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| {{#Wiki_filter:CATEGORY1REGULATOYINFORMATION DISTRIBUTION YSTEM(RIDS)ACCESSION NBR:9705290178 DOC.DATE:97/05/21NOTARIZED:NODOCKETFACIL:50-315DonaldC.CookNuclearPoeerPlantiUnitiiIndianaM0500031550'-316DonaldC.CookNucleav.PoeerPlant.Unit2.EndianaM05000316AUTH.NAI'IEAUTHORAFFILIATION FITZPATRICKiE.AmericanElectricPowerCo.~Inc.RECIP.NAME,RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) | | {{#Wiki_filter:CATEGORY 1 REGULATO Y INFORMATION DISTRIBUTION YSTEM (RIDS)ACCESSION NBR: 9705290178 DOC.DATE: 97/05/21 NOTAR I ZED: NO DOCKET FACIL: 50-315 Donald C.Cook Nuclear Poeer Planti Unit ii Indiana M 05000315 50'-316 Donald C.Cook Nucleav.Poeer Plant.Unit 2.Endiana M 05000316 AUTH.NAI'IE AUTHOR AFFILIATION FITZPATR ICKi E.Amer i can Electric Power Co.~Inc.RECIP.NAME, RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forfardsresponseto.970326RAIreplantraceway/f irestopconfiguration inresponsetoconcernsfovGL-92-08.
| | Forfar ds response to.970326 RAI re plant raceway/f ire stop conf iguration in response to concerns f ov GL-92-08."Thermo-Lag 330-1 Fire Bav;v iev s." DISTRIBUTION CODE: A029D COP EES RECEI')ED: |
| "Thermo-Lag 330-1FireBav;vievs."DISTRIBUTION CODE:A029DCOPEESRECEI')ED: | | LTR ENCL SIZE: I ITLE: Genev ic Lettev 92-008 Thermo-Lag 330 Fire Bav riev NOTES:+87 E RECIP EENT ID CODE/NAI'IE PD3-3 LA HECKMANi J INTERNAL.FILE CEN~TZ~O~'%FR/DRPW/PD3-1 RGN3 FILF.1 1 1 1 1 NRR/DE/EELB NRR/DSS*/SPL'B COPIES RECIPIENT LTTR ENCL ID CODE/NAME 0 PD3-3 PD 1 COPIES LTTR EiNCL 1 1 1 1 1,1 G 0 Y EXTERNAL: NOAC QI~R,~(ngS NRC PDR 1 oca, e tw e~t'~i eh D 0 N NOTE TO ALL"RZDS" RECIPZENTSI PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COP EES REQUIRED: LTTR 10 ENCL 9 ed-8 t a l l Indiana Michigan~Power Company 500 Circle Drive Buchanan, Mi 491071395 INQMNA Sllml6AN PQWM May 21, 1997 AEP:NRC:0692DM Docket Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: |
| LTRENCLSIZE:IITLE:GenevicLettev92-008Thermo-Lag 330FireBavrievNOTES:+87ERECIPEENTIDCODE/NAI'IE PD3-3LAHECKMANiJINTERNAL.
