|
|
| (2 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 04/23/1998 | | | issue date = 04/23/1998 |
| | title = LER 98-020-00:on 980408,interim LER - Determined That Containment Recirculation Sump Ph Upper Limit Exceeded. Caused by Analysis Input Omission.Condition Remains Under Evaluation to Determine Appropriate action.W/980423 Ltr | | | title = LER 98-020-00:on 980408,interim LER - Determined That Containment Recirculation Sump Ph Upper Limit Exceeded. Caused by Analysis Input Omission.Condition Remains Under Evaluation to Determine Appropriate action.W/980423 Ltr |
| | author name = KINGSEED J, SAMPSON J R | | | author name = Kingseed J, Sampson J |
| | author affiliation = AMERICAN ELECTRIC POWER CO., INC. | | | author affiliation = AMERICAN ELECTRIC POWER CO., INC. |
| | addressee name = | | | addressee name = |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:eCATEGORYREGULATORY INFORMATION DXSTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9804280038 DOC.DATE: | | {{#Wiki_filter:e CATEGORY REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS) |
| 98/04/23NOTARIZED: | | ACCESSION NBR:9804280038 DOC.DATE: 98/04/23 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTK.NAME AUTHOR AFFILIATION KZAGSEED,J. Indiana Michigan Power Co. |
| NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTK.NAME AUTHORAFFILIATION KZAGSEED,J.
| | SAMPSON,J.R. Indiana Michigan Power Co. |
| IndianaMichiganPowerCo.SAMPSON,J.R.
| | RECIP.NAME RECIPIENT AFFILIATION |
| IndianaMichiganPowerCo.RECIP.NAME RECIPIENT AFFILIATION
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER98-020-00:on 980408,interimLER-determined thatcontainment recirculation sumppHupperlimitexceeded.
| | LER 98-020-00:on 980408, interim LER - determined that containment recirculation sump pH upper limit exceeded. |
| Causedbyanalysisinputomission.
| | Caused by analysis input omission. Condition remains under evaluation to determine appropriate action.W/980423 ltr. |
| Condition remainsunderevaluation todetermine appropriate action.W/980423 ltr.DISTRIBUT10N CODE:ZE22TCOPIESRECEIVED:LTR ENCLSIZE:TXTLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ERECIPIENT IDCODE/NAME PD3-3PDINTERNAL: | | DISTRIBUT10N CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE: |
| .8FILECENTEELBNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRZB RGN3'ILE01EXTERNAL: | | TXTLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES: |
| LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL112211111111111111111111RECIPXENT XDCODE/NAME STANG,JAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL111111'111111111111111DUENNOTETOALL"RIDS"RECIPIENTS:
| | RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: . 8 2 2 AEOD/SPD/RRAB 1 1 FILE CENT 1 1 NRR/DE/ECGB 1 1' EELB 1 1 NRR/DE/EMEB 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRZB 1 1 RES/DET/EIB 1 1 RGN3 'ILE 01 1 1 D |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE, J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U |
| LTTR24ENCL24 IndianaMichiganPowerCompanyaeC'ac<=ace
| | E N |
| 'lIs~a'Iv<~CIMDIAbfANICHIGAMPOSERApril23,1998UnitedStatesNuclearRegulatory Commission DocumentControlDeskWashington, DC20555Operating LicensesDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledthefollowing reportisbeingsubmitted: | | NOTE TO ALL "RIDS" RECIPIENTS: |
