reactor Trip Due to a Secondary Plant Transient ML0528703602005-10-0505 October 2005 Special Report for D. C. Cook Unit 2 Re Unit 2 Reactor Coolant Inventory Tracking System ML0508903452005-03-22022 March 2005 LER 99-001-01 Donald C. Cook Nuclear Plant Unit 2, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations ML0210601432002-04-12012 April 2002 LER 02-02-00, Donald C. Cook Nuclear Plant Unit 2, Technical Specification 3.9.4.c Was Violated During Core Alteration ML0209205342002-03-15015 March 2002 LER 99-012-01 for Cook Nuclear Plant, Unit 1 Re Auxiliary Building ESF Ventilation System May Not Be Capable of Maintaining ESF Room Temperature Post-Accident ML9936300511999-12-20020 December 1999 LER 99-S004-00, Intentionally Falsifying Documentation Results in Unauthorized Unescorted Access, on 11/18/99. with Letter Dated 12/20/99 ML9934002411999-11-29029 November 1999 LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination ML18219B5201978-09-27027 September 1978 09/27/1978 Letter Enclosure of Licensee Event Report ML18219E1521978-09-27027 September 1978 Submit Licensee Event Report Nos. RO 78-051/03L-0 & RO 78-052/03L-0 ML18219B5211978-09-19019 September 1978 09/19/1978 Letter Enclosure of Licensee Event Report ML18219E1531978-09-18018 September 1978 Submit Licensee Event Report No. RO 78-050/03L-0 ML18219B5541978-09-18018 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-062/03L-0) ML18219B5551978-09-12012 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-56/03L-1 and RO 78-061/03L-0) ML18219E1541978-09-12012 September 1978 Submit Licensee Event Report No. RO 78-049/03L-0 ML18219B5561978-09-0808 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0) ML18219E1551978-09-0808 September 1978 Submit Licensee Event Report No. RO 78-048/03L-0 ML18219B5571978-09-0505 September 1978 Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0 ML18219B5581978-08-30030 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report RO 78-058/03L-0 ML18219B5621978-08-22022 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-056/03L-0 and RO 78-057/03L-0) ML18219B5611978-08-18018 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-052/03L-0, RO 78-053/03L-0, RO 78-054-03L-0 and RO 78-055/03L-0) ML18219E1561978-08-15015 August 1978 Submit Licensee Event Report No. RO 78-047/03L-0 ML18219E1571978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0 ML18219E1581978-08-14014 August 1978 Submit Licensee Event Report Nos. RO 78-043/03L-1 & RO 78-044/03L-1 ML18219E1601978-08-11011 August 1978 Submit Licensee Event Report Nos. 1978-043-03L & 1978-044-03L ML18219B5641978-08-10010 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-051/03L-0) ML18219B5651978-08-0909 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-1) ML18219B5661978-08-0808 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-050/03L-0) ML18219B5671978-08-0404 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-049/03L-0) ML18219B5681978-08-0202 August 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-029/03L-1 and RO 78-048/03L-0) ML18219B5691978-07-21021 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-019/03L-1 and RO 78-023/03L-1) ML18219B5701978-07-18018 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-047/03L-0) ML18219B5711978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-043/03L-0), Submitted Late Due to a Paper Defect ML18219B5721978-07-11011 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-034/03L-1, RO 78-044/03L-0, RO 78-045/03L-0, RO 78-046/03L-0) ML18219B5731978-07-0505 July 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-042/03L-0) ML18219B5751978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken IR 05000316/19780371978-06-29029 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 50-316/78-037), Stating Corrective Actions Taken ML18219B5771978-06-22022 June 1978 D.C. Cook - Submit Licensee Event Report RO 78-036/03L-0 for Unit 2 ML18219B5761978-06-21021 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-035/03L-0), a Resubmittal of LER 78-034/03L-0 Dated 6/19/1978 IR 05000316/19780341978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5781978-06-19019 June 1978 D.C. Cook - Submit Licensee Event Report RO 50-316/78-034/03L-0 for Unit 2 ML18219B5221978-06-0606 June 1978 06/06/1978 Letter Licensee Event Report ML18219B5741978-06-0303 June 1978 Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-038/03L-0, RO 78-039/03L-0, RO 78-040/03L-0, RO 78-041/03L-0) ML18219B5241978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5231978-06-0202 June 1978 06/02/1978 Letter Licensee Event Report ML18219B5251978-05-25025 May 1978 05/25/1978 Letter Licensee Event Report 2017-05-19
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I e AEC DIST'TIG" FOR PART 50 DQCI'ET ME AXIAL (TEi'PORARY FORi'il)CONTROL NO: FILE: 210 F RO;l Indiana It: Michigan Power Bridgman, Mich.49106 R.W.Jur enson oDATE OF DOC DATE REC'D 12-0-4 TV,'X RPT OTHER TO: Mr.J.G.Keppler ORIG 1 signed CC OTHER SENT AEC PDR SENT LOCAL PDR CLASS UNCLA XX PROPIixIFO INPUT NO CYS REC'D 1 DOC,iET NO: 50-315 DESCRIPTION:
Ltr furnishing suppl to A'bnorma Occurrence AO-50-315/74-09 involving the brea'being closed w1.thout having intermediate range channels in service on 12-18-74....
