|
|
| Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED DISTMBUTION DEMONSTPWTION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)DOCKET0500031505000316ID | | {{#Wiki_filter:ACCELERATED DISTMBUTION DEMONSTPWTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET 05000315 05000316 I D |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Forwardsmarkeduptable,providedasattachment to881005ltr,reflecting relaxation ofqualification requirements ofaccumulator level&pressuremonitoring instrumentation fromRegGuide1.97Category2toCategory3.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
| | Forwards marked up table, provided as attachment to 881005 ltr,reflecting relaxation of qualification requirements of accumulator level&pressure monitoring instrumentation from Reg Guide 1.97 Category 2 to Category 3.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: |
| GeneralDistribution NOTES:ACCESSION NBR:9405100084 DOC.DATE:
| | General Distribution NOTES: ACCESSION NBR:9405100084 DOC.DATE: 94/04/29 NOTARIZED: |
| 94/04/29NOTARIZED: | | NO FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,J. |
| NOFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,J.
| | Indiana Michigan Power Co.(formerly Indiana&Michigan Ele 8 RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T. |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEle8RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T.
| | Document Control Branch (Document Control Desk)RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPW NRR/DSSA/SRXB OC LFDCB E 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS: |
| DocumentControlBranch(Document ControlDesk)RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
| | D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.2N79)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 Indiana hlHchigan Power Company P.O.Box 16631 Columbus, OH 43216 II AEP:NRC:0773AP Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 REGULATORY GUIDE 1.97 ACCUMULATOR VOLUME AND PRESSURE U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: W.T.Russell April 29, 1994. |
| NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2EXTERNAL: | |
| NRCPDRCOPIESLTTRENCL1122111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DORS/OTS BNRR/DRPWNRR/DSSA/SRXB OCLFDCBE01NSICCOPIESLTTRENCL11111111101111DDDNOTETOALL"RIDS"RECIPIENTS:
| |
| DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.2N79)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| |
| LTTR16ENCL14 IndianahlHchigan PowerCompanyP.O.Box16631Columbus, OH43216IIAEP:NRC:0773AP DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74REGULATORY GUIDE1.97ACCUMULATOR VOLUMEANDPRESSUREU.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:W.T.RussellApril29,1994.
| |
|
| |
|
| ==DearMr.Russell:== | | ==Dear Mr.Russell:== |
| ThisletterisinregardtotheSafetyEvaluation (SE)performed onrelaxingthequalification requirements ofaccumulator levelandpressuremonitoring instrumentation, fromRegulatory Guide1.97Category2toCategory3,preparedanddistributed byyourstaffinalettertoIndianaMichiganPowerCompany,datedNovember17,1993.Thatletter,further,requested thatyoubenotifiedoftheactionsweplantotakeandourscheduleforimplementation.
| | This letter is in regard to the Safety Evaluation (SE)performed on relaxing the qualification requirements of accumulator level and pressure monitoring instrumentation, from Regulatory Guide 1.97 Category 2 to Category 3, prepared and distributed by your staff in a letter to Indiana Michigan Power Company, dated November 17, 1993.That letter, further, requested that you be notified of the actions we plan to take and our schedule for implementation. |
| Atthistimeourintendedactions,whicharecompleted withthissubmittal, aretoremovetheseinstruments fromourenvironmental qualification (EQ)programandtochangethequalification requirements oftheseinstruments fromCategory2toCategory3onthetablethatwasprovidedtoyouasanattachment toourletterAEP:NRC:0773AB, datedOctober5,1988.Amarkedupcopyofthattable,margin-marked forquickreference, isprovidedasanattachment tothisletter.Astofutureaction(s),
| | At this time our intended actions, which are completed with this submittal, are to remove these instruments from our environmental qualification (EQ)program and to change the qualification requirements of these instruments from Category 2 to Category 3 on the table that was provided to you as an attachment to our letter AEP:NRC:0773AB, dated October 5, 1988.A marked up copy of that table, margin-marked for quick reference, is provided as an attachment to this letter.As to future action(s), while these instruments will be maintained on their current surveillance/calibration frequency, they will not be changed out unless they fail or become a high maintenance problem, at which time we would most likely opt to substitute instruments that meet Regulatory Guide 1~97 Category 3 qualification requirements. |
| whiletheseinstruments willbemaintained ontheircurrentsurveillance/calibration frequency, theywillnotbechangedoutunlesstheyfailorbecomeahighmaintenance problem,atwhichtimewewouldmostlikelyopttosubstitute instruments thatmeetRegulatory Guide1~97Category3qualification requirements.
