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| | issue date = 02/28/1995 | | | issue date = 02/28/1995 |
| | title = Forwards Proposed Ts,Revising Train A/B Battery Profiles & Modifying Train N Batteries Profile Request for Mod | | | title = Forwards Proposed Ts,Revising Train A/B Battery Profiles & Modifying Train N Batteries Profile Request for Mod |
| | author name = FITZPATRICK E | | | author name = Fitzpatrick E |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:P.RIQRITY 1(ACCELERATED RIDSPROCESSING REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)DOCKET0500031505000316P | | {{#Wiki_filter:P.RIQRITY (ACCELERATED RIDS PROCESSING 1 |
| | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:9503080168 DOC.DATE: 95/02/28 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ForwardsproposedTS,revising trainA/Bbatteryprofiles6modifying trainNbatteries profilerequestformod.DISTRIBUTION CODE:A001DCOPIESRECEIVED:
| | Forwards proposed TS,revising train A/B battery profiles 6 modifying train N batteries profile request for mod. |
| LTRJENCLlSIZE:k~TITLE:ORSubmittal:
| | DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED: LTR Submittal: General Distribution J ENCL l SIZE: k~ |
| GeneralDistribution ACCESSION NBR:9503080168 DOC.DATE:
| | NOTES R RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: IL'E 'CENTER 01 1 1 NRR/DRCH/HICB 1 1 |
| 95/02/28NOTARIZED:
| | ~NRR/DSSA~SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 . 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| YESFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM50-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaMAUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
| | 0 C |
| IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)NOTESRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
| | U N |
| IL'E'CENTER01~NRR/DSSA~SPLB NUDOCS-ABSTRACT EXTERNAL: | | NOTE TO ALL"RIDS" RECIPIENTS: |
| NOACCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2NRCPDRCOPIESLTTRENCL1111111.011RD0CUNNOTETOALL"RIDS"RECIPIENTS:
| | PLEASE HELP US TO REDUCE KVASTE! CONTACI THE DOCUiIENTCO4"I ROL DESK, ROOI1I PI-37 (EXT. 504-2083 ) TO EL!ihIINATE YOUR NAi!E FROM DISTRIBUTION LISTS I'OR DOCL'MEN'I'S YOU DON"I'EED! |
| PLEASEHELPUSTOREDUCEKVASTE!CONTACITHEDOCUiIENTCO4"I ROLDESK,ROOI1IPI-37(EXT.504-2083)TOEL!ihIINATEYOURNAi!EFROMDISTRIBUTION LISTSI'ORDOCL'MEN'I'S YOUDON"I'EED!
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10 |
| TOTALNUMBEROFCOPIESREQUIRED:
| | |
| LTTR11ENCL10 I
| | I indiana Michigan t 'ower Company |
| t/.~I'e~\'indianaMichigan'owerCompanyP.O.Box16631Columbus, OH43216February28,1995ENtMANANSCHESJEN PQ5ÃMAEP'NRC'0896U DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | /. \ |
| DonaldC.CookNuclearPlantUnits1and2TECHNICAL SPECIFICATION CHANGEREQUEST;REVISETHETRAINA/BBATTERYPROFILESANDMODIFYTRAINNBATTERIES'ROFILE REQUESTFORMODIFICATION
| | ~ |
| \ThepurposeofthisletteristomodifyourAEP:NRC:0896S letter,samesubject,datedJuly19,1994,asrequested bytheNRRstaff.InaJanuary13,1995,telephone conference theNRRreviewing. | | ~ I'e P.O. Box 16631 Columbus, OH 43216 ENtMANA NSCHESJEN PQ5ÃM February 28, 1995 AEP'NRC'0896U Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| engineerrequested thatweadoptthelanguageofthelatestrevisiontoIEEEStandard450withregardtothemodifiedperformance testanddegradedperformance testrecommendations.
