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| | issue date = 04/06/1994 | | | issue date = 04/06/1994 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove License Condition Reference to Table 1 of Fire Protection Safety Evaluation Rept for Cook Nuclear Plant, Approved on 790604 & Issued on 790731 | | | title = Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove License Condition Reference to Table 1 of Fire Protection Safety Evaluation Rept for Cook Nuclear Plant, Approved on 790604 & Issued on 790731 |
| | 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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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 15 | | | page count = 15 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED DITRIBUTION DEMONSTATIONSYSTEM4~REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9404130015 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DI TRIBUTION DEMONST ATION SYSTEM 4~ |
| 94/04/06NOTARIZED: | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
| | ACCESSION NBR:9404130015 DOC.DATE: 94/04/06 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 & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstolicensesDPR-58&DPR-74,proposing toremovelicensecondition reference totable1offireprotection safetyevaluation rept,forCookNuclearPlant,approvedon790604&issuedon790731.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | Application for amends to licenses DPR-58 & DPR-74,proposing to remove license condition reference to table 1 of fire D protection safety evaluation rept, for Cook Nuclear Plant, approved on 790604 & issued on 790731. |
| GeneralDistribution NOTES:DRECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNAL:
| | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: |
| NRR/DE/EELB NRR/DRCH/HI CBNRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2EXTERNALNRCPDRCOPIESLTTRENCL1122111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DORS/OTS BNRR/DRPWNRR/DSSA/SRXB OC/LFDCBE~IL01NSICCOPIESLTTRENCL11111111101111DDDNOTETOALL"RIDS"RECIPIENTS: | | TITLE: OR Submittal: General Distribution NOTES: |
| DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
| | RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 0 OGC/HDS2 1 0 E~IL 01 1 1 EXTERNAL NRC PDR 1 1 NSIC 1 1 D |
| LTTR16ENCL14 IndianaMichigan~PowerCompanyP.O.Box16631Coiumbus, OH43216INWAl84MCHII6'HAM ltaOMKRAEP:NRC'0692CJ DonaldC.CookNuclearPlantUnits1and2DocketNo.50-315and50-316LicenseNo.DPR-58andDPR-74LICENSEAMENDMENT U.S.NuclearRegulatory Commission DocumentControlDeskWashington, D.C.20555Attn:W.T.RussellApril6,1994
| | D D |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 |
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| ==DearMr.Russell:==
| | Indiana Michigan Power Company |
| Thisletteranditsattachments constitute anapplication foramendment tothelicensesforDonaldC.CookNuclearPlant,Units1and2.Weproposetoremovethelicensecondition reference toTable1oftheFireProtection SafetyEvaluation ReportforCookNuclearPlant,approvedonJune4,1979,andissuedunderacoverletterdatedJuly31,1979.Theobjectives ofthis1979licensecondition havebeenachieved.
| | ~ |
| Thelicenseconditions'eference totheadministrative controlsforfireprotection, asdescribed inthelicensee's submittals datedJanuary31,1977,andOctober27,1977,willremain.Theselicenseconditions currently readasfollows:DocketNo.315Amendment No.312.c(4)Thelicenseemayproceedwithandisrequiredtocompletethemodifications identified inTable1oftheFireProtection SafetyEvaluation ReportfortheDonaldC.CookNuclearPlantdatedJune4,1979.Thesemodifications shallbecompleted inaccordance withthedatescontained inTable1ofthatSERorSupplements thereto.Administrative controlsforfireprotection asdescribed inthelicensee's submittals datedJanuary31,1977andOctober27,1977shallbeimplemented andmaintained.