| | Sincerely, r'.E.Fitzpatrick Vice President eh QGGQ3.6--.F'DR o084 940Sg 0~DOCK 0S04>9.,S000ggS------F.'DR'0 |
| Sincerely, r'.E.Fitzpatrick VicePresident ehQGGQ3.6-- | | 'Op 0 Mr.W.T.Russell-2-AEP:NRC:0773AP Attachment cc: A.A.Blind G.Charnoff J.B.Martin-Region III NFEM Section Chief NRC Resident Inspector J.R.Padgett Attachment to AEP:NRC:0773AP MARKED UP COPY OF AEP:NRC:0773AB AND REVISED PAGE OF SAME LETTER Typo D Variables: "those variables that provide information to indicate tho oporation of individual safety systems and other systems important to safety.Those variables azo to help the operator hake appropriate decisions in using the individual system important to safety in mitigating the consequences of an accident." Note: The schedule and status for each instzument is for when all the applicable rsco~ndations of Regulatory Guide 1.97 Rev.3 will be met.Item No~Purpose D-1 RHR system Variable U-l Schedule RHR system 2 flow IFI-310o311 320,321 0-1500 GPM A NA A NA NA 1500-5000 GPM Control Room Panel RHR No action required Sss NA footnotes ()))&(mzm)(Deviation No.DV-3)Cat.Tag Nos Rango E S Q S P Display Remarks/Action Req'd Q Q A F S Location U-2 Schedule NA D 2 RHR heat 2 sxchangoz outlet tempezature ITI-310 o 320 0-4000F A NAA NA NA Control Room Panel RHR No Further action zequired CMPLT Sss footnote (ii)(Deviation No.s DV-1&DV-3)CMPLT D-3a SI System Accumulator 3 tank lovel ZLA-110, 111, 120,121o130 131gl40~141 4.148 to NA NA NA NA NA 120.8 in.(wide range)(52%of total volume)104.15 to 120.8 in (narrow range)(7.5%of total volume)Control Room Panel SIS No further action required Category requirements relaxed to categozy 3 as stated in SER provided by the NRC dated Nov.17, 1993 CMPLT CMPLT D-3b Accumulator 3 Tank pressure IPA-110olllo 120, 121, 130, 131 o 140 o 141 0-800 psig NA NA NA NA NA Contxol Room Panel SIS No further action rsquized Category requirements relaxed to categazy 3 as stated in SER provided by ths NRC dated Nav.17, 1993.CMPLT CMPLT D-4 D-5 D-6 D-7 Accumulator 2 Tank Zsolation valve position Boric acid Charging flow Flow in HPZ system Flow in IPZ system IM3-110,120, 130, 140 closed or open NANAA NANA Contzol Room Panel SIS None required see footnote NA (r)&(kk)(Deviation No.3)See item D-24 See item A-1 See item D-1 NA D-8 D-9 Primazy coolant system RWST lovel RCP status Ql,Q2,Q3,Q4 0 1200 A NA NA NA NA NA Control Room Panel RCP Sse item A-16 No action required NA NA D-10 Primary system 2 safety relief valve positions or flow thru or pressure in relief lines.QR-107 AOBo NA CoD A NA A NA NA Control Room Panel RC No action required sse footnote (b)(Deviation No.s DV-1&DV 3)NA NA D-11 Pzessurizor lovel See item A-10 D-12 Pressurizer 2 heater status Group Al,A2, on/off A3,C1,C2,C3 NA NA A NA NA Control Room Panel PRE No action zoquired ses faotnotss (d)&(ll)(Deviation No.DV-3)NA NA For Definition af"A" See Section 3.0 hvtaCnmenl. |