| | Donald C. Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION CHANGE REQUEST; REVISE THE TRAIN A/B BATTERY PROFILES AND MODIFY TRAIN N BATTERIES'ROFILE REQUEST FOR MODIFICATION |
| Tosatisfyhisrequest,paragraph "e"onpages3/48-14and3/48-18fortheDonaldC.CookNuclearPlantUnits1and2technical specifications respectively shouldreadasfollows."Atleastonceper60months,conductaperformance testofbatterycapacityduringshutdown(MODES5or6),byverifying
| | \ |
| .thatthebatterycapacityisatleast80%ofthemanufacturer's rating.Whenthistestisperformed inplaceofabatteryservicetest,amodifiedperformance testshallbeconducted. | | The purpose of this letter is to modify our AEP:NRC:0896S letter, same subject, dated July 19, 1994, as requested by the NRR staff. |
| Annualperformance testsofbatterycapacityshallbegiventoanybatterythatshowssigns ofdegradation orhasreached85%oftheservicelifeexpectedfortheapplication.
| | In a January 13, 1995, telephone conference the NRR reviewing. |
| Degradation isindicated whenthebatterycapacitydropsmorethan10%fromitscapacityonthepreviousperformance test,oris-below90%ofthemanufacturer's rating.Ifthebatteryhasreached85%ofservicelife,deliversa capacityof100%orgreaterofthemanufacturer's ratedcapacity, andhasshownnosignsofdegradation, performance testingattwoyearintervals isacceptable untilthebatteryshowssignsofdegradation." | | engineer requested that we adopt the language of the latest revision to IEEE Standard 450 with regard to the modified performance test and degraded performance test recommendations. To satisfy his request, paragraph "e" on pages 3/4 8-14 and 3/4 8-18 for the Donald C. Cook Nuclear Plant Units 1 and 2 technical specifications respectively should read as follows. |
| 070OSS.9503080168 950228PDRADOCK05000315PPDR | | "At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying |
| .~0 U.S.NuclearRegulatory Commission Page2AEP:NRC:0896U Thebatterysurveillance requirements havebeenmodifiedtoreflectthecommentsasrequested. | | .that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted. |
| Foryourconvenience, acopyoftheexistingT/Ss,markedtoreflectallthechanges,isincludedasAttachment 1~Attachment 2isatypedcopyoftheT/Ss,astheyshouldappear,withbarmarginsindicating thechanges.Pleasenotethenewformatweareimplementing toallowelectronic accesstotheT/Ss.Withthenewformattherearepagination changesandminoradministrative changestoTable4.8-2inbothunitsinanongoingefforttoachieveuniformity betweentheunits.Wehavereviewedthestaff'srequested changesandbelievethesignificant hazardsconsideration performed pursuantto10CFR50.92fortheoriginalsubmittal isvalid.Therefore, wehavenotprovidedfurtherjustification forthechangesrequested bytheNRRstaff.Webelievetheproposedadditional changeswillnotresultin(1)asignificant changeinthetypesofeffluentorasignificant increaseintheamountofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
| | Annual performance tests of battery capacity shall be given to any battery that showssigns of degradation or has reached 85% of the service life expected for the application. |
| TheseproposedT/SchangeshavebeenreviewedandapprovedbythePlantNuclearSafetyReviewCommittee andwillbeapprovedbytheNuclearSafetyandDesignReviewCommittee atthenextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(l),
| | Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is-below 90% of the manufacturer's rating. If the battery has reached 85% of service life, deliversa capacity of 100% |
| copiesofthisletteranditsattachments havebeentransmitted toMr.J.R.PadgettoftheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.Sincerely, E'gpWE.E.FitpatrickVicePresident ehSWORNTOANDSUBSCRIBED BEFOREMETHIS~PDAYOF~~c1995Attachment cc:A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector
| | or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation." |
| -BridgmanJ.R.PadgettNoryPublic 0/ŽJ}} | | 070OSS. |
| | 9503080168 950228 PDR ADOCK 05000315 P PDR |
| | |
| | . ~ 0 U. S. Nuclear Regulatory Commission AEP:NRC:0896U Page 2 The battery surveillance requirements have been modified to reflect the comments as requested. For your convenience, a copy of the existing T/Ss, marked to reflect all the changes, is included as ~ Attachment 2 is a typed copy of the T/Ss, as they should appear, with bar margins indicating the changes. Please note the new format we are implementing to allow electronic access to the T/Ss. With the new format there are pagination changes and minor administrative changes to Table 4.8-2 in both units in an ongoing effort to achieve uniformity between the units. |
| | We have reviewed the staff's requested changes and believe the significant hazards consideration performed pursuant to 10 CFR 50.92 for the original submittal is valid. Therefore, we have not provided further justification for the changes requested by the NRR staff. |
| | We believe the proposed additional changes will not result in (1) a significant change in the types of effluent or a significant increase in the amount of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| | These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be approved by the Nuclear Safety and Design Review Committee at the next regularly scheduled meeting. |
| | In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health. |
| | Sincerely, E'g pW E. E. Fit patrick SWORN TO AND SUBSCRIBED BEFORE ME Vice President THIS ~P DAY OF ~~c 1995 eh Attachment No ry Public cc: A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett |
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| | J}} |
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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
P.RIQRITY (ACCELERATED RIDS PROCESSING 1
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9503080168 DOC.DATE: 95/02/28 NOTARIZED: YES DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards proposed TS,revising train A/B battery profiles 6 modifying train N batteries profile request for mod.
DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED: LTR Submittal: General Distribution J ENCL l SIZE: k~
NOTES R RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 1 INTERNAL: IL'E 'CENTER 01 1 1 NRR/DRCH/HICB 1 1
~NRR/DSSA~SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 . 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
0 C
U N
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE KVASTE! CONTACI THE DOCUiIENTCO4"I ROL DESK, ROOI1I PI-37 (EXT. 504-2083 ) TO EL!ihIINATE YOUR NAi!E FROM DISTRIBUTION LISTS I'OR DOCL'MEN'I'S YOU DON"I'EED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10
I indiana Michigan t 'ower Company
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~ I'e P.O. Box 16631 Columbus, OH 43216 ENtMANA NSCHESJEN PQ5ÃM February 28, 1995 AEP'NRC'0896U Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Donald C. Cook Nuclear Plant Units 1 and 2 TECHNICAL SPECIFICATION CHANGE REQUEST; REVISE THE TRAIN A/B BATTERY PROFILES AND MODIFY TRAIN N BATTERIES'ROFILE REQUEST FOR MODIFICATION
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The purpose of this letter is to modify our AEP:NRC:0896S letter, same subject, dated July 19, 1994, as requested by the NRR staff.
In a January 13, 1995, telephone conference the NRR reviewing.
engineer requested that we adopt the language of the latest revision to IEEE Standard 450 with regard to the modified performance test and degraded performance test recommendations. To satisfy his request, paragraph "e" on pages 3/4 8-14 and 3/4 8-18 for the Donald C. Cook Nuclear Plant Units 1 and 2 technical specifications respectively should read as follows.
"At least once per 60 months, conduct a performance test of battery capacity during shutdown (MODES 5 or 6), by verifying
.that the battery capacity is at least 80% of the manufacturer's rating. When this test is performed in place of a battery service test, a modified performance test shall be conducted.
Annual performance tests of battery capacity shall be given to any battery that showssigns of degradation or has reached 85% of the service life expected for the application.
Degradation is indicated when the battery capacity drops more than 10% from its capacity on the previous performance test, or is-below 90% of the manufacturer's rating. If the battery has reached 85% of service life, deliversa capacity of 100%
or greater of the manufacturer's rated capacity, and has shown no signs of degradation, performance testing at two year intervals is acceptable until the battery shows signs of degradation."
070OSS.
9503080168 950228 PDR ADOCK 05000315 P PDR
. ~ 0 U. S. Nuclear Regulatory Commission AEP:NRC:0896U Page 2 The battery surveillance requirements have been modified to reflect the comments as requested. For your convenience, a copy of the existing T/Ss, marked to reflect all the changes, is included as ~ Attachment 2 is a typed copy of the T/Ss, as they should appear, with bar margins indicating the changes. Please note the new format we are implementing to allow electronic access to the T/Ss. With the new format there are pagination changes and minor administrative changes to Table 4.8-2 in both units in an ongoing effort to achieve uniformity between the units.
We have reviewed the staff's requested changes and believe the significant hazards consideration performed pursuant to 10 CFR 50.92 for the original submittal is valid. Therefore, we have not provided further justification for the changes requested by the NRR staff.
We believe the proposed additional changes will not result in (1) a significant change in the types of effluent or a significant increase in the amount of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed T/S changes have been reviewed and approved by the Plant Nuclear Safety Review Committee and will be approved by the Nuclear Safety and Design Review Committee at the next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.
Sincerely, E'g pW E. E. Fit patrick SWORN TO AND SUBSCRIBED BEFORE ME Vice President THIS ~P DAY OF ~~c 1995 eh Attachment No ry Public cc: A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett
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