| | P.O. Box 16631 Coiumbus, OH 43216 INWAl84 MCHII6'HAM ltaOMKR AEP:NRC'0692CJ Donald C. Cook Nuclear Plant Units 1 and 2 Docket No. 50-315 and 50-316 License No. DPR-58 and DPR-74 LICENSE AMENDMENT U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: W. T. Russell April 6, 1994 |
| 9404130015 94040bPDRADOCK05000315PDRo~I(
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| Mr.W.T.Russell2AEP:NRC:0692CJ DocketNo.316Amendment No.122.c(3)(o) irePotectoThelicenseemayproceedwithandisrequiredtocompletethemodifications identified inTable1oftheFireProtection SafetyEvaluation ReportfortheDonaldC.CookNuclearPlantdatedJune4,1979.Thesemodifications shallbecompleted inaccordance withthedatescontained inTable1ofthatSERorSupplements thereto.Administrative controlsforfireprotection asdescribed inthelicensee's submittals datedJanuary31,1977andOctober27,1977shallbeimplemented andmaintained. | | ==Dear Mr. Russell:== |
| Itisproposedthatthefirsttwosentences ofparagraphs 2.c(4)and2.c(3)(o),
| | |
| above,bedeleted.Attachment 1providesadetaileddescription oftheproposedchanges,thereasonsforthechanges,andourproposeddetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92,Attachment 2containstheexistinglicensecondition pagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposed, revisedlicensecondition pages.Therearetwenty-three schedular modifications identified inTable1oftheFireProtection SafetyEvaluation ReportforDonaldC.CookNuclearPlantdatedJune4,1979.Alltwenty-three itemshavebeencompleted. | | This letter and its attachments constitute an application for amendment to the licenses for Donald C. Cook Nuclear Plant, Units 1 and 2. We propose to remove the license condition reference to Table 1 of the Fire Protection Safety Evaluation Report for Cook Nuclear Plant, approved on June 4, 1979, and issued under a cover letter dated July 31, 1979. The objectives of this 1979 license condition have been achieved. The license conditions'eference to the administrative controls for fire protection, as described in the licensee's submittals dated January 31, 1977, and October 27, 1977, will remain. These license conditions currently read as follows: |
| Threeoftheseitemssubsequently havebeenchanged,asalsodiscussed inAttachment l.Webelievethattheproposedchangeswillnotresultinthefollowing:
| | Docket No. 315 Amendment 2.c(4) The licensee may proceed with and is No. 31 required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C. Cook Nuclear Plant dated June 4, 1979. These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto. |
| (1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. | | Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee (PNSRC)andtheNuclearSafetyandDesignReviewCommittee (NSDRC).Incompliance withtherequirements of10CFR50.91(b)(1),
| | 9404130015 94040b o~ |
| copiesofthisletterandit'sattachments havebeentransmitted toMr.J.R.PadgettoftheMichiganPublicServiceCommission andtheMichiganDepartment ofPublicHealth.
| | PDR ADOCK 05000315 PDR I ( |
| Mr.W.T.Russell3AEP'NRC:0692CJ Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached. | | |
| Sincerely, EeE.E.FitptrickVicePresident drAttachments cc:A.A.BlindG.CharnoffJ.B.Martin-RegionIIINFEMSectionChiefNRCResidentInspector J.R.Padgett STATEOFOHIO)COUNTYOFFRANKLIN) | | Mr. W. T. Russell 2 AEP:NRC:0692CJ Docket No. 316 ire P otect o Amendment No. 12 2.c(3)(o) The licensee may proceed with and is required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C. Cook Nuclear Plant dated June 4, 1979. These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto. |
| E.E.Fitzpatrick, beingdulysworn,deposesandsaysthatheistheVicePresident oflicenseeIndianaMichiganPowerCompany,thathehasreadtheforegoing Responses totheLICENSEAMENDMENT andknowsthecontentsthereof;andthatsaidcontentsaretruetothebestofhisknowledge andbelief.Subscribed endsworntomebeforethis~dayof19~vssNOTARYPUBLICPilihD.HlLLNOTARYPUBLIC.STATEOFOHIO 0I,~'11~ | | Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained. |
| ATTACHMENT 1TOAEP:NRC:0692CJ DESCRIPTION, REASONS,JUSTIFICATION AND10CFR50.92SIGNIFICANT HAZARDSEVALUATION FORTHECHANGESTOTHELICENSESFORDONALDC.COOKNUCLEARPLANTUNITS1AND2 Attachment 1toAEP:NRC:0692CJ Page1DESCRIPTION OFTHECHANGESThelicensecondition references Table1ofthe1979FireProtection SafetyEvaluation Report(SEE).Table1ofthe1979FireProtection SERisascheduleforthecompletion oftwenty-three modifications requiredtomeetBranchTechnical PositionAuxiliary andPowerConversions SystemsBranch9.5-1(BTPAPCSB9.5-1).Alltwenty-three modifications havebeencompleted andsothisscheduleisnowobsolete. | | It is proposed that the first two sentences of paragraphs 2.c(4) and 2.c(3)(o), above, be deleted. Attachment 1 provides a detailed description of the proposed changes, the reasons for the changes, and our proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92, Attachment 2 contains the existing license condition pages marked to reflect the proposed changes. Attachment 3 contains the proposed, revised license condition pages. |
| Thelicensecondition's reference totheadministrative controlsforfireprotection described inthelicensee's submittals datedJanuary31,1977,andOctober27,1977,isnotbeingchanged.Sincethe1979FireProtection SERwehavemadechangestothreeofthesemodifications asfollows:ItemC-ProvideCascadeRecharinStatioThreecascaderecharging stationswereoriginally installed ontheUnit1633'urbine
| | There are twenty-three schedular modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for Donald C. Cook Nuclear Plant dated June 4, 1979. All twenty-three items have been completed. Three of these items subsequently have been changed, as also discussed in Attachment l. |
| : building, theUnit2609'ranebayandintheplantfiretruckgaragetomeetthiscommitment.
