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| | issue date = 05/26/1995 | | | issue date = 05/26/1995 |
| | title = 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 | | | title = 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 |
| | 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 = 10 | | | page count = 10 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:cr,~'>Iyes!~i,(iIRIORITY1CCELERATED RIDSPROCESSING) | | {{#Wiki_filter:cr,~ |
| REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)0ACCESSION NBR:9506060449 DOC.DATE: | | I yes |
| 95/05/26NOTARIZED: | | ! ~i, RIORITY CCELERATED RIDS PROCESSING) 1 (iI REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| YESDOCKETNFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
| | ACCESSION NBR:9506060449 DOC.DATE: 95/05/26 NOTARIZED: YES DOCKET N 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 P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) 5~ |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganElePRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)5~
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstolicensesDPR-586DPR-74,modifyin techspecs3/4.3.1(ReactorTripSysInstrumentation) | | Application for amends to licenses DPR-58 6 DPR-74,modifyin tech specs 3/4.3.1 (Reactor Trip Sys Instrumentation) I 3/4.3.2 (ESFAS Instrumentation) S bases to relocate tables of response time limits to UFSAR,per GL 93-08. 0 DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR TITLE: OR Submittal: General Distribution l ENCL 7 SIZE: (0+'VV t |
| I3/4.3.2(ESFASInstrumentation)
| | R NOTES: |
| SbasestorelocatetablesofresponsetimelimitstoUFSAR,per GL93-08.DISTRIBUTION CODE:AOOIDCOPIESRECEIVED:LTR lENCL7SIZE:(0+'VVTITLE:ORSubmittal:
| | I RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 J 1 1 INTER : FILE CE 1 1 NRR/DE/EMCB 1 1 CH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| GeneralDistribution RtNOTES:IRECIPIENT IDCODE/NAME PD3-1LAJINTER:FILECECH/HICBNRR/DSSA/SRXB OGC/HDS2EXTERNAL:
| | C U |
| NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL1111111111DCUNNOTETOALL"BIDS"RECIPIENTS:
| | N NOTE TO ALL"BIDS" RECIPIENTS: |
| PLEASEHELPUSTOREDUCEiVASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPI-37(EXT.504-2083)TOELIXIINATEYOURXrhiIEPRO%IDISTRIBUTION LISTSI:ORDOC!'MENTSYOUDON"I'EED!TOTALNUMBEROFCOPIESREQUIRED:
| | PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2083 ) TO ELIXIINATE YOUR XrhiIE PRO%I DISTRIBUTION LISTS I:OR DOC! 'MENTS YOU DON"I'EED! |
| LTTR12ENCL11 0:~<e0'h IndianaMichiganPowerCompanyP.O.Box16631Columbus, OH432165May26,1995AEP'NRC:1210 DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 |
| DonaldC.CookNuclearPlantUnits1and2RELOCATION OFTECHNICAL SPECIFICATION TABLESOFINSTRUMENT RESPONSETIMELIMITS(GENERICLETTER93-08)Thisletteranditsattachments constitute anapplication foramendment ofthetechnical specifications (T/Ss)fortheDonaldC.CookNuclearPlantunits1and2.Specifically, weproposetomodifyT/Ss3/4.3.1(ReactorTripSystemInstrumentation) and3/4.3.2(Engineered SafetyFeatureActuation SystemInstrumentation) andtheiraccompanying Bases,torelocatethetablesofresponsetimelimitstotheUFSAR.Thesechangesaresubmitted asalineitemimprovement inaccordance withtheguidanceofGenericLetter93-08.Attachment 1providesadetaileddescription oftheproposedchanges,justification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarkedtoreflecttheproposedchanges.Attachment 3containstheproposedrevisedT/Spages.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
| | |
| TheproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andtheNuclearSafetyandDesignReviewCommittee.
| | 0: 0 'h |
| 950b0b0449 95052bPDRADQCK,050003i5 P"'DR 01 U.S;NuclearRegulatory Commission Page2AEP'NRC:1210 Incompliance withtherequirements of10CFR50.91(b)(1), | | ~ <e |
| copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.Sincerely, VicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS~~@DAYOF1995NotaryPulicehAttachments CC;A.A.BlindG.CharnoffJ.B.MartinNFEMSectionChiefNRCResidentInspector
| | |
| -BridgmanJ.R.Padgett 00egQrI/~~rHl,P~ | | Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 5 |
| ATTACHMENT 1TOAEP:NRC:1210 JUSTIFICATION AND10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2TECHNICAL SPECIFICATIONS 95O6Q60449 II ATTACHMENT 1TOAEP:NRC:1210 Page1DESCRIPTION OFCHANGESUnits1and2technical specification (T/S)Tables3.3-2(ReactorTripSystemInstrumentation ResponseTimes)and3~3-5(Engineered SafetyFeaturesResponseTimes)aredeleted.Asdiscussed below,theinformation currently contained inthesetableswillberelocated totheUFSAR.2.Units1and2T/Ss3.3.1.1and3.3.2.1aremodifiedtoremovereference toTables3.3-2and3.3-5,respectively. | | May 26, 1995 AEP'NRC:1210 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| 3.Units1and2BasespageB2-7ismodifiedtoremovespecifictimeresponseinformation fromthedescription ofthereactorcoolantbusundervoltage andunderfrequency reactortrips.4.Unit1BasespageB3/43-1andunit2BasespagesB3/43-1andB3/43-laarerevisedtodeletediscussion ofresponsetimesdesignated as"notapplicable" andresponsetimesassociated withRWSTandVCTvalves.5.Units1and2T/S4.3.1.1.3 ismodifiedtoincludeafootnotecurrently locatedintheresponsetimetable(Table3.3-2).Thefootnotestates:"Neutrondetectors areexemptfromresponsetimetesting.Responsetimeoftheneutronfluxsignalportionofthechannelshallbemeasuredfromdetectoroutputorinputoffirstelectronic component