| | Donald C.Cook Nuclear Plant Units 1 and 2 RESPONSE TO GENERIC LETTER 92-08 (TAC NOS.M85538 AND M85539)THERMO-LAG 330-1 FIRE BARRIERS REQUEST FOR ADDITIONAL INFORMATION In our letter dated December 27, 1996 (AEP:NRC:692DB), we informed the NRC that corrective actions in response to the concerns identified in NRC generic letter 92-08, and subsequent requests for additional information, have been completed at Cook Nuclear Plant.By letter dated March 26, 1997, your staff requested additional information concerning how our raceway/fire stop configuration, described in AEP:NRC:692DB, meets the NRC fire protection requirements and Cook Nuclear Plant licensing and design bases.Our response to the request for additional information is contained in the attachments. |
| FILECEN~TZ~O~'%FR/DRPW/PD3-1 RGN3FILF.11111NRR/DE/EELB NRR/DSS*/SPL'B COPIESRECIPIENT LTTRENCLIDCODE/NAME 0PD3-3PD1COPIESLTTREiNCL11111,1G0YEXTERNAL:
| | Attachment 1 describes our use of fire stops for the 20 foot separation boundary.Attachments 2 and 3 contain the technical evaluations for auxiliary building fire zones 6M and 6S, and fire zones 44N and 44S, respectively. |
| NOACQI~R,~(ngS NRCPDR1oca,etwe~t'~iehD0NNOTETOALL"RZDS"RECIPZENTSI PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPEESREQUIRED:
| | Attachments 4 and 5 contain design detail drawings 2-1434R-5 and 2-1419R-6, respectively. |
| LTTR10ENCL9ed-8 tall IndianaMichigan~PowerCompany500CircleDriveBuchanan, Mi491071395 INQMNASllml6ANPQWMMay21,1997AEP:NRC:0692DM DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | Sincerely, CW p E.E.Fitzpatrick Vice President vlb Attachments CC: A.A.Blind A.B.Beach MDEQ-DW Ec RDP NRC Resident Inspector J.R.Padgett 9705290i78 PDR" ADOCK P 97052i 050003i5 PDR 3%&.g IN (.e~0 Lzs ff!ffff!fff!ffllllfffffffffrfffffffff 1 l E ATTACHMENT 1 TO AEP:NRC:0692DM FIRE STOPS FOR 20 FOOT SEPARATION BOUNDARY |
| DonaldC.CookNuclearPlantUnits1and2RESPONSETOGENERICLETTER92-08(TACNOS.M85538ANDM85539)THERMO-LAG 330-1FIREBARRIERSREQUESTFORADDITIONAL INFORMATION InourletterdatedDecember27,1996(AEP:NRC:692DB),
| |
| weinformedtheNRCthatcorrective actionsinresponsetotheconcernsidentified inNRCgenericletter92-08,andsubsequent requestsforadditional information, havebeencompleted atCookNuclearPlant.ByletterdatedMarch26,1997,yourstaffrequested additional information concerning howourraceway/fire stopconfiguration, described inAEP:NRC:692DB, meetstheNRCfireprotection requirements andCookNuclearPlantlicensing anddesignbases.Ourresponsetotherequestforadditional information iscontained intheattachments.
| |
| Attachment 1describes ouruseoffirestopsforthe20footseparation boundary. | |
| Attachments 2and3containthetechnical evaluations forauxiliary buildingfirezones6Mand6S,andfirezones44Nand44S,respectively. | |
| Attachments 4and5containdesigndetaildrawings2-1434R-5 and2-1419R-6, respectively. | |
| Sincerely, CWpE.E.Fitzpatrick VicePresident vlbAttachments CC:A.A.BlindA.B.BeachMDEQ-DWEcRDPNRCResidentInspector J.R.Padgett9705290i78 PDR"ADOCKP97052i050003i5PDR3%&.gIN(.e~0Lzsff!ffff!fff!ffllllfffffffffrfffffffff 1lE ATTACHMENT 1TOAEP:NRC:0692DM FIRESTOPSFOR20FOOTSEPARATION BOUNDARY | |
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| Attachment 1toAEP:NRC:0692DM Page1IntheNRCRAIdatedMarch26,1997,thefollowing requestwasmade."Additional information isrequiredtoresolvethestaff'squestions andreviewthenewconfiguration. | | Attachment 1 to AEP:NRC:0692DM Page 1 In the NRC RAI dated March 26, 1997, the following request was made."Additional information is required to resolve the staff's questions and review the new configuration. |