| | We believe that the proposed changes will not result in the following: (1) a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| Theseunitshavesincebeenreplacedwithanaircompressor approvedforbreathing air.Theuseofanaircompressor ispermissible underAppendixAtoBTPAPCSB9.5-1.Item9-FireProofMetalHatchesThehatchesindicated inthetablewereallprotected originally byPyrocrete fireproofing.
| | These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and the Nuclear Safety and Design Review Committee (NSDRC). |
| ThiswaslaterreplacedbyTSImaterialaspartoftheplant'sAppendixRcompliance strategy.
| | In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and it's attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health. |
| InanSERdatedJune17,1988,theNRCacceptedadeviation requestforunratedmetalhatches.WhiletheTSImaterialisstillinplaceonmostofthehatches,itwillnotbereplacedifremovedordamagedandnosurveillance isbeingconducted onthematerial.
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| Item20-DieselFirePumControllers Theoldscreenhouse dieseldrivenfirepumps wereupgradedtobeincompliance withtheSER.Newfirewaterstoragetanks,firepumps,andassociated components havebeeninstalled aspartofthededicated fireprotection watersupply.Theoldscreenhouse dieseldrivenfirepumpswerethenconsidered tobeafixed"backup"firesuppression watersystem.Thisinstallation hasbeenacceptedby,theNRCstaffviatheMarch31,1993,letterforAmendment Nos.171and154.OnMarch16,1994,alettertitled"Revision ofInformation Regarding theBackupFireWaterSupply"wassenttotheNRC.Thisletterexplainsthattheoldscreenhouse dieseldrivenfirepumps,whichtakedirectsuctionfromtheforebaystructure, havebeenexperiencing recurrent operational
| | Mr. W. T. Russell 3 AEP'NRC:0692CJ This letter is submitted pursuant to 10 CFR 50.30(b) and, as such, an oath statement is attached. |
| | Sincerely, Ee Fit E. E. trick p |
| | Vice President dr Attachments cc: A. A. Blind G. Charnoff J. B. Martin - Region III NFEM Section Chief NRC Resident Inspector J. R. Padgett |
| | |
| | STATE OF OHIO) |
| | COUNTY OF FRANKLIN) |
| | E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the foregoing Responses to the LICENSE AMENDMENT and knows the contents thereof; and that said contents are true to the best of his knowledge and belief. |
| | Subscribed end sworn to day of me before this ~ |
| | 19~v s s |
| | NOTARY PUBLIC Pilih D. HlLL NOTARY PUBLIC. STATE OF OHIO |
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| | 0 I |
| | , ~'1 1 |
| | ~ |
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| | ATTACHMENT 1 TO AEP:NRC:0692CJ DESCRIPTION, REASONS, JUSTIFICATION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR THE CHANGES TO THE LICENSES FOR DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 to AEP:NRC:0692CJ Page 1 DESCRIPTION OF THE CHANGES The license condition references Table 1 of the 1979 Fire Protection Safety Evaluation Report (SEE). Table 1 of the 1979 Fire Protection SER is a schedule for the completion of twenty-three modifications required to meet Branch Technical Position Auxiliary and Power Conversions Systems Branch 9.5-1 (BTP APCSB 9.5-1). All twenty-three modifications have been completed and so this schedule is now obsolete. The license condition's reference to the administrative controls for fire protection described in the licensee's submittals dated January 31, 1977, and October 27, 1977, is not being changed. |
| | Since the 1979 Fire Protection SER we have made changes to three of these modifications as follows: |
| | Item C - Provide Cascade Rechar in Statio Three cascade recharging stations were originally installed on the Unit 1 633'urbine building, the Unit 2 609'rane bay and in the plant fire truck garage to meet this commitment. These units have since been replaced with an air compressor approved for breathing air. The use of an air compressor is permissible under Appendix A to BTP APCSB 9.5-1. |
| | Item 9 - Fire Proof Metal Hatches The hatches indicated in the table were all protected originally by Pyrocrete fire proofing. This was later replaced by TSI material as part of the plant's Appendix R compliance strategy. In an SER dated June 17, 1988, the NRC accepted a deviation request for unrated metal hatches. While the TSI material is still in place on most of the hatches, it if will not be replaced removed or damaged and no surveillance is being conducted on the material. |
| | Item 20 - Diesel Fire Pum Controllers The old screenhouse diesel driven firepumps were upgraded to be in compliance with the SER. New fire water storage tanks, fire pumps, and associated components have been installed as part of the dedicated fire protection water supply. The old screenhouse diesel driven fire pumps were then considered to be a fixed "backup" fire suppression water system. |