| .F'DRo084940Sg0~DOCK0S04>9.,S000ggS------F.'DR'0 | | to hbI'NKC:U//DAB Page 3/Type D Variables: |
| 'Op0Mr.W.T.Russell-2-AEP:NRC:0773AP Attachment cc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector J.R.Padgett Attachment toAEP:NRC:0773AP MARKEDUPCOPYOFAEP:NRC:0773AB ANDREVISEDPAGEOFSAMELETTER TypoDVariables: | | II those variables that provide information to indicate the operation of individual safety systems and other systems important to, safety.These variables are to help the operator make appropriate decisions in using the individual systems important to safety in mitigating the consequences of an accident." Note: The schedule and status for each.instrument is for when all of the appllcableg recommendations of Regulatory Guide 1.97, Rev 3 will be met.Item Purpose No.Variable Cat.Tag Nos.Range Remarks/Action Req'd E S g S P Display V-l V-2 h F S Location Schedule Schedule D-1 RHR System RHR System 2 Flow IFI-310 311, 320,321 0-1500 GPM A 1500-5000 GPM Nh A NA Nh Control Room No Action Required Panel RHR See footnotes ()))&(mmm)(Deviation No.DV-3)NA NA D-2 RHR Heat Ex-2 change Out-let Temp ITI-310,320 0-400'F A NA A NA NA Control Room Panel RHR No further action required (See footnote (ii)(Deviation No.s DV-1,&DV-3)CMPLT CMPI.T D-3a SI Systems Accumulator |
| "thosevariables thatprovideinformation toindicatethooporation ofindividual safetysystemsandothersystemsimportant tosafety.Thosevariables azotohelptheoperatorhakeappropriate decisions inusingtheindividual systemimportant tosafetyinmitigating theconsequences ofanaccident." | | /ILA-110,111 Tank l.evel~120,121, 130,131, 140,141 4.148 to A 120.8 in.(wide range)(52X of Total Volume)104.15 to 120.8 in.(narrow range)(7.5X of Total Volume)NA A NA NA Control Room Panel SIS Replace the wide range 1989 re-1990 re-transmitter each tank fueling fueling with,env. |
| Note:Thescheduleandstatusforeachinstzument isforwhenalltheapplicable rsco~ndations ofRegulatory Guide1.97Rev.3willbemet.ItemNo~PurposeD-1RHRsystemVariableU-lScheduleRHRsystem2flowIFI-310o311 320,3210-1500GPMANAANANA1500-5000 GPMControlRoomPanelRHRNoactionrequiredSssNAfootnotes | | qual.equipment outage outage See footnotes (iii)qualification shall apply to the wide range instruments only.(Deviation No.s DV-I, 6 (DV-3)D-3b Accumulator Tank Pres-sure IPA-110,111, 120,121, 130,131, 140,141 0-800 psig A NA h NA NA Control Room Replace one transmitter/ |
| ()))&(mzm)(Deviation No.DV-3)Cat.TagNosRangoESQSPDisplayRemarks/Action Req'dQQAFSLocationU-2ScheduleNAD2RHRheat2sxchangoz outlettempezature ITI-310o3200-4000FANAANANAControlRoomPanelRHRNoFurtheractionzequiredCMPLTSssfootnote(ii)(Deviation No.sDV-1&DV-3)CMPLTD-3aSISystemAccumulator 3tanklovelZLA-110,111,120,121o130 131gl40~141 4.148toNANANANANA120.8in.