ENCLOSURES:
rs[~WUO qn~N q C't 1[t<iNLJuwl u~i PLANT NAME: Cook 1 BUTLER (S)W/Copies CLARK (S)W/Copies PARR (S)W/Copies 46llgL (S)W/+Copies SCHIIENCER (S)W/Copies STOLZ (S)W/Copies VQSALLO (S)W/Copies PURPLE{S)W/Copies i1EQ EX'ECH REVIEW AEC DR'I AGC 2 ROOM P-506-A+AIACCARRY AJNZZXNG/STAFF
~XGHT CREASE L@AWLICKI GXAEIBUSSO C8HAO BOYD CTELLO MOORE (S)(BWR)KIOUSTON DEXOUNG (S)(PWR)AOVAK SKOVHOLT (S)40SS GOLLER (S)APPOLITO PE COLLINS TEDESCO DENISE~NG REG OPR@t AINAS XLE®XON Q}4ENAROYA.R.WILSON IAx STEELE~VOLDIER REGAN (E)W/Copies LEAR (S)Iif/Copies sPEIs (s)W/Copies ZIE>fANN (S)W/Copies DXCKER (E).W/Copies KNXGHTON (E)W/Copies YOUNGBLOOD (E)Co ies INTc>x AL DISt I DENXON GRIMES GAMMILL~TNER BALLARD SPANGLER ENUXRO MULLER DXCKER KNXGEETON YOUNGBLOOD REGAN PROJECT LDR HARLESS I=.)U 7 I 0 ixI LXC.ASST.~AT XN 9XGGS (S)BRAITMAN GEARIN (S)SALTZMAN..'GOULBOURNE (S)B.HURT KREUTZER (E)LEE (S)PLANS>UIXGRET (S)MCDONALD ED (E)CHAPMAN ERVXCE (S)DUBE w/input SEEEPPARD (S)E.COUPE SMTER (E)~D.THOMPSON (Q)SMITH (S)~KLECmR TEETS (S)6fF.WXTLIAI(fS WILLIAMS (E)WILSON (S)INGRAM (S)FOR ACTIONX'Ii" FOR XIATIO'" DE/1~~N=4.-TXC(ABERNATHY) 51"NSXC(BUCHANAN) 1"ASLB 1 NEWE.'ON ANDERSON Q5"ACRS SENT TO LXC~ASST'.Service 1-9-75 E):TERN.RL DIS R IBUTIQi~!(1)(2)(10)-NATIONAL LABS 1-N.PENNINGTON, RM E-201 G.T.1-CONSULTAEG S NEWI IARK/BLUE/AGBABIAN 1"PDR SAN/LA/NY 1 BROOKEiAVEN NAT LAB 1-G, ULRIKSON, ORNL.1-AGMED(RUTH GUSSMAN)RM B-127 G.T.1-J~RUNKLES, RM E-201 G.T.
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=-<<I'P I INDIANA D NIIDNIIDAN PDINER DDNIPANYi DONALD C COOK NUCLEAR PLANT>ig g P.O.Box 458, Bridgman, Michigan 49106-'+ill)December 30,-1974 5o-3)5 U.S.Atomic Energy Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Attention:
Mr.J.G.Keppler;Regional Director Gentlemen:
The following is a supplement to Abnormal Occurrence Number AO-050-315/74-09v Prior to commencing the Rod Drop Time Preoperational Test on December 18, 1974, the Intermediate Range Nuclear Instrumentation was placed in service as required by Technical Specifications Table 3.3-1 Number 5.AA review of previous testing which involved closing reactor trip breakers showed that on December 9, 1974, during Protection System Time Response Testing, the breakers were closed without having Intermediate Range Channels in service.CORRECTIVE ACTIONS TAKEN (1)The Intermediate Range Channels were placed in service on 2345 December 18, 1974.(2)It was determined that the health and safety of the public was not jeopardized since the CRDM Motor Generators were not energized while the Reactor Trip Breakers were closed, thus movement of the Control Rods was impossible.
CORRECTIVE STEPS TAKEN TO AVOID RE-OCCURRENCE (1)A change to Surveillance Test Procedure THP 4030 STP.100 was issued which requires Intermediate RangeeChannels to be in operation prior to commencing this test.JAM 2l975 0~~K l U.S.Ato Energy Commission December 30, 1974 Page 2 DATE FULL COMPLIANCE WILL BE ACHIEVED (1)Full compliance has now been achieved (effective 12-18-74).
Respectfully, baf cc: J.E.Dol an R.S.Hunter R.M.Kopper G.E.LeMasters G.E.Lien PNSRC R.J.Vollen BPI K.R.-Baker, Resident Inspector.W.Jurg en Plant Man ger LlCENSEE EVENT REPORT I XII six 7 89 CONTROL OLOCK: 1 (P SE PRINT ALL REQUIRED INFORMlLTION) l R=3O-7g LCENSE EVENT TYPE TYPE LICENSEE NAME LICENSE NUMBER 30 31 32 25 26 14 15 yogCg OO-OoOOO-oo A i i i i~pi REPORT.REPORT[OD1]t'ONT
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80 80 80 80 80 80 7 89 FACILITY Qg c~oo o vz*7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY[gg z.~z 7 8 9 10 11 PERSONNEL EXPOSURES 7 89 11 12 13 PERSONNEL INJURIES~<<L0Dg~67.7 89 11 12 PROBABLE CONSEQUENCES Q~g 7 89 LOSS OR DAMAGE TO FACILITY Q~g g Nh, 7 89 10 PUBLICITY 7 89 ADDITIONAL FACTORS METHOO OF OISCOVERY 44 45 e 46 OISCOVERY OESCRIPTION m SY pe.c.Cepze~NR~VE 80 LOCATION OF RELEASE 44 45 80 80 80 80 80)U TeST-%HAT~SAFGY QoT)EDPARQLZ&D 80 7 8 9 80 7 89 NAME:....I 5-59OL 80 GPO 88 I~8 8T I 4 l h 4 I f T~,I