| | This installation has been accepted by the NRC staff via the March 31, 1993, letter for Amendment Nos. 171 and 154. |
| | On March 16, 1994, a letter titled "Revision of Information Regarding the Backup Fire Water Supply" was sent to the NRC. This letter explains that the old screenhouse diesel driven fire pumps, which take direct suction from the forebay structure, have been experiencing recurrent operational |
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| | to AEP:NRC:0692CJ Page 2 problems due to zebra mussel infestation. Therefore, the old screenhouse diesel driven fire pumps are no longer considered to be a reliable and economically viable backup source of fire suppression water, and other "backup" fire suppression water is available. The old screenhouse diesel driven fire pumps have been retired from fire protection service, REASON FOR THE CHANGES This amendment. was written to delete the license condition reference to Table 1 of the June 4, 1979, SER in paragraph 2,C(4) issued with Amendment No. 31 from Docket No. 315 and to delete the license condition reference to Table 1 of the June 4, 1979, SER in paragraph 2.C(3)(o) issued with Amendment No. 12 from Docket No. 316. |
| | JUSTIFICATION OF THE CHANGES The modifications identified in Table 1 were scheduled to be completed during the first through the fourth refueling outages. These modifications have been implemented and this schedule is now obsolete. |
| | The changes to the modifications that have been implemented are consistent with the intent of 10 CFR 50 Appendix A. The change to Item 7C is acceptable under BTP APCSB 9.5-1, and it is a practical enhancement. The found acceptable by the NRC. |
| | changes to Item 9 has been reviewed and Information regarding the retirement of the old screenhouse diesel driven fire pumps has been provided to the NRC. The "backup" fire suppression water is available and is expected to be acceptable to the NRC. |
| | Our response to BTP APCSB 9.5-1 is in our Fire Protection Program Manual (FPPM). We intend to add to the UFSAR reference to the FPPM, during the next UFSAR update. Thus, any future changes to our response to BTP APCSB 9.5-1 or to our June 4, 1979, Fire Protection Safety Evaluation Report will be subject to a 10 CFR 50.59(a)(2) safety evaluation. |
| | 10 CFR 50 92 Si ificant Hazards Evaluation Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not: |
| | (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. |
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| | to AEP:NRC:0692CJ Page 3 Our evaluation of the proposed change with respect to these criteria is provided below. |
| | Criterion 1 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not involve a significant increase in the probability or consequences of an accident previously analyzed as follows. |
| | Item 7C - The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1. |
| | Item 9 - The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988. |
| | Item 20 - The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos 171 and 154. The |
| | ~ |
| | retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of "backup" fire suppression water. |
| | Criterion 2 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not create the possibility of a new or different kind of accident from any accident previously evaluated as follows. |
| | Item 7C - The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1. |
| | Item 9 - The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988. |
| | Item 20 - The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos. 171 and 154. The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of "backup" fire suppression water. |
| | to AEP:NRC:0692CJ Page 4 Criterion 3 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not involve a significant reduction in a margin of safety as follows. |
| | Item 7C - The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1. Filled spare breathing air bottles are on-site and the local municipal department will provide assistance as needed. |
| | Item 9 - The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988. |
| | Item 20 - The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos. 171 and 154. The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of "backup" fire suppression water. |
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| Attachment 1toAEP:NRC:0692CJ Page2problemsduetozebramusselinfestation.