| 98-020-00 Sincerely, | | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24 |
| $QJ.R.Sampson.SiteVicePresident lmbdAttachment A.B.Beach,RegionIIIE.E.Fitzpatrick P.A.BarrettS.J.BrewerR.WhaleD.HahnRecordsCenter,INPONRCResidentInspector yV'804280038 980423PDRADOCK050003i58PDR HRCFORH366(5-92)U.S.HUCLEARREGULATORY COMMISSIOH LICENSEEEVENTREPORT(LER),PPROVEOBYOMBHO.3150-0104 EXPIRES5/31/95ESTIMATED BURDENPERRESPONSETOCOMPLYNITHTHIIHFDRHATIDH coLLEGTIDN REGUEsT:50.0HRs.FDRNARCOMMENTSREGARDING BURDENESTIHATEToTHIHFORHATIOH ANDRECORDSMANAGEMENT BRANCH(HNB7714),U.S.NUCLEARREGULATORY COMMISSIONg IIASMINGTOH, DC20555-0001, ANDTOTHEPAPERNORREDUCTION PROJECT(3150-0104),
| | |
| OFFICE0MANAGEHENT ANDBUDGETIIASHINGTOH DC20503.FACILITYNAHE(1)DonaldC.CookNuclearPlant-Unit1DOCKETNUHBER(2)50.315Page1of1TITLE(4)InterimLER-Containment Recirculation SumppHUpperLimitExceededDuetoAnalysisInputOmissionEVENTDATE5LERHUMBER6REPORTDATE7OTHERFACILITIES INVOLVED8MONTHDAYYEARYEAR04089898SEQUENTIAL NUMBER020REVISIONNUMBER00MON'IHOAY0423FACILITYNAMECook-Unit2FACILITYHAMEDOCKETHUHBER50-316DOCKETNUMBEROPERATIHGMODE(9)PONERLEVEL(10)0TH50.73(a)(2)(iii) 50.73a2iv50.73(a)(2)(v) 50.73a2vii50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 20.2203(a)(3)(I) 20.2203a3ii20.2203(a)(4) 50.36c150.36(c)(2) 50.73(a)(2)(I) 73.71(b)73.71o20.2201(b) 20.2203a120.2203(a)(2)(I) 20.2203a2ii20.2203(a)(2)(iii) 20.2203(a)(2)(iv)
| | Indiana Michigan Power Company aeC'ac<=ace |
| OTHER(SpecifyinAbstractbelowandinText,HRCForm366A)20.2203(a)(2)(v) 5073(a)(2)(il) 50'73(a)(2)(x)
| | 'l Is |
| LICENSEECONTACTFORTHISLER12SREPORTISSUBHITTED PURSUANTTOTHEREOUIREMENTS OF10CFR:Checkoneormoe11NAHEMr.JebKingseed, NuclearSafetyAnalysisManagerTELEPHOHE NUMBER(IncludeAreaCode)616697-5106COMPLETEONELINEFOREACHCOMPOHENT FAILUREDESCRIBED INTHISREPORTCAUSESYSTEHCOMPOHEHT MANUFACTURER REPORTABLE TOHPRDSCAUSESYSTEMCOMPONENT MAHUFACTURER REPORTABLE TOHPRDSgyes:;;4):
| | 'I v<~ C ~ |
| SUPPLEHENTAL REPORTEXPECTED14XYES(Ifyes,completeEXPECTEDSUBMISSION DATE).NOEXPECTEDSUBMISSION DATE(15)MONTHDAYYEAR073198ABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten tines)(16)OnApril9,1998,anENSnotification wasmadeinaccordance with10CFR50.72(b)(2)(i), | | a IMDIAbfA NICHIGAM POSER April 23, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager: |
| foracondition whichwasfoundwhilebothunitswereshutdown, whichhaditbeenfoundwhilethereactorwasinoperation, couldhaveresultedinthenuclearplantbeinginanunanalyzed condition.
| | In accordance with the criteria established by 10 CFR 50.73 entitled the following report is being submitted: |
| ThisnotiTication isaresultofanissuediscovered duringasafetysystemfunctional inspection ofthecontainment spraysystem.Ithasbeendetermined thattheWestinghouse methodforcalculating themaximumpHinthecontainment sumpafteranaccidentmightresultinapHthatistoobasic.Whileresponding toanAEPauditquestion, Westinghouse discovered thatthesodiumhydroxide contained withintheicecondenser icebedshadnotbeenincludedinanyoftheBORDERanalysisperformed forCookPlant.BORDERisacomputerprogramusedtodetermine thepHinthecontainment sump.Theimpactofthisisthattheactualcontainment sumppHvaluefollowing atossofcoolantaccidentexceedsthemaximumpHlimitintheBasesforTechnical Specification (T/S)9.5.Preliminary calculations indicateapHvalueofapproximately 9.7ispossible.
| | 98-020-00 Sincerely, J. R. Sampson. |
| TheT/SisbasedonBranchTechnical PositionMTEB6-1onthepHforemergency coolingwaterforPWRs.Thereference statesthatthepHshouldbeinthehighendoftherangeof7.0to9.5forgreaterassurance thatstresscorrosion crackingwillnotoccur.Thereference doesnotgiveanyguidanceonwhattheaffectswouldbeif9.5isexceeded, thustheunanalyzed condition.
| | $ Q Site Vice President lmbd Attachment A. B. Beach, Region III E. E. Fitzpatrick P. A. Barrett S. J. Brewer R. Whale D. Hahn Records Center, INPO NRC Resident Inspector yV'804280038 980423 PDR ADOCK 050003i5 8 PDR |
| Thesignificance oftheimpactofthepHabovetherangeintheT/Srequiresfurtherevaluation.
| | |
| Thiscondition remainsunderevaluation todetermine appropriate actiontorectifythisissue.Additionally, thisissueisbeingevaluated forpotential 10CFRPart21reportability.
| | HRC FORH 366 U.S. HUCLEAR REGULATORY COMMISSIOH , PPROVEO BY OMB HO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY NITH THI IHFDRHATIDH coLLEGTIDN REGUEsT: 50.0 HRs. FDRNAR LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIHATE To TH IHFORHATIOH AND RECORDS MANAGEMENT BRANCH (HNB 7714), U.S. NUCLEAR REGULATORY COMMISSIONg IIASMINGTOH, DC 20555-0001, AND TO THE PAPERNOR REDUCTION PROJECT (3150-0104), OFFICE 0 MANAGEHENT AND BUDGET IIASHINGTOH DC 20503. |
| AnupdatetothisinterimLERwillbesubmitted byJuly31,1998.}}
| | FACILITY NAHE (1) (2) |
| | Donald C. Cook Nuclear Plant - Unit 1 DOCKET NUHBER Page1 of1 50.315 TITLE (4) |
| | Interim LER -Containment Recirculation Sump pH Upper Limit Exceeded Due to Analysis Input Omission EVENT DATE 5 LER HUMBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 SEQUENTIAL REVISION FACILITY NAME DOCKET HUHBER MONTH DAY YEAR YEAR MON'IH NUMBER NUMBER OAY Cook - Unit 2 50-316 FACILITY HAME DOCKET NUMBER 04 08 98 98 020 00 04 23 OPERAT IHG TH S REPORT IS SUBHITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR : Check one or mo e 11 MODE (9) 20.2201(b) 20.2203(a)(3)(I) 50.73(a)(2)(iii) 73.71(b) |
| | PONER 0 |
| | 20.2203 a 1 20.2203 a 3 ii 50.73 a 2 iv 73.71o LEVEL (10) 20.2203(a)(2)(I) 20.2203(a)(4) 50.73(a)(2)(v) OTHER 20.2203 a 2 ii 50.36 c 1 50.73 a 2 vii (Specify in 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(viii)(A) Abstract below 20.2203(a)(2)(iv) 50.73(a)(2)(I) 50.73(a)(2)(viii)(B) and in Text, HRC Form 366A) 20.2203(a)(2)(v) 50 73(a)(2)(il) 50'73(a)(2)(x) |
| | LICENSEE CONTACT FOR THIS LER 12 NAHE TELEPHOHE NUMBER (Include Area Code) |
| | Mr. Jeb Kingseed, Nuclear Safety Analysis Manager 616 697-5106 COMPLETE ONE LINE FOR EACH COMPOHENT FAILURE DESCRIBED IN THIS REPORT REPORTABLE REPORTABLE CAUSE SYSTEH COMPOHEHT MANUFACTURER CAUSE SYSTEM COMPONENT MAHUFACTURER TO HPRDS TO HPRDS gyes:;;4): |
| | SUPPLEHENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR YES SUBMISSION X (If yes, complete NO 07 31 98 EXPECTED SUBMISSION DATE). DATE (15) |
| | ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten tines) (16) |
| | On April 9, 1998, an ENS notification was made in accordance with 10 CFR 50.72(b)(2)(i), for a condition which was found while both units were shutdown, which had it been found while the reactor was in operation, could have resulted in the nuclear plant being in an unanalyzed condition. This notiTication is a result of an issue discovered during a safety system functional inspection of the containment spray system. |
| | It has been determined that the Westinghouse method for calculating the maximum pH in the containment sump after an accident might result in a pH that is too basic. While responding to an AEP audit question, Westinghouse discovered that the sodium hydroxide contained within the ice condenser ice beds had not been included in any of the BORDER analysis performed for Cook Plant. BORDER is a computer program used to determine the pH in the containment sump. The impact of this is that the actual containment sump pH value following a toss of coolant accident exceeds the maximum pH limit in the Bases for Technical Specification (T/S) 9.5. Preliminary calculations indicate a pH value of approximately 9.7 is possible. The T/S is based on Branch Technical Position MTEB 6-1 on the pH for emergency cooling water for PWRs. The reference states that the pH should be in the high end of the range of 7.0 to 9.5 for greater assurance that stress corrosion cracking will not occur. The reference does not give any guidance on what the affects would be if 9.5 is exceeded, thus the unanalyzed condition. The significance of the impact of the pH above the range in the T/S requires further evaluation. |
| | This condition remains under evaluation to determine appropriate action to rectify this issue. Additionally, this issue is being evaluated for potential 10CFR Part 21 reportability. An update to this interim LER will be submitted by July 31, 1998.}} |
Similar Documents at Cook |
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
ML17335A5171999-02-11011 February 1999
LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted
ML17335A5141999-02-10010 February 1999
LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405
ML17335A5011999-02-0101 February 1999
LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr
ML17335A4951999-01-29029 January 1999
LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr
ML17335A4961999-01-27027 January 1999
LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr
ML17335A4921999-01-19019 January 1999
LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components
ML17335A4721999-01-0606 January 1999
LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing
ML17335A4691999-01-0606 January 1999
LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr
ML17335A4661999-01-0505 January 1999
LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing
ML17335A4631999-01-0404 January 1999
LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr
ML17335A4481998-12-30030 December 1998
LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr
ML17335A4581998-12-28028 December 1998
LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process
ML17335A4281998-12-22022 December 1998
LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event
ML17335A4111998-12-17017 December 1998
LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr
ML17335A4141998-12-16016 December 1998
LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122
ML17335A4181998-12-16016 December 1998
LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria
ML17335A3871998-12-11011 December 1998
LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing
ML17335A3821998-12-0808 December 1998
LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr
ML17335A3781998-12-0707 December 1998
LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr
ML17335A3771998-12-0303 December 1998
LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned
ML17335A3741998-12-0202 December 1998
LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3
1999-09-17
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999
LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr
ML17335A5531999-10-0707 October 1999
LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented
ML17335A5631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr
ML17335A5621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr
ML17335A5481999-09-30030 September 1999
Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3).
ML17335A5451999-09-28028 September 1999
Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios.
ML17326A1291999-09-17017 September 1999
LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary
ML17326A1481999-09-17017 September 1999
Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2.
ML17326A1211999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr
ML17326A1201999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr
ML17326A1121999-08-27027 August 1999
LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed
ML17326A1011999-08-26026 August 1999
LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs
ML17326A0911999-08-16016 August 1999
LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4
ML17326A0771999-08-0404 August 1999
LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830
ML17335A5461999-08-0202 August 1999
Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates.
ML17326A0871999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr
ML17326A0861999-07-31031 July 1999
Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr
ML17326A0741999-07-29029 July 1999
LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves
ML17326A0661999-07-26026 July 1999
LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr
ML17326A0651999-07-22022 July 1999
LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis
ML17326A0491999-07-13013 July 1999
LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr
ML17326A0331999-07-0101 July 1999
LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written
ML17326A0511999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr
ML17326A0501999-06-30030 June 1999
Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr
ML17326A0151999-06-18018 June 1999
LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified
ML17325B6421999-06-0101 June 1999
LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed
ML17325B6311999-06-0101 June 1999
LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions
ML17326A0061999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr
ML17326A0071999-05-31031 May 1999
Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr
ML17325B6351999-05-28028 May 1999
LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions
ML17265A8231999-05-24024 May 1999
LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made
ML17325B6001999-05-20020 May 1999
LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed
ML17325B5861999-05-10010 May 1999
LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised
ML17325B5811999-05-0404 May 1999
LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared
ML17325B5771999-05-0303 May 1999
LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design
ML17335A5301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr
ML17335A5291999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr
ML17325B5581999-04-16016 April 1999
LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold
ML17325B5471999-04-12012 April 1999
LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation
ML17325B5321999-04-0707 April 1999
LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate
ML17325B5161999-04-0101 April 1999
LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures
ML17325B5491999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr
ML17325B5441999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr
ML17325B5221999-03-29029 March 1999
LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing
ML17325B4801999-03-18018 March 1999
LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling
ML17325B4741999-03-18018 March 1999
LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed
ML17325B5671999-03-0202 March 1999
Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218.
ML17325B4631999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr
ML17325B4621999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr
ML17325B4571999-02-24024 February 1999
LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors
1999-09-30
[Table view] |
Text
e CATEGORY REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9804280038 DOC.DATE: 98/04/23 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTK.NAME AUTHOR AFFILIATION KZAGSEED,J. Indiana Michigan Power Co.
SAMPSON,J.R. Indiana Michigan Power Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 98-020-00:on 980408, interim LER - determined that containment recirculation sump pH upper limit exceeded.
Caused by analysis input omission. Condition remains under evaluation to determine appropriate action.W/980423 ltr.
DISTRIBUT10N CODE: ZE22T COPIES RECEIVED:LTR ENCL SIZE:
TXTLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. E NOTES:
RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD3-3 PD 1 1 STANG,J 1 1 INTERNAL: . 8 2 2 AEOD/SPD/RRAB 1 1 FILE CENT 1 1 NRR/DE/ECGB 1 1' EELB 1 1 NRR/DE/EMEB 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRCH/HQMB 1 1 NRR/DRPM/PECB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRZB 1 1 RES/DET/EIB 1 1 RGN3 'ILE 01 1 1 D
EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE, J H 1 1 NOAC POORE,W. 1 1 NOAC QUEENER,DS 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 U
E N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 24
Indiana Michigan Power Company aeC'ac<=ace
'l Is
'I v<~ C ~
a IMDIAbfA NICHIGAM POSER April 23, 1998 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Operating Licenses DPR-58 Docket No. 50-315 Document Control Manager:
In accordance with the criteria established by 10 CFR 50.73 entitled the following report is being submitted:
98-020-00 Sincerely, J. R. Sampson.
$ Q Site Vice President lmbd Attachment A. B. Beach, Region III E. E. Fitzpatrick P. A. Barrett S. J. Brewer R. Whale D. Hahn Records Center, INPO NRC Resident Inspector yV'804280038 980423 PDR ADOCK 050003i5 8 PDR
HRC FORH 366 U.S. HUCLEAR REGULATORY COMMISSIOH , PPROVEO BY OMB HO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY NITH THI IHFDRHATIDH coLLEGTIDN REGUEsT: 50.0 HRs. FDRNAR LICENSEE EVENT REPORT (LER) COMMENTS REGARDING BURDEN ESTIHATE To TH IHFORHATIOH AND RECORDS MANAGEMENT BRANCH (HNB 7714), U.S. NUCLEAR REGULATORY COMMISSIONg IIASMINGTOH, DC 20555-0001, AND TO THE PAPERNOR REDUCTION PROJECT (3150-0104), OFFICE 0 MANAGEHENT AND BUDGET IIASHINGTOH DC 20503.
FACILITY NAHE (1) (2)
Donald C. Cook Nuclear Plant - Unit 1 DOCKET NUHBER Page1 of1 50.315 TITLE (4)
Interim LER -Containment Recirculation Sump pH Upper Limit Exceeded Due to Analysis Input Omission EVENT DATE 5 LER HUMBER 6 REPORT DATE 7 OTHER FACILITIES INVOLVED 8 SEQUENTIAL REVISION FACILITY NAME DOCKET HUHBER MONTH DAY YEAR YEAR MON'IH NUMBER NUMBER OAY Cook - Unit 2 50-316 FACILITY HAME DOCKET NUMBER 04 08 98 98 020 00 04 23 OPERAT IHG TH S REPORT IS SUBHITTED PURSUANT TO THE REOUIREMENTS OF 10 CFR : Check one or mo e 11 MODE (9) 20.2201(b) 20.2203(a)(3)(I) 50.73(a)(2)(iii) 73.71(b)
PONER 0
20.2203 a 1 20.2203 a 3 ii 50.73 a 2 iv 73.71o LEVEL (10) 20.2203(a)(2)(I) 20.2203(a)(4) 50.73(a)(2)(v) OTHER 20.2203 a 2 ii 50.36 c 1 50.73 a 2 vii (Specify in 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(viii)(A) Abstract below 20.2203(a)(2)(iv) 50.73(a)(2)(I) 50.73(a)(2)(viii)(B) and in Text, HRC Form 366A) 20.2203(a)(2)(v) 50 73(a)(2)(il) 50'73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER 12 NAHE TELEPHOHE NUMBER (Include Area Code)
Mr. Jeb Kingseed, Nuclear Safety Analysis Manager 616 697-5106 COMPLETE ONE LINE FOR EACH COMPOHENT FAILURE DESCRIBED IN THIS REPORT REPORTABLE REPORTABLE CAUSE SYSTEH COMPOHEHT MANUFACTURER CAUSE SYSTEM COMPONENT MAHUFACTURER TO HPRDS TO HPRDS gyes:;;4):
SUPPLEHENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR YES SUBMISSION X (If yes, complete NO 07 31 98 EXPECTED SUBMISSION DATE). DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten tines) (16)
On April 9, 1998, an ENS notification was made in accordance with 10 CFR 50.72(b)(2)(i), for a condition which was found while both units were shutdown, which had it been found while the reactor was in operation, could have resulted in the nuclear plant being in an unanalyzed condition. This notiTication is a result of an issue discovered during a safety system functional inspection of the containment spray system.
It has been determined that the Westinghouse method for calculating the maximum pH in the containment sump after an accident might result in a pH that is too basic. While responding to an AEP audit question, Westinghouse discovered that the sodium hydroxide contained within the ice condenser ice beds had not been included in any of the BORDER analysis performed for Cook Plant. BORDER is a computer program used to determine the pH in the containment sump. The impact of this is that the actual containment sump pH value following a toss of coolant accident exceeds the maximum pH limit in the Bases for Technical Specification (T/S) 9.5. Preliminary calculations indicate a pH value of approximately 9.7 is possible. The T/S is based on Branch Technical Position MTEB 6-1 on the pH for emergency cooling water for PWRs. The reference states that the pH should be in the high end of the range of 7.0 to 9.5 for greater assurance that stress corrosion cracking will not occur. The reference does not give any guidance on what the affects would be if 9.5 is exceeded, thus the unanalyzed condition. The significance of the impact of the pH above the range in the T/S requires further evaluation.
This condition remains under evaluation to determine appropriate action to rectify this issue. Additionally, this issue is being evaluated for potential 10CFR Part 21 reportability. An update to this interim LER will be submitted by July 31, 1998.