(widerange)(52%oftotalvolume)104.15to120.8in(narrowrange)(7.5%oftotalvolume)ControlRoomPanelSISNofurtheractionrequiredCategoryrequirements relaxedtocategozy3asstatedinSERprovidedbytheNRCdatedNov.17,1993CMPLTCMPLTD-3bAccumulator 3TankpressureIPA-110olllo 120,121,130,131o140o1410-800psigNANANANANAContxolRoomPanelSISNofurtheractionrsquizedCategoryrequirements relaxedtocategazy3asstatedinSERprovidedbythsNRCdatedNav.17,1993.CMPLTCMPLTD-4D-5D-6D-7Accumulator 2TankZsolation valvepositionBoricacidChargingflowFlowinHPZsystemFlowinIPZsystemIM3-110,120, 130,140closedoropenNANAANANAContzolRoomPanelSISNonerequiredseefootnoteNA(r)&(kk)(Deviation No.3)SeeitemD-24SeeitemA-1SeeitemD-1NAD-8D-9PrimazycoolantsystemRWSTlovelRCPstatusQl,Q2,Q3,Q4 01200ANANANANANAControlRoomPanelRCPSseitemA-16NoactionrequiredNANAD-10Primarysystem2safetyreliefvalvepositions orflowthruorpressureinrelieflines.QR-107AOBoNACoDANAANANAControlRoomPanelRCNoactionrequiredssefootnote(b)(Deviation No.sDV-1&DV3)NANAD-11Pzessurizor lovelSeeitemA-10D-12Pressurizer 2heaterstatusGroupAl,A2,on/offA3,C1,C2,C3 NANAANANAControlRoomPanelPRENoactionzoquiredsesfaotnotss (d)&(ll)(Deviation No.DV-3)NANAForDefinition af"A"SeeSection3.0 hvtaCnmenl. | | 1989 re-1990 re-Panel SIS tank with env.qualified fueling fueling equipment. |
| tohbI'NKC:U//DAB Page3/TypeDVariables:
| | qualification outage outage shall apply to only one instrument/tank.(Deviation No.s DV-l, 6 DV-3)D-4 Accumulator 2 Tank Isola-tion Valve Position IM0-110,120, 130 I 140 Closed or Open NA NA A Nh NA Control Room None Required Panel SIS See footnote (r)&(kk)(Deviation No.3)Nh NA For Definition of"A" See Section 3.0}} |
| IIthosevariables thatprovideinformation toindicatetheoperation ofindividual safetysystemsandothersystemsimportant to,safety.Thesevariables aretohelptheoperatormakeappropriate decisions inusingtheindividual systemsimportant tosafetyinmitigating theconsequences ofanaccident."
| |
| Note:Thescheduleandstatusforeach.instrument isforwhenalloftheappllcableg recommendations ofRegulatory Guide1.97,Rev3willbemet.ItemPurposeNo.VariableCat.TagNos.RangeRemarks/Action Req'dESgSPDisplayV-lV-2hFSLocationScheduleScheduleD-1RHRSystemRHRSystem2FlowIFI-310311,320,3210-1500GPMA1500-5000 GPMNhANANhControlRoomNoActionRequiredPanelRHRSeefootnotes | |
| ()))&(mmm)(Deviation No.DV-3)NANAD-2RHRHeatEx-2changeOut-letTempITI-310,320 0-400'FANAANANAControlRoomPanelRHRNofurtheractionrequired(Seefootnote(ii)(Deviation No.sDV-1,&DV-3)CMPLTCMPI.TD-3aSISystemsAccumulator | |
| /ILA-110,111 Tankl.evel~120,121,130,131,140,1414.148toA120.8in.(widerange)(52XofTotalVolume)104.15to120.8in.(narrowrange)(7.5XofTotalVolume)NAANANAControlRoomPanelSISReplacethewiderange1989re-1990re-transmitter eachtankfuelingfuelingwith,env. | |
| qual.equipment outageoutageSeefootnotes (iii)qualification shallapplytothewiderangeinstruments only.(Deviation No.sDV-I,6(DV-3)D-3bAccumulator TankPres-sureIPA-110,111, 120,121,130,131,140,1410-800psigANAhNANAControlRoomReplaceonetransmitter/ | |
| 1989re-1990re-PanelSIStankwithenv.qualified fuelingfuelingequipment.
| |
| qualification outageoutageshallapplytoonlyoneinstrument/tank. | |
| (Deviation No.sDV-l,6DV-3)D-4Accumulator 2TankIsola-tionValvePositionIM0-110,120, 130I140ClosedorOpenNANAANhNAControlRoomNoneRequiredPanelSISSeefootnote(r)&(kk)(Deviation No.3)NhNAForDefinition of"A"SeeSection3.0}} | |
Similar Documents at Cook |
|---|
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
ACCELERATED DISTMBUTION DEMONSTPWTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET 05000315 05000316 I D
SUBJECT:
Forwards marked up table, provided as attachment to 881005 ltr,reflecting relaxation of qualification requirements of accumulator level&pressure monitoring instrumentation from Reg Guide 1.97 Category 2 to Category 3.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
General Distribution NOTES: ACCESSION NBR:9405100084 DOC.DATE: 94/04/29 NOTARIZED:
NO FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,J.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele 8 RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T.
Document Control Branch (Document Control Desk)RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPW NRR/DSSA/SRXB OC LFDCB E 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.2N79)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 Indiana hlHchigan Power Company P.O.Box 16631 Columbus, OH 43216 II AEP:NRC:0773AP Donald C.Cook Nuclear Plant Units 1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 REGULATORY GUIDE 1.97 ACCUMULATOR VOLUME AND PRESSURE U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: W.T.Russell April 29, 1994.
Dear Mr.Russell:
This letter is in regard to the Safety Evaluation (SE)performed on relaxing the qualification requirements of accumulator level and pressure monitoring instrumentation, from Regulatory Guide 1.97 Category 2 to Category 3, prepared and distributed by your staff in a letter to Indiana Michigan Power Company, dated November 17, 1993.That letter, further, requested that you be notified of the actions we plan to take and our schedule for implementation.
At this time our intended actions, which are completed with this submittal, are to remove these instruments from our environmental qualification (EQ)program and to change the qualification requirements of these instruments from Category 2 to Category 3 on the table that was provided to you as an attachment to our letter AEP:NRC:0773AB, dated October 5, 1988.A marked up copy of that table, margin-marked for quick reference, is provided as an attachment to this letter.As to future action(s), while these instruments will be maintained on their current surveillance/calibration frequency, they will not be changed out unless they fail or become a high maintenance problem, at which time we would most likely opt to substitute instruments that meet Regulatory Guide 1~97 Category 3 qualification requirements.
Sincerely, r'.E.Fitzpatrick Vice President eh QGGQ3.6--.F'DR o084 940Sg 0~DOCK 0S04>9.,S000ggS------F.'DR'0
'Op 0 Mr.W.T.Russell-2-AEP:NRC:0773AP Attachment cc: A.A.Blind G.Charnoff J.B.Martin-Region III NFEM Section Chief NRC Resident Inspector J.R.Padgett Attachment to AEP:NRC:0773AP MARKED UP COPY OF AEP:NRC:0773AB AND REVISED PAGE OF SAME LETTER Typo D Variables: "those variables that provide information to indicate tho oporation of individual safety systems and other systems important to safety.Those variables azo to help the operator hake appropriate decisions in using the individual system important to safety in mitigating the consequences of an accident." Note: The schedule and status for each instzument is for when all the applicable rsco~ndations of Regulatory Guide 1.97 Rev.3 will be met.Item No~Purpose D-1 RHR system Variable U-l Schedule RHR system 2 flow IFI-310o311 320,321 0-1500 GPM A NA A NA NA 1500-5000 GPM Control Room Panel RHR No action required Sss NA footnotes ()))&(mzm)(Deviation No.DV-3)Cat.Tag Nos Rango E S Q S P Display Remarks/Action Req'd Q Q A F S Location U-2 Schedule NA D 2 RHR heat 2 sxchangoz outlet tempezature ITI-310 o 320 0-4000F A NAA NA NA Control Room Panel RHR No Further action zequired CMPLT Sss footnote (ii)(Deviation No.s DV-1&DV-3)CMPLT D-3a SI System Accumulator 3 tank lovel ZLA-110, 111, 120,121o130 131gl40~141 4.148 to NA NA NA NA NA 120.8 in.(wide range)(52%of total volume)104.15 to 120.8 in (narrow range)(7.5%of total volume)Control Room Panel SIS No further action required Category requirements relaxed to categozy 3 as stated in SER provided by the NRC dated Nov.17, 1993 CMPLT CMPLT D-3b Accumulator 3 Tank pressure IPA-110olllo 120, 121, 130, 131 o 140 o 141 0-800 psig NA NA NA NA NA Contxol Room Panel SIS No further action rsquized Category requirements relaxed to categazy 3 as stated in SER provided by ths NRC dated Nav.17, 1993.CMPLT CMPLT D-4 D-5 D-6 D-7 Accumulator 2 Tank Zsolation valve position Boric acid Charging flow Flow in HPZ system Flow in IPZ system IM3-110,120, 130, 140 closed or open NANAA NANA Contzol Room Panel SIS None required see footnote NA (r)&(kk)(Deviation No.3)See item D-24 See item A-1 See item D-1 NA D-8 D-9 Primazy coolant system RWST lovel RCP status Ql,Q2,Q3,Q4 0 1200 A NA NA NA NA NA Control Room Panel RCP Sse item A-16 No action required NA NA D-10 Primary system 2 safety relief valve positions or flow thru or pressure in relief lines.QR-107 AOBo NA CoD A NA A NA NA Control Room Panel RC No action required sse footnote (b)(Deviation No.s DV-1&DV 3)NA NA D-11 Pzessurizor lovel See item A-10 D-12 Pressurizer 2 heater status Group Al,A2, on/off A3,C1,C2,C3 NA NA A NA NA Control Room Panel PRE No action zoquired ses faotnotss (d)&(ll)(Deviation No.DV-3)NA NA For Definition af"A" See Section 3.0 hvtaCnmenl.
to hbI'NKC:U//DAB Page 3/Type D Variables:
II those variables that provide information to indicate the operation of individual safety systems and other systems important to, safety.These variables are to help the operator make appropriate decisions in using the individual systems important to safety in mitigating the consequences of an accident." Note: The schedule and status for each.instrument is for when all of the appllcableg recommendations of Regulatory Guide 1.97, Rev 3 will be met.Item Purpose No.Variable Cat.Tag Nos.Range Remarks/Action Req'd E S g S P Display V-l V-2 h F S Location Schedule Schedule D-1 RHR System RHR System 2 Flow IFI-310 311, 320,321 0-1500 GPM A 1500-5000 GPM Nh A NA Nh Control Room No Action Required Panel RHR See footnotes ()))&(mmm)(Deviation No.DV-3)NA NA D-2 RHR Heat Ex-2 change Out-let Temp ITI-310,320 0-400'F A NA A NA NA Control Room Panel RHR No further action required (See footnote (ii)(Deviation No.s DV-1,&DV-3)CMPLT CMPI.T D-3a SI Systems Accumulator
/ILA-110,111 Tank l.evel~120,121, 130,131, 140,141 4.148 to A 120.8 in.(wide range)(52X of Total Volume)104.15 to 120.8 in.(narrow range)(7.5X of Total Volume)NA A NA NA Control Room Panel SIS Replace the wide range 1989 re-1990 re-transmitter each tank fueling fueling with,env.
qual.equipment outage outage See footnotes (iii)qualification shall apply to the wide range instruments only.(Deviation No.s DV-I, 6 (DV-3)D-3b Accumulator Tank Pres-sure IPA-110,111, 120,121, 130,131, 140,141 0-800 psig A NA h NA NA Control Room Replace one transmitter/
1989 re-1990 re-Panel SIS tank with env.qualified fueling fueling equipment.
qualification outage outage shall apply to only one instrument/tank.(Deviation No.s DV-l, 6 DV-3)D-4 Accumulator 2 Tank Isola-tion Valve Position IM0-110,120, 130 I 140 Closed or Open NA NA A Nh NA Control Room None Required Panel SIS See footnote (r)&(kk)(Deviation No.3)Nh NA For Definition of"A" See Section 3.0