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| Therefore, theoldscreenhouse dieseldrivenfirepumpsarenolongerconsidered tobeareliableandeconomically viablebackupsourceoffiresuppression water,andother"backup"firesuppression waterisavailable.
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| Theoldscreenhouse dieseldrivenfirepumpshavebeenretiredfromfireprotection service,REASONFORTHECHANGESThisamendment.
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| waswrittentodeletethelicensecondition reference toTable1oftheJune4,1979,SERinparagraph 2,C(4)issuedwithAmendment No.31fromDocketNo.315andtodeletethelicensecondition reference toTable1oftheJune4,1979,SERinparagraph 2.C(3)(o) issuedwithAmendment No.12fromDocketNo.316.JUSTIFICATION OFTHECHANGESThemodifications identified inTable1werescheduled tobecompleted duringthefirstthroughthefourthrefueling outages.Thesemodifications havebeenimplemented andthisscheduleisnowobsolete.
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| Thechangestothemodifications thathavebeenimplemented areconsistent withtheintentof10CFR50AppendixA.ThechangetoItem7Cisacceptable underBTPAPCSB9.5-1,anditisapractical enhancement.
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| ThechangestoItem9hasbeenreviewedandfoundacceptable bytheNRC.Information regarding theretirement oftheoldscreenhouse dieseldrivenfirepumpshasbeenprovidedtotheNRC.The"backup"firesuppression waterisavailable andisexpectedtobeacceptable totheNRC.OurresponsetoBTPAPCSB9.5-1isinourFireProtection ProgramManual(FPPM).WeintendtoaddtotheUFSARreference totheFPPM,duringthenextUFSARupdate.Thus,anyfuturechangestoourresponsetoBTPAPCSB9.5-1ortoourJune4,1979,FireProtection SafetyEvaluation Reportwillbesubjecttoa10CFR50.59(a)(2) safetyevaluation.
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| 10CFR5092SiificantHazardsEvaluation Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or(3)involveasignificant reduction inamarginofsafety.
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| Attachment 1toAEP:NRC:0692CJ Page3Ourevaluation oftheproposedchangewithrespecttothesecriteriaisprovidedbelow.Criterion 1Thisupdateofthefireprotection modifications contained inTable1oftheJuly31,1979,fireprotection SERdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzedasfollows.Item7C-Theuseofanaircompressor ratherthanthecascaderecharging stationsdoesnotadversely impacttheabilitytosupplybreathing airforthefirebrigadeandisacceptable underBTPAPCSB9.5-1.Item9-TheuseofunratedmetalhatcheshasbeenacceptedbytheNRCinaSERdatedJune17,1988.Item20-ThenewfirepumpshavealreadybeenacceptedbytheNRCintheSERdatedMarch31,1993,Amendment Nos~171and154.Theretirement oftheoldscreenhouse dieseldrivenfirepumpsisbasedontheavailability ofanothersupplyof"backup"firesuppression water.Criterion 2Thisupdateofthefireprotection modifications contained inTable1oftheJuly31,1979,fireprotection SERdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated asfollows.Item7C-Theuseofanaircompressor ratherthanthecascaderecharging stationsdoesnotadversely impacttheabilitytosupplybreathing airforthefirebrigadeandisacceptable underBTPAPCSB9.5-1.Item9-TheuseofunratedmetalhatcheshasbeenacceptedbytheNRCinaSERdatedJune17,1988.Item20-ThenewfirepumpshavealreadybeenacceptedbytheNRCintheSERdatedMarch31,1993,Amendment Nos.171and154.Theretirement oftheoldscreenhouse dieseldrivenfirepumpsisbasedontheavailability ofanothersupplyof"backup"firesuppression water.
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| Attachment 1toAEP:NRC:0692CJ Page4Criterion 3Thisupdateofthefireprotection modifications contained inTable1oftheJuly31,1979,fireprotection SERdoesnotinvolveasignificant reduction inamarginofsafetyasfollows.Item7C-Theuseofanaircompressor ratherthanthecascaderecharging stationsdoesnotadversely impacttheabilitytosupplybreathing airforthefirebrigadeandisacceptable underBTPAPCSB9.5-1.Filledsparebreathing airbottlesareon-siteandthelocalmunicipal department willprovideassistance asneeded.Item9-TheuseofunratedmetalhatcheshasbeenacceptedbytheNRCinaSERdatedJune17,1988.Item20-ThenewfirepumpshavealreadybeenacceptedbytheNRCintheSERdatedMarch31,1993,Amendment Nos.171and154.Theretirement oftheoldscreenhouse dieseldrivenfirepumpsisbasedontheavailability ofanothersupplyof"backup"firesuppression water.