| Specifically, pleaseaddress,indetail,howtheraceway/fire stopconfiguration described intheletterofDecember27,1996,meetsNRCfireprotection requirements andtheD.C.Cooklicensing anddesignbases.Inthisdiscussion, identifyanyexemptions fromSectionIII.GorAppendixRto10CFRPart50thathavebeenrequested andgrantedforthefirestopconfigurations described intheletterofDecember27,1996.Inaddition, submitthedesigndetailsofthefirestops,thedrawingsshowingthelocations oft.hefirestopsandfireareaswheretheyarecredited, andtheengineering analysesthatsupportachieving a20footseparation usingcabletrayfire"-tops."NRCFireProtection Reuirements andCookNuclearPlantLicensinandDesinBasesThesafeshutdowncapability assessment (SSCA)wascreatedtoaddresscompliance with10CFR50,appendixR,sectionZIZ.G.AppendixR,sectionZIZ.G.2.(b) providesonemeansofensuringthatoneoftheredundant trainsisfreeoffiredamage.Thissectionstates,"[S]eparation ofcablesandequipment andassociated non-safetycircuitsofredundant trainsbyahorizontal distanceofmorethan20feetwithnointervening combustible orfirehazards.Inaddition, firedetectors andanautomatic firesuppression systemshallbeinstalled inthefirearea;...." | | Specifically, please address, in detail, how the raceway/fire stop configuration described in the letter of December 27, 1996, meets NRC fire protection requirements and the D.C.Cook licensing and design bases.In this discussion, identify any exemptions from Section III.G or Appendix R to 10 CFR Part 50 that have been requested and granted for the fire stop configurations described in the letter of December 27, 1996.In addition, submit the design details of the fire stops, the drawings showing the locations of t.he fire stops and fire areas where they are credited, and the engineering analyses that support achieving a 20 foot separation using cable tray fire"-tops." NRC Fire Protection Re uirements and Cook Nuclear Plant Licensin and Desi n Bases The safe shutdown capability assessment (SSCA)was createdto address compliance with 10 CFR 50, appendix R, section ZIZ.G.Appendix R, section ZIZ.G.2.(b) provides one means of ensuring that one of the redundant trains is free of fire damage.This section states,"[S]eparation of cables and equipment and associated non-safety circuits of redundant trains by a horizontal distance of more than 20 feet with no intervening combustible or fire hazards.In addition, fire detectors and an automatic fire suppression system shall be installed in the fire area;...." Rev.0 of the SSCA, dated March 1983, was submitted to the NRC on March 31, 1983, by our letter AEP:NRC:0692E. |
| Rev.0oftheSSCA,datedMarch1983,wassubmitted totheNRConMarch31,1983,byourletterAEP:NRC:0692E. | | This submittal contained sections 8.3.1 and 8.16.1, that described two locations where section ZII.G.2.(b) was utilized.In both ituations, the SSCA stated that certain"open cable trays traversing the zone from the north side to the south side will be appropriately fire stopped to prevent fire propagation from one section of the fire zone to the other" Rev.1 to the SSCA was submitted on March 20, 1987, by AEP:NRC:~92AZ.There was no change to the statements in sections 8.3.1 and 8.16.1 quoted above.Generic letter (GL)86-10 contains guidance regarding the meaning and intent of section III.G.2.(b) wording for intervening combustibles and exemption requests.Based on the information in GL 86-10, the cables in the trays without some form of non-combustible covering are considered intervening combustibles. |
| Thissubmittal contained sections8.3.1and8.16.1,thatdescribed twolocations wheresectionZII.G.2.(b) wasutilized.
| | However, because the use of fire stops met our original licensing bases (SSCA)and predated GL 86-10, we did not believe the installation of additional fire stops warranted an exemption request relative to the subject fire stop configuration. |
| Inbothituations, theSSCAstatedthatcertain"opencabletraystraversing thezonefromthenorthsidetothesouthsidewillbeappropriately firestoppedtopreventfirepropagation fromonesectionofthefirezonetotheother"Rev.1totheSSCAwassubmitted onMarch20,1987,byAEP:NRC:~92AZ.Therewasnochangetothestatements insections8.3.1and8.16.1quotedabove.Genericletter(GL)86-10containsguidanceregarding themeaningandintentofsectionIII.G.2.(b) wordingforintervening combustibles andexemption requests.
| | Desi n Details Attachments 4 and 5 are drawings that show the two locations where fire stops are provided in accordance with section III.G.2.(b) |
| Basedontheinformation inGL86-10,thecablesinthetrayswithoutsomeformofnon-combustible coveringareconsidered intervening combustibles.
