Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999
Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21
IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
ML20217D9241999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
ML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML20196K5961999-06-30030 June 1999
Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML20207A9201999-05-21021 May 1999
Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML20205P0591999-04-14014 April 1999
Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view] |
Text
CATEGORY1.REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)r'CCESSION NBR:9809160029 DOC.DATE:
98/09/04NOTARIZED:
NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPower.Plant,Unit2,XndianaM05000316 AUTH.NAMEAUTHORAFFILIATION POWERS,R.P.
IndianaMichiganPowerCo.(formerly Indiana&.MichiganEleRECIP.NAME RECIPIENT AFFILIATION RecordsManagement Branch(Document ControlDesk)
SUBJECT:
Submitsaddiinforereliefrequestforthird10-Yrintervalpumpin-service testplan.Proposedalternative beingsubmitted becausecoderequirements forvibration cannotbemetduetocontainment spraypumpsbeingtested.DISTRIBUTION CODE:A047DCOPIESRECEIVED:LTR ENCL'SIZE:TITLE:ORSubmittal:
Inservice/Testing/Relief fromASMECode-GL-89-04NOTES:ATRECIPIENT IDCODE/NAME PD3-3LASTANG,JINTERNAL:
AEOD/SPD/RAB NRR/DE/ECGB OGC/HDS3'ES/DET/EMMEB COPIESLTTRENCL111111111011RECIPIENT IDCODE/NAME PD3-3PDFIECENUDOCS-ABSTRACT RES/DET/EIB COPIESLTTRENCL11111111EXTERNAL:
LITCOANDERSONNRCPDR1111NOAC11DNNOTETOALLnRIDSnRECIPIENTS PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
LTTR13ENCL12 IndianaMichigan~PowerCompany500CircleDriveBuchanan, Ml491071373INOIAiMNICHIGAHIrWMSeptember 4,1998AEP:NRC:0969BM 10CFR50.55aDocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskMailStop0-Pl-17Washington, D.C.20555-0001 Gentlemen:
DonaldC.CookNuclearPlantUnits1and2RELIEFREQUESTFORTHETHIRDTENYEARINTERVALPUMPIN-SERVICE TESTPLANADDITIONAL INFORMATION Thepurposeofthisletteristoproposeanalternative totherequirements ofASMESectionXI,OMa-1988, Part6,paragraph 5.2,Table34forthecontainment spray(CTS)pumps.This~alternative isbeingsubmitted undertheprovisions of10CFR50.55a(a)(3)(ii),
"compliance withthespecified requirements ofthissectionwouldresultinhardshiporunusualdifficulty withoutacompensating increaseinthelevelofqualityorsafety".Theproposedalternative isbeingsubmitted becausethecoderequirements forvibration cannotbemetduetotheCTSpumpsbeingtestedatlowflowconditions andbecauseofthepumps'esign.
Ouroriginalreliefrequestsforthethirdtenyearintervalweresubmitted byletterAEP:NRC:0969AM, datedJune12,1996.ByletterdatedMay27,1997,theNRCdeniedthereliefrequestforthecontainment spraypumps,statingthatinsufficient information wasprovidedintheoriginalrequest.OnJanuary13,1998,andFebruary9,1998,discussions wereheldwithmembersofyourstaffregarding testingoftheseCTSpumps,andarequestforinterimreliefwassubmitted viaAEP:NRC:0969BJ, datedMarch3,1998.Theinterimreliefwasrequested whileamodification wasmadetooursparepumpatthemanufacturer's servicecenter.Themodification tothepumpwasmadeinanattempttoreducethepump'svibration levelsatlowflowsatwhichthevibration dataaretaken.Themodifications, however,didnotsignificantly reducethevibration levelsatlowflow,andpermanent reliefisbeingrequested.
Thepermanent reliefrequestiscontained intheattachment tothisletter.Thereliefrequestcontainstheadditional information theNRCrequested intheMay27,1997,denial.9809160029',980904 PDRADOCK05000315P'DR U.S.NuclearRegulatory Commission Page2AEP:NRC:0969BM Expedited reviewofthisreliefrequestisrequested becausethisreliefisnecessary forrestartofourunits.Sincerely, REPEPowersVicePresident
/jmcAttachments ceJ.A.AbramsonJ.L.Caldwell, w/attachments MDEQ-DW&RPDNRCResidentInspector, w/attachments J.R.Sampson,w/attachments U.S.NuclearRegulatory Commission Page3AEP:NRC:0969BM bc:T.P.Beilman,w/attachments E.R.Eckstein/D.