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Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld
ML17326A1161999-09-10010 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0921999-08-17017 August 1999
Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections
ML17325B6041999-05-21021 May 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements
ML17325B5511999-04-19019 April 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17335A3661998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys
ML17335A3631998-12-0303 December 1998
Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors
ML17335A3591998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17335A3561998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A2631998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp
ML17335A2761998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2671998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled
ML17335A2311998-09-14014 September 1998
Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A1901998-08-28028 August 1998
Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs
ML17334A7471998-06-10010 June 1998
Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change
ML17334B7011998-03-0303 March 1998
Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases
ML17334B6561997-10-0808 October 1997
Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl
ML17333B0431997-09-19019 September 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9831997-08-11011 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2101997-08-0101 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS
ML17333A8281997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8311997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted
ML17333A7121996-12-20020 December 1996
Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency
ML17334B5941996-07-11011 July 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl
ML17334B5901996-06-19019 June 1996
Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking.
ML17334B5891996-06-11011 June 1996
Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05
ML17333A4201996-04-0808 April 1996
Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1
ML17333A3551996-03-12012 March 1996
Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
ML17334B5751996-02-29029 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl
ML17334B5741996-02-26026 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks
ML17333A3201996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor
ML17333A3151996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test
ML17333A2641996-01-12012 January 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves
ML17333A2391995-12-19019 December 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B
ML17332B0111995-11-10010 November 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations
ML17332A9971995-10-20020 October 1995
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV
ML17332A9111995-08-0606 August 1995
Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified
ML17334B5561995-08-0404 August 1995
Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld
ML17332A8271995-06-30030 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1
ML17334B5501995-06-20020 June 1995
License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07
ML17332A7991995-06-15015 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H
ML17334B5481995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria
ML17334B5461995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08
ML17332A7661995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty
ML17332A7741995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1
ML17332A7771995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly
1999-09-23
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases
ML17335A5591999-10-11011 October 1999
Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes
ML17335A5411999-10-0101 October 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl
ML17326A1571999-09-23023 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures
ML17326A1421999-09-17017 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld
ML17326A1161999-09-10010 September 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling
ML17326A0921999-08-17017 August 1999
Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections
ML17325B6041999-05-21021 May 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements
ML17325B5511999-04-19019 April 1999
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs
ML17335A3661998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys
ML17335A3631998-12-0303 December 1998
Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors
ML17335A3591998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17335A3561998-12-0303 December 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A2631998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp
ML17335A2761998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2671998-10-0808 October 1998
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled
ML17335A2311998-09-14014 September 1998
Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A1901998-08-28028 August 1998
Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs
ML17334A7471998-06-10010 June 1998
Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change
ML17334B7011998-03-0303 March 1998
Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases
ML17334B6561997-10-0808 October 1997
Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl
ML17333B0431997-09-19019 September 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9831997-08-11011 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2101997-08-0101 August 1997
Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS
ML17333A8281997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8311997-03-26026 March 1997
Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted
ML17333A7121996-12-20020 December 1996
Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency
ML17334B5941996-07-11011 July 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl
ML17334B5901996-06-19019 June 1996
Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking.