| | .These drawings show the cable trays located in the subject 20 foot separation spaces, the location of the fire stops on the trays, details of the fire stops, and fire zone locations. |
| However,becausetheuseoffirestopsmetouroriginallicensing bases(SSCA)andpredatedGL86-10,wedidnotbelievetheinstallation ofadditional firestopswarranted anexemption requestrelativetothesubjectfirestopconfiguration. | | These drawings have details showing extensions added to the sides of certain trays.The following is provided to clarify why and how these extensions were added.For some control cable installations, additional space was needed for proper installation of the silicone Attachment 1 to AEP:NRC:0692DM Page 2 foam and spreading of the cables.The added space is provided by sheet metal extensions. |
| DesinDetailsAttachments 4and5aredrawingsthatshowthetwolocations wherefirestopsareprovidedinaccordance withsectionIII.G.2.(b)
| | In attachment 4, these extensions are'hown on drawing 2-1419R-6 in details KB, MB, F9, H9, K9 and M9, and in attachment 5 on drawing 2-1434R-S, they are shown in details J2 and L2.For these installations, the sides of the raceway/fire stop configurations have been extended as shown.This design detail is not applicable to power cable trays.The silicone foam is entirely enclosed between the metal housing and the damming material.The damming material at the ends of the silicone foam reservoir separates the control cables.As the silicone foam expands and fills the enclosed space, it also separates the control cables.En ineerin Anal ses That Su ort Achievin a 20 Foot Se aration Usin Cable Tra Fire Sto s Attachments 2 and 3 are technical evaluations 11.42 and 1.43 respectively. |
| .Thesedrawingsshowthecabletrayslocatedinthesubject20footseparation spaces,thelocationofthefirestopsonthetrays,detailsofthefirestops,andfirezonelocations. | | At the end of each of the technical evaluations there is a conclusion section.That section provides a summary of the defense-in-depth that leads to the conclusion that a fire on either side of the subject 20 foot separation spaces will not spread to the other side.This summary does not take credit for other attributes such as the enclosed (control cable)trays and the small quantity of cables, ranging from 3 to 20, in the open (power cable)trays, both of which further contribute to minimizing the impact of the intervening combustibles within the designated 20 foot spaces.During preparation of this response, it was noticed that the title and purpose of these technical evaluations may need clarification. |
| Thesedrawingshavedetailsshowingextensions addedtothesidesofcertaintrays.Thefollowing isprovidedtoclarifywhyandhowtheseextensions wereadded.Forsomecontrolcableinstallations, additional spacewasneededforproperinstallation ofthesilicone Attachment 1toAEP:NRC:0692DM Page2foamandspreading ofthecables.Theaddedspaceisprovidedbysheetmetalextensions.
| | Appendix R section III.G.2.(b) was paraphrased and contains the phrase"with no intervening combustibles". |
| Inattachment 4,theseextensions are'hownondrawing2-1419R-6 indetailsKB,MB,F9,H9,K9andM9,andinattachment 5ondrawing2-1434R-S, theyareshownindetailsJ2andL2.Fortheseinstallations, thesidesoftheraceway/fire stopconfigurations havebeenextendedasshown.Thisdesigndetailisnotapplicable topowercabletrays.Thesiliconefoamisentirelyenclosedbetweenthemetalhousingandthedammingmaterial.
| | We agree that the cables under discussion are intervening combustibles. |
| Thedammingmaterialattheendsofthesiliconefoamreservoir separates thecontrolcables.Asthesiliconefoamexpandsandfillstheenclosedspace,italsoseparates thecontrolcables.EnineerinAnalsesThatSuortAchievina20FootSearationUsinCableTraFireStosAttachments 2and3aretechnical evaluations 11.42and1.43respectively.
| | However, these technical evaluation evaluate the ability of the"twenty foot wide separation space" to prevent the spread of fire between fire zones and to maintain safe shutdown capability for both units.Three differences between the current design/procedures and the description in the technical evaluations were noted.All three differences have either no impact or they enhance the a~~cribed situation. |
| Attheendofeachofthetechnical evaluations thereisaconclusion section.Thatsectionprovidesasummaryofthedefense-in-depth thatleadstotheconclusion thatafireoneithersideofthesubject20footseparation spaceswillnotspreadtotheotherside.Thissummarydoesnottakecreditforotherattributes suchastheenclosed(controlcable)traysandthesmallquantityofcables,rangingfrom3to20,intheopen(powercable)trays,bothofwhichfurthercontribute tominimizing theimpactoftheintervening combustibles withinthedesignated 20footspaces.Duringpreparation ofthisresponse, itwasnoticedthatthetitleandpurposeofthesetechnical evaluations mayneedclarification.
| | The three differences are: 1)the boundaries have shifted slightly from those described in the evaluations and shown on the sketches attached to the evaluations (no impact);2)the fire loadings have been reduced because of thermo-lag removal (enhancement); |
| AppendixRsectionIII.G.2.(b) wasparaphrased andcontainsthephrase"withnointervening combustibles".