R.Hafer/K.R.BakerJ.J.EutoFOLIO,w/attachments E.HinesJ.B.Kingseed/M.
S.Ackerman/G.
P.Arent/M.J.GumnsF.R.Pisarsky/B.
B.BradleyJ.F.Stang,Jr.,NRC-Washington, DC,w/attachments ATTACHMENT TOAEP:NRC:0969BM CONTAINMENT SPRAYPUMPRELIEFREQUEST Attachment toAEP:NRC:0969BM Page1~Summa'he CookNuclearPlanthasfourcontainment spray(CTS)pumpsofanoldervintagethatmetthe1983codeedition,butareunabletoconformwiththevibration requirements imposedbythecodeupgradeforthethirdten-yearin-service testinterval.
Theirinability toconformisnotduetodegradedperformance, butratheraconsequence oftheiroriginaldesignandtheirbeingtestedatlowflowconditions.
Amodification wasperformed tothespareassemblyinanefforttoreducelowflowvibrations towithinlimitsspecified, bythecode.Extensive testingofthepre-andpost-modification designwasperformed onthespareCTSpumpwiththeassistance ofthepump'smanufacturer.
Theseeffortsrevealedthatvibrations encountered onpumpsinstalled inthefieldhavesimilarvibration signatures tothesparepumpwhichhadnopreviousruntimeandwasthoroughly inspected priortotesting.Thevibrations experienced weredetermined tobearesultofimpellervanepassduringlowflowconditions.
Thisvibration wasinversely proportional toflowrate,withvibrations decreasing toacceptable limitsatthepump'sdesignflowrating.Althoughsomereduction inpumpvibrations wasachieved, therevisedacceptance limitswerenotmet.Basedontestingperformed itwasconcluded thatfullcompliance withthecodewouldrequireeitheracompletenewtestcircuitcapableofaccommodating fullflow,oraredesigned rotatingelement(e.g.fivevaneimpeller),
whichwouldreducethevanepassfrequency vibration.
Timetoimplement eitheroneoftheseoptionshasbeenestimated atsixtotenmonths.Consequently, theirinstallation wouldresultinasignificant hardshipwithoutacompensating increasein,safety.Therefore, analternate monitoring methodisproposedtomeettheintentofthecode,detection ofpumpdegradation, andtoprovidereasonable assurance ofanacceptable levelofqualityandsafety.Thealternate surveillance specified tomonitorthesafeoperation ofthisequipment adoptsanapproachtoanalyzeavibration signature, orspectrum.
Insteadofanoverallaccumulative
- approach, thevibration signature willbedividedintonarrowbandsoffrequency suchthatspecificformsofincipient degradation canbedetected.
Discussions withthedirectoroftheVibration Institute, membersofASME/ANSI 0&Mworkinggroupforin-service testing,thepumpmanufacturer, andpersonnel fromothernuclearutilities confirmthatspectralanalysisisanacceptable industrypracticeforpredictive maintenance onrotatingmachinery.
Attachment toAEP:NRC:0969BM Page2lnadditiontothealternate testingspecified intheattachedreliefrequest,predictive maintenance, suchasinfraredthermography ofmotorbearingsandspectralmonitoring onthepumpcasings,willbeemployed.
Althoughnotpartofthereliefrequest,theseadditional effortswillfurtherenhancemonitoring oftheCTSpumps.REQUESTNO.1RELIEFREQUESTTHIRDTEN-YEARINTERVALPUMPZN-SERVICE TESTPLANTITLE:Containment SprayPumpVibration LimitsUNITAPPLICABILITY:
Units1and2PUMPNAME:Containment SprayPUMPNUMBER(S):PP-009SYSTEM:Containment Spray(CTS)FLOWDIAGRAM:5144ASMECLASS:2PUMPFUNCTION:
Providecoolingwaterflowtocontainment atmosphere inaLOCAorsteamline break.RELIEFTYPE:ProposedAlternative spraytheASMECODETESTREQUIREMENTS
REFERENCE:
OMa-1988, Part6;paragraph 5.2TestProcedure andtheRangesforVibration TestParameters showninTable3a.CODEREQUIREMENT DESCRIPTION:
Forcentrifugal pumpsrunningat2600rpm,whereV,isthereferenced broadbandunfiltered vibration measurement; Acceptable rangeat52.5V,Alertrange>2.5V,to6V,or>0.325,in/secRequiredactionrange>6V,or>0.70in/secBASISFORCODEALTERNATIVE:
TheCTSpumpsinstalled atCookNuclearPlantvibrateinexcessoftherequiredactionlevelspecified withinTable3aofOMa-1988.Thisisnotduetodegradedperformance, butratherequipment designandthelimitedflowachievable duringsurveillance testing.Baselinetestingofasparepumpassemblyconfirmed thatthevibration decreases withincreasing flow,towithinacceptable limits,asshowninfigure1.TheCTSpumpsareasinglestageunitmountedvertically.