ML17334B5891996-06-11011 June 1996
Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05
ML17333A4201996-04-0808 April 1996
Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1
ML17333A3551996-03-12012 March 1996
Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5
ML17334B5751996-02-29029 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl
ML17334B5741996-02-26026 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks
ML17333A3201996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor
ML17333A3151996-02-22022 February 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test
ML17333A2641996-01-12012 January 1996
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves
ML17333A2391995-12-19019 December 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B
ML17332B0111995-11-10010 November 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations
ML17332A9971995-10-20020 October 1995
Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV
ML17332A9111995-08-0606 August 1995
Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified
ML17334B5561995-08-0404 August 1995
Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld
ML17332A8271995-06-30030 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1
ML17334B5501995-06-20020 June 1995
License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07
ML17332A7991995-06-15015 June 1995
Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H
ML17334B5481995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria
ML17334B5461995-05-26026 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08
ML17332A7661995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty
ML17332A7741995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1
ML17332A7771995-05-25025 May 1995
Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly
1999-09-23
[Table view] |
Text
ACCELERATED DI TRIBUTION DEMONST ATION SYSTEM 4~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9404130015 DOC.DATE: 94/04/06 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 & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to licenses DPR-58 & DPR-74,proposing to remove license condition reference to table 1 of fire D protection safety evaluation rept, for Cook Nuclear Plant, approved on 790604 & issued on 790731.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 D HICKMAN,J 2 2 INTERNAL: NRR/DE/EELB 1 1 NRR/DORS/OTS B 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OC/LFDCB 1 0 OGC/HDS2 1 0 E~IL 01 1 1 EXTERNAL NRC PDR 1 1 NSIC 1 1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14
Indiana Michigan Power Company
~
P.O. Box 16631 Coiumbus, OH 43216 INWAl84 MCHII6'HAM ltaOMKR AEP:NRC'0692CJ Donald C. Cook Nuclear Plant Units 1 and 2 Docket No. 50-315 and 50-316 License No. DPR-58 and DPR-74 LICENSE AMENDMENT U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: W. T. Russell April 6, 1994
Dear Mr. Russell:
This letter and its attachments constitute an application for amendment to the licenses for Donald C. Cook Nuclear Plant, Units 1 and 2. We propose to remove the license condition reference to Table 1 of the Fire Protection Safety Evaluation Report for Cook Nuclear Plant, approved on June 4, 1979, and issued under a cover letter dated July 31, 1979. The objectives of this 1979 license condition have been achieved. The license conditions'eference to the administrative controls for fire protection, as described in the licensee's submittals dated January 31, 1977, and October 27, 1977, will remain. These license conditions currently read as follows:
Docket No. 315 Amendment 2.c(4) The licensee may proceed with and is No. 31 required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C. Cook Nuclear Plant dated June 4, 1979. These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto.
Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.
9404130015 94040b o~
PDR ADOCK 05000315 PDR I (
Mr. W. T. Russell 2 AEP:NRC:0692CJ Docket No. 316 ire P otect o Amendment No. 12 2.c(3)(o) The licensee may proceed with and is required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C. Cook Nuclear Plant dated June 4, 1979. These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto.
Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.
It is proposed that the first two sentences of paragraphs 2.c(4) and 2.c(3)(o), above, be deleted. Attachment 1 provides a detailed description of the proposed changes, the reasons for the changes, and our proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92, Attachment 2 contains the existing license condition pages marked to reflect the proposed changes. Attachment 3 contains the proposed, revised license condition pages.
There are twenty-three schedular modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for Donald C. Cook Nuclear Plant dated June 4, 1979. All twenty-three items have been completed. Three of these items subsequently have been changed, as also discussed in Attachment l.
We believe that the proposed changes will not result in the following: (1) a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC) and the Nuclear Safety and Design Review Committee (NSDRC).
In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and it's attachments have been transmitted to Mr. J. R. Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.
Mr. W. T. Russell 3 AEP'NRC:0692CJ This letter is submitted pursuant to 10 CFR 50.30(b) and, as such, an oath statement is attached.
Sincerely, Ee Fit E. E. trick p
Vice President dr Attachments cc: A. A. Blind G. Charnoff J. B. Martin - Region III NFEM Section Chief NRC Resident Inspector J. R. Padgett
STATE OF OHIO)
COUNTY OF FRANKLIN)
E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the foregoing Responses to the LICENSE AMENDMENT and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed end sworn to day of me before this ~
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NOTARY PUBLIC Pilih D. HlLL NOTARY PUBLIC. STATE OF OHIO
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ATTACHMENT 1 TO AEP:NRC:0692CJ DESCRIPTION, REASONS, JUSTIFICATION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR THE CHANGES TO THE LICENSES FOR DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 to AEP:NRC:0692CJ Page 1 DESCRIPTION OF THE CHANGES The license condition references Table 1 of the 1979 Fire Protection Safety Evaluation Report (SEE). Table 1 of the 1979 Fire Protection SER is a schedule for the completion of twenty-three modifications required to meet Branch Technical Position Auxiliary and Power Conversions Systems Branch 9.5-1 (BTP APCSB 9.5-1). All twenty-three modifications have been completed and so this schedule is now obsolete. The license condition's reference to the administrative controls for fire protection described in the licensee's submittals dated January 31, 1977, and October 27, 1977, is not being changed.