| | and 3)the daily tour is being upgraded to a procedure versus a guideline (enhancement). |
| Weagreethatthecablesunderdiscussion areintervening combustibles.
| | These differences have no significant impact on the evaluations. |
| However,thesetechnical evaluation evaluatetheabilityofthe"twentyfootwideseparation space"topreventthespreadoffirebetweenfirezonesandtomaintainsafeshutdowncapability forbothunits.Threedifferences betweenthecurrentdesign/procedures andthedescription inthetechnical evaluations werenoted.Allthreedifferences haveeithernoimpactortheyenhancethea~~cribed situation. | | ~Summar The SSCA (rev.0 and 1), submitted to the NRC, stated that a commitment to meet appendix R, section III.G.2.(b) requirements at two locations would be accomplished by providing fire stops in cable trays traversing the separation space.No commitment was made to provide a covering of the intervening combustibles. |
| Thethreedifferences are:1)theboundaries haveshiftedslightlyfromthosedescribed intheevaluations andshownonthesketchesattachedtotheevaluations (noimpact);2)thefireloadingshavebeenreducedbecauseofthermo-lag removal(enhancement);
| | The thermo-lag was believed to be a non-combustible wrapping and was added to some cable trays traversing the separation space.When the thermo-lag was removed, the cable between the fire stops became an intervening combustible. |
| and3)thedailytourisbeingupgradedtoaprocedure versusaguideline (enhancement).
| | Because our licensing bases use of fire stops predated GL 86-10 guidance, we believed that an exemption was not required.The safe shutdown impact of the use of fire stops is contained in the technical evaluations prepared for |
| Thesedifferences havenosignificant impactontheevaluations.
| |
| ~SummarTheSSCA(rev.0and1),submitted totheNRC,statedthatacommitment tomeetappendixR,sectionIII.G.2.(b) requirements attwolocations wouldbeaccomplished byproviding firestopsincabletraystraversing theseparation space.Nocommitment wasmadetoprovideacoveringoftheintervening combustibles. | |
| Thethermo-lag wasbelievedtobeanon-combustible wrappingandwasaddedtosomecabletraystraversing theseparation space.Whenthethermo-lag wasremoved,thecablebetweenthefirestopsbecameanintervening combustible.
| |
| Becauseourlicensing basesuseoffirestopspredatedGL86-10guidance, webelievedthatanexemption wasnotrequired.
| |
| Thesafeshutdownimpactoftheuseoffirestopsiscontained inthetechnical evaluations preparedfor
| |
|
| |
|
| Attachment 1toAEP:NRC:0692DM Page3theselocat'ons. | | Attachment 1 to AEP:NRC:0692DM Page 3 these locat'ons. |
| Thesetechnical ovaluations showthattheintentofappendixR,section'ZXE.G.2.(b) hasbeenmet.
| | These technical ovaluations show that the intent of appendix R, section'ZXE.G.2.(b) has been met. |
| J ATTACHMENT 2TOAEP:NRC:0692DM TECHNICAL EVALUATION FORAUXILIARY BUILDINGFIREZONES6MAND6S}} | | J ATTACHMENT 2 TO AEP:NRC:0692DM TECHNICAL EVALUATION FOR AUXILIARY BUILDING FIRE ZONES 6M AND 6S}} |
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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
CATEGORY 1 REGULATO Y INFORMATION DISTRIBUTION YSTEM (RIDS)ACCESSION NBR: 9705290178 DOC.DATE: 97/05/21 NOTAR I ZED: NO DOCKET FACIL: 50-315 Donald C.Cook Nuclear Poeer Planti Unit ii Indiana M 05000315 50'-316 Donald C.Cook Nucleav.Poeer Plant.Unit 2.Endiana M 05000316 AUTH.NAI'IE AUTHOR AFFILIATION FITZPATR ICKi E.Amer i can Electric Power Co.~Inc.RECIP.NAME, RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forfar ds response to.970326 RAI re plant raceway/f ire stop conf iguration in response to concerns f ov GL-92-08."Thermo-Lag 330-1 Fire Bav;v iev s." DISTRIBUTION CODE: A029D COP EES RECEI')ED:
LTR ENCL SIZE: I ITLE: Genev ic Lettev 92-008 Thermo-Lag 330 Fire Bav riev NOTES:+87 E RECIP EENT ID CODE/NAI'IE PD3-3 LA HECKMANi J INTERNAL.FILE CEN~TZ~O~'%FR/DRPW/PD3-1 RGN3 FILF.1 1 1 1 1 NRR/DE/EELB NRR/DSS*/SPL'B COPIES RECIPIENT LTTR ENCL ID CODE/NAME 0 PD3-3 PD 1 COPIES LTTR EiNCL 1 1 1 1 1,1 G 0 Y EXTERNAL: NOAC QI~R,~(ngS NRC PDR 1 oca, e tw e~t'~i eh D 0 N NOTE TO ALL"RZDS" RECIPZENTSI PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COP EES REQUIRED: LTTR 10 ENCL 9 ed-8 t a l l Indiana Michigan~Power Company 500 Circle Drive Buchanan, Mi 491071395 INQMNA Sllml6AN PQWM May 21, 1997 AEP:NRC:0692DM 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 RESPONSE TO GENERIC LETTER 92-08 (TAC NOS.M85538 AND M85539)THERMO-LAG 330-1 FIRE BARRIERS REQUEST FOR ADDITIONAL INFORMATION In our letter dated December 27, 1996 (AEP:NRC:692DB), we informed the NRC that corrective actions in response to the concerns identified in NRC generic letter 92-08, and subsequent requests for additional information, have been completed at Cook Nuclear Plant.By letter dated March 26, 1997, your staff requested additional information concerning how our raceway/fire stop configuration, described in AEP:NRC:692DB, meets the NRC fire protection requirements and Cook Nuclear Plant licensing and design bases.Our response to the request for additional information is contained in the attachments.
Attachment 1 describes our use of fire stops for the 20 foot separation boundary.Attachments 2 and 3 contain the technical evaluations for auxiliary building fire zones 6M and 6S, and fire zones 44N and 44S, respectively.
Attachments 4 and 5 contain design detail drawings 2-1434R-5 and 2-1419R-6, respectively.
Sincerely, CW p E.E.Fitzpatrick Vice President vlb Attachments CC: A.A.Blind A.B.Beach MDEQ-DW Ec RDP NRC Resident Inspector J.R.Padgett 9705290i78 PDR" ADOCK P 97052i 050003i5 PDR 3%&.g IN (.e~0 Lzs ff!ffff!fff!ffllllfffffffffrfffffffff 1 l E ATTACHMENT 1 TO AEP:NRC:0692DM FIRE STOPS FOR 20 FOOT SEPARATION BOUNDARY
Attachment 1 to AEP:NRC:0692DM Page 1 In the NRC RAI dated March 26, 1997, the following request was made."Additional information is required to resolve the staff's questions and review the new configuration.
Specifically, please address, in detail, how the raceway/fire stop configuration described in the letter of December 27, 1996, meets NRC fire protection requirements and the D.C.Cook licensing and design bases.In this discussion, identify any exemptions from Section III.G or Appendix R to 10 CFR Part 50 that have been requested and granted for the fire stop configurations described in the letter of December 27, 1996.In addition, submit the design details of the fire stops, the drawings showing the locations of t.he fire stops and fire areas where they are credited, and the engineering analyses that support achieving a 20 foot separation using cable tray fire"-tops." NRC Fire Protection Re uirements and Cook Nuclear Plant Licensin and Desi n Bases The safe shutdown capability assessment (SSCA)was createdto address compliance with 10 CFR 50, appendix R, section ZIZ.G.Appendix R, section ZIZ.G.2.(b) provides one means of ensuring that one of the redundant trains is free of fire damage.This section states,"[S]eparation of cables and equipment and associated non-safety circuits of redundant trains by a horizontal distance of more than 20 feet with no intervening combustible or fire hazards.In addition, fire detectors and an automatic fire suppression system shall be installed in the fire area;...." Rev.0 of the SSCA, dated March 1983, was submitted to the NRC on March 31, 1983, by our letter AEP:NRC:0692E.
This submittal contained sections 8.3.1 and 8.16.1, that described two locations where section ZII.G.2.(b) was utilized.In both ituations, the SSCA stated that certain"open cable trays traversing the zone from the north side to the south side will be appropriately fire stopped to prevent fire propagation from one section of the fire zone to the other" Rev.1 to the SSCA was submitted on March 20, 1987, by AEP:NRC:~92AZ.There was no change to the statements in sections 8.3.1 and 8.16.1 quoted above.Generic letter (GL)86-10 contains guidance regarding the meaning and intent of section III.G.2.(b) wording for intervening combustibles and exemption requests.Based on the information in GL 86-10, the cables in the trays without some form of non-combustible covering are considered intervening combustibles.
However, because the use of fire stops met our original licensing bases (SSCA)and predated GL 86-10, we did not believe the installation of additional fire stops warranted an exemption request relative to the subject fire stop configuration.
Desi n Details Attachments 4 and 5 are drawings that show the two locations where fire stops are provided in accordance with section III.G.2.(b)
.These drawings show the cable trays located in the subject 20 foot separation spaces, the location of the fire stops on the trays, details of the fire stops, and fire zone locations.
These drawings have details showing extensions added to the sides of certain trays.The following is provided to clarify why and how these extensions were added.For some control cable installations, additional space was needed for proper installation of the silicone Attachment 1 to AEP:NRC:0692DM Page 2 foam and spreading of the cables.The added space is provided by sheet metal extensions.
In attachment 4, these extensions are'hown on drawing 2-1419R-6 in details KB, MB, F9, H9, K9 and M9, and in attachment 5 on drawing 2-1434R-S, they are shown in details J2 and L2.For these installations, the sides of the raceway/fire stop configurations have been extended as shown.This design detail is not applicable to power cable trays.The silicone foam is entirely enclosed between the metal housing and the damming material.The damming material at the ends of the silicone foam reservoir separates the control cables.As the silicone foam expands and fills the enclosed space, it also separates the control cables.En ineerin Anal ses That Su ort Achievin a 20 Foot Se aration Usin Cable Tra Fire Sto s Attachments 2 and 3 are technical evaluations 11.42 and 1.43 respectively.
At the end of each of the technical evaluations there is a conclusion section.That section provides a summary of the defense-in-depth that leads to the conclusion that a fire on either side of the subject 20 foot separation spaces will not spread to the other side.This summary does not take credit for other attributes such as the enclosed (control cable)trays and the small quantity of cables, ranging from 3 to 20, in the open (power cable)trays, both of which further contribute to minimizing the impact of the intervening combustibles within the designated 20 foot spaces.During preparation of this response, it was noticed that the title and purpose of these technical evaluations may need clarification.
Appendix R section III.G.2.(b) was paraphrased and contains the phrase"with no intervening combustibles".
We agree that the cables under discussion are intervening combustibles.
However, these technical evaluation evaluate the ability of the"twenty foot wide separation space" to prevent the spread of fire between fire zones and to maintain safe shutdown capability for both units.Three differences between the current design/procedures and the description in the technical evaluations were noted.All three differences have either no impact or they enhance the a~~cribed situation.
The three differences are: 1)the boundaries have shifted slightly from those described in the evaluations and shown on the sketches attached to the evaluations (no impact);2)the fire loadings have been reduced because of thermo-lag removal (enhancement);
and 3)the daily tour is being upgraded to a procedure versus a guideline (enhancement).
These differences have no significant impact on the evaluations.
~Summar The SSCA (rev.0 and 1), submitted to the NRC, stated that a commitment to meet appendix R, section III.G.2.(b) requirements at two locations would be accomplished by providing fire stops in cable trays traversing the separation space.No commitment was made to provide a covering of the intervening combustibles.
The thermo-lag was believed to be a non-combustible wrapping and was added to some cable trays traversing the separation space.When the thermo-lag was removed, the cable between the fire stops became an intervening combustible.
Because our licensing bases use of fire stops predated GL 86-10 guidance, we believed that an exemption was not required.The safe shutdown impact of the use of fire stops is contained in the technical evaluations prepared for
Attachment 1 to AEP:NRC:0692DM Page 3 these locat'ons.
These technical ovaluations show that the intent of appendix R, section'ZXE.G.2.(b) has been met.
J ATTACHMENT 2 TO AEP:NRC:0692DM TECHNICAL EVALUATION FOR AUXILIARY BUILDING FIRE ZONES 6M AND 6S