Thepumpshavedualsuctioninadoublevolutecasingequippedwithanimpellerwithanevennumber(4)ofvanes.Theradialclearance "GapB"betweentheimpeller's vanesandeachvolutelipissmall.Thepipingconfiguration onlyallowsthesepumpstobetestedatlowflow,about25%oftheirbestefficiency point.Theresultant flowvectors,whichrepresent fluidleavingthetipofeachvane,arenotinlinewitheithervolute.
Attachment toAEP:NRC:0969BM Page3Consequently, hydraulic shockwavesdevelopatthevanepassfrequency of4timestherunningspeed,or119.38Hz(-7200CPM),asshowninbothfigures2and3.Inanefforttocomplywiththenewcodevibration requirements, amodification wasmadetoourspareassemblyatthepumpmanufacturer's servicecenter.Thisconsisted ofmaximizing the"GapB"clearance bycuttingbackeachcasingdischarge volute.Theobjective wastoreducetheoverallvibration atlowflowtoanacceptable levelwithoutaffecting thehydraulic performance ofthepump.Pre-andpost-modification testresultsareshowninfigures4and5.Figure4illustrates thatthepumphydraulic performance atthedesignflowwasnotaffected.
However,figure5illustrates lessthan1/3ofthedesiredvibration improvement wasachievedataflowrateequivalent totheplant'stestcircuit.Vibration atthedesignflowof3200gpmwasessentially unchanged, remaining withinacceptable limits.Basedonasfoundtestingofthesparepumpassembly, modifications andsubsequent testingresults,itwasconcluded thatliteralcompliance withthenewcodewouldrequireoneofthefollowing options:1)Acompletenewtestcircuittoaccommodate amuchhigherflowrate.2)Adifferent rotatingelementforthepump(e.g.fivevane),whichshouldreducethevanepassfrequency andoverallvibration.
Thefirstoptionmustprovideapproximately 1500gpmadditional flowcapacity, accountforpumpheatgenerated duringthetest,andmeettheoriginaldesignbasisrequirement thattheCTSdischarge headerbemaintained dryfromthetopofbothCTSsprayheatexchangers allthewayintocontainment.
Therearetwomethodstoaccomplish thisoption:A)Toprovidetheflowcapacityandheatremovalcapability withoutfillingtheCTSheatexchanger wouldrequireapproximately 500feetoflargeborepipeperunittorecirculate thewaterfromtherefueling waterstoragetank(RWST).TheroutingofthispipebetweentheRWSTlocatedoutsideintheyard,andeachpumplocatedinthebasementoftheauxiliary
- building, wouldencounter numerousstructural interferences, orB)UseoftheCTSheatexchanger wouldsupportanalternate routecontained entirelywithintheauxiliary building.
However,thisroutewouldrequireadditionofseveralisolation valves,approximately 150feetoflargeborepipingperunit,andadditional ventingcapability.
Itwouldlikelyalsorequireacoderelieftoperformthesurveillance inmode5,becauseofapotential forentraining theairpresentintheCTSdischarge
- header, Attachment toAEP:NRC:0969BM Page4Thesecondoptionistodesignandmanufacture anewimpeller.
Themanufacturer doesnotcurrently haveafivevaneimpellerdesignedforthisapplication, thus,thiswouldrequireextensive development andtesting.Thiswouldaffectthehydraulic performance ofthemachines, andcouldrequirefullflowtestingoftheinstalled pumpstovalidatethedesignchange.Timerequiredtoimplement anyofthepreviously described optionshasbeenestimated atsixtotenmonths.Consequently, theirinstallation wouldresultinasignificant hardshipwithoutacompensating increaseinsafety.Therefore, alternative monitoring isproposedtomeettheintentofthecode,andtoassureanacceptable levelofqualityandsafety.PROPOSEDALTERNATIVE TESTING:Theproposedalternative testingistoperformspectralmonitoring andanalysisoverthefrequency rangespecified inASMEOMa-1988, Part6.Analysisistobeperformed onallfrequencies contained inthefrequency range,alarmingtobeperformed onthefrequencies ofdegradation identified below:~Fundamental TrainFrequency (FTF)~BallSpinFrequency (BSF)~2TimesBallSpinFrequency (2XBSF)~BearingPassOuterRaceFrequency (BPOR)~BearingPassInnerRaceFrequency (BPIR)Thefrequencies forestablishing thealarmsarecontained withinthefollowing tables,including AlertandActionalarmlevels.Thealertandactionalarmlevelswillbebasedonthemaximumpeakvalueofdegradation frequencies contained withineachbandofthebaselinespectralmeasurement.
Bandswhichcontainnodistinctdegradation frequency shallbealarmedusingtheproductof2.5timesand6timesthemaximumpeakvalueofthebaselinespectralmeasurement inaccordance withtable3.aofASMEOMa-1988Part6.
Attachment toAEP:NRC:0969BM Page5DeradationItemFTFBSF2XBSFBPORBPIROutboardMotorBearingFreuenc(Hz)11.51362.475124.9592.106145.83InboardMotorBearingFreuenc(Hz)12.20980.146160.29122.09175.47Alertlevelsperalarmbandnottoexceed0.325ipswithaminimumalarmsettingof0.03ipseActionlevelsperalarmbandnottoexceed0.70ipswithaminimumalarmsettingof0.06ips.Alarmbandsaresettoincludethosefrequencies ofdegradation asfollows:BandMinimumFrequency (Hz)9.8214.8860.99121200600MaximumFrequency (Hz)14.5859.50116.032006001000Itisimportant tonotethattheabovealarmbandscoverallbut6.76Hzofthecoderequiredfrequency range.Those6.76Hznotalarmedincludeonlyvanepass'andlinefrequencies notrelatedtomechanical degradation.
Although6.76Hzofthefrequency rangeisnotalarmed,analysiswillbeperformed onfrequencies withineachunalarmed band.Eachbandischosentoprovidealarmcapability forspecificdegradation frequencies asshownbelow.BandOutboardBearingFTFN/AFTFN/AInboardBearingN/ARPMMachineBSF,BPOR2xBSF,BPIRN/AN/ABSF2xBSF,BPOR,BPIRN/AN/AN/AN/AN/AN/ABands5and6aresettoindicatemultiplesofafundamental defectfrequency, andarenotsettolookforfrequencies ofdegradation thatonlyoccurwithinthosebands.
Attachment toAEP:NRC:0969BM Page6BASISFORCONCLUDING ALTERNATIVE TESTINGYIELDSACCEPTABLE LEVELSOFQUALITYANDSAFETY:Toconfirmthatvibration atvanepassisnotanoperational concernforthesepumps,theplant'sspareassemblywassenttothemanufacturer's facilityforflowlooptesting.Thesparepumphasneverbeeninstalled ortestedin-situ;therefore, itservedasabaselinetojudgehowthiskindofpumpperformswithnoelapsedruntime.CookNuclearPlantpersonnel andtheplant'svibration equipment wereusedduringtestingtoeliminate variables whencomparing testresultstodatacollected ontheinstalled pumps.Xnaddition, aninternalpumpinspection wasperformed verifying allcriticaldimensions tobewithinacceptable tolerances.
Figure2showsthevibration spectrumforthesparemachineasreceivedbythemanufacturer, beforethevolutelipmodification wasperformed.
Thissignature wastakenwhileoperating at733gpm,whichcloselyapproximates thetestconditions attheplant.Thespectrumillustrates thedominance vanepassfrequency hasovertheentirespectrum, withnoevidenceofdegradation atanyotherfrequency.
Figure3isarecentvibration spectrumfortheunit1eastCTSpumptakenduringanin-service test,performed afterroughly22yearsofservice.ThisspectralplotistypicalofthedataobtainedfortheotherCTSpumpsinstalled attheplant.Figures2and3arevirtually identical, confirming thatthevibration component occurring atvanepassfrequency isanexpectedconsequence ofpumpinternaldesignoperating atthein-service testflowrate,andnotanindication ofpumpdegradation.
Fullflowtestingofthesparepumpalsoverifiedthatasflowrateisincreased closertothepump'sbestefficiency point,overallvibration andvanepassfrequency decreasetolevelswellbelowthecodealertvalue.Therefore, overallvibration atflowratesexpectedduringadesignbasisaccidentsatisfycoderequirements (Figure1).Thepumpmanufacturer hasindicated thatvibration occurring atvanepassfrequency doesnotrepresent degradation, norwouldtherebeanymechanical defectsproducedbyoperating atlowflowconditions forshortperiodsoftime,suchasperiodicplantin-'ervice tests.Toconfirmthisassertion, thefourCTSpumpsinstalled attheplantwillbedisassembled andnondestructively examinedforsignsofdegradation priortorestart.Eachpumpmotorwillalsobedisassembled andinspected to'nsureitsbearingshavenotdegraded.
Theseinspections willprovidereasonable assurance thatquarterly testsperformed atlowflowhavenotcauseddegradation andwillestablish anacceptable baselinefortrendingfutureperformance usingtheproposedalternative methods.
Attachment toAEP:NRC:0969BM Page7Vibration monitoring isintendedtodetectchangesinamachine's mechanical performance.
Thecodecurrently requiresabroadbandunfiltered measurement from1/3minimumpumprunningspeeduptoatleast1000Hz.Thistypeofbroadbandmeasurement providesanoverallnumberindicative ofenergycontained withinfrequency range.Itdoesnotindicatethatadiscreetfrequency responsehaschangedand,therefore, cannotprecisely identifywhatformofdegradation maybeincipient.
Tobemoreeffective, vibration monitoring shoulddetectdeviations atdiscreetfrequencies.
Toprovideahigherdegreeofassurance thatnodegradation isoccurring, spectralmonitoring willbeperformed toidentifychangesindiscreetdegradation frequencies.
Spectralmonitoring iscapableofdetermining whichfrequency,-
ifany,hasdeviatedfrombaseline.
Analysisofspectralmeasurements allowsforidentification ofdiscreetfrequencies indicative ofmechanical degradation.
Identification ofthosediscreetdegradation frequencies allowsmoreaccuratemechanical performance
- analysis, andadditional diagnostics arenottypically requiredtoidentifyrootcause.Basedontheabilityofthealternative testingtoidentifyspecificdegradation types,andthatunalarmed frequencies willbeanalyzed, itisconcluded thattheproposedalternative testingprovidesanacceptable levelofqualityandsafety.
Attachment toAEP:NRC:0969BM Page8FigUre1:Vibration AffectedByFlow1.20.8~~>06-.O0I>0.4.Readingsatlowerbearingperpendicular toshaffparallel:with pumpsuction/discharge nozzles(2V)0.20100015002000250030003500400045005000Flow(gpm)
+OverallAsFoundHVanePassAsFound t
Attachment toAEP:NRC:0969BM Page9Figure2:Sparepumponminiflowbeforelipperpendicular toshaftandparallelnozzles(2V).cutatlowerbearingwithsuction/discharge VOTOP444g7200CDIRT~,III2xVohtPSIO>
I~IIIFigure3:Unit1EastCTSonminiflowatlowerbearingperpendicular toshaftandparallelwithsuction/discharge nozzles(2V)measuredon01/25/98.
VOTOPOOLSIIJI2XVihOP4$4IizMz
Attachment toAEP:NRC:0969BM Page10Figure4:Hydraulics AffectedByLipCut600550-500-..=K450400500150025003500I45005500+AsFoundoPostLipCutFlow(gpm}
Attachment toAEP:NRC:0969BM Page11Figure5:Vibration AffectedByLipCut1.20.8VlCL0.6O0.Rea'din'gs atlower.bearihg':p'er'pendlcular toshaft:-:;.'ai allelwith'-pump suetionld1scharge
'noziles(2V)--,0.4-'.2500100015002000250030003500400045005000Flow(gpm)+OverallAsFoundQVanePassAsFound40verallAfterLipCutXVanePassAfterLipCut