Since the 1979 Fire Protection SER we have made changes to three of these modifications as follows:
Item C - Provide Cascade Rechar in Statio Three cascade recharging stations were originally installed on the Unit 1 633'urbine building, the Unit 2 609'rane bay and in the plant fire truck garage to meet this commitment. These units have since been replaced with an air compressor approved for breathing air. The use of an air compressor is permissible under Appendix A to BTP APCSB 9.5-1.
Item 9 - Fire Proof Metal Hatches The hatches indicated in the table were all protected originally by Pyrocrete fire proofing. This was later replaced by TSI material as part of the plant's Appendix R compliance strategy. In an SER dated June 17, 1988, the NRC accepted a deviation request for unrated metal hatches. While the TSI material is still in place on most of the hatches, it if will not be replaced removed or damaged and no surveillance is being conducted on the material.
Item 20 - Diesel Fire Pum Controllers The old screenhouse diesel driven firepumps were upgraded to be in compliance with the SER. New fire water storage tanks, fire pumps, and associated components have been installed as part of the dedicated fire protection water supply. The old screenhouse diesel driven fire pumps were then considered to be a fixed "backup" fire suppression water system.
This installation has been accepted by the NRC staff via the March 31, 1993, letter for Amendment Nos. 171 and 154.
On March 16, 1994, a letter titled "Revision of Information Regarding the Backup Fire Water Supply" was sent to the NRC. This letter explains that the old screenhouse diesel driven fire pumps, which take direct suction from the forebay structure, have been experiencing recurrent operational
to AEP:NRC:0692CJ Page 2 problems due to zebra mussel infestation. Therefore, the old screenhouse diesel driven fire pumps are no longer considered to be a reliable and economically viable backup source of fire suppression water, and other "backup" fire suppression water is available. The old screenhouse diesel driven fire pumps have been retired from fire protection service, REASON FOR THE CHANGES This amendment. was written to delete the license condition reference to Table 1 of the June 4, 1979, SER in paragraph 2,C(4) issued with Amendment No. 31 from Docket No. 315 and to delete the license condition reference to Table 1 of the June 4, 1979, SER in paragraph 2.C(3)(o) issued with Amendment No. 12 from Docket No. 316.
JUSTIFICATION OF THE CHANGES The modifications identified in Table 1 were scheduled to be completed during the first through the fourth refueling outages. These modifications have been implemented and this schedule is now obsolete.
The changes to the modifications that have been implemented are consistent with the intent of 10 CFR 50 Appendix A. The change to Item 7C is acceptable under BTP APCSB 9.5-1, and it is a practical enhancement. The found acceptable by the NRC.
changes to Item 9 has been reviewed and Information regarding the retirement of the old screenhouse diesel driven fire pumps has been provided to the NRC. The "backup" fire suppression water is available and is expected to be acceptable to the NRC.
Our response to BTP APCSB 9.5-1 is in our Fire Protection Program Manual (FPPM). We intend to add to the UFSAR reference to the FPPM, during the next UFSAR update. Thus, any future changes to our response to BTP APCSB 9.5-1 or to our June 4, 1979, Fire Protection Safety Evaluation Report will be subject to a 10 CFR 50.59(a)(2) safety evaluation.
10 CFR 50 92 Si ificant Hazards Evaluation Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
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to AEP:NRC:0692CJ Page 3 Our evaluation of the proposed change with respect to these criteria is provided below.
Criterion 1 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not involve a significant increase in the probability or consequences of an accident previously analyzed as follows.
Item 7C - The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1.
Item 9 - The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988.
Item 20 - The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos 171 and 154. The
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retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of "backup" fire suppression water.
Criterion 2 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not create the possibility of a new or different kind of accident from any accident previously evaluated as follows.
Item 7C - The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1.
Item 9 - The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988.
Item 20 - The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos. 171 and 154. The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of "backup" fire suppression water.
to AEP:NRC:0692CJ Page 4 Criterion 3 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not involve a significant reduction in a margin of safety as follows.
Item 7C - The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1. Filled spare breathing air bottles are on-site and the local municipal department will provide assistance as needed.
Item 9 - The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988.
Item 20 - The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos. 171 and 154. The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of "backup" fire suppression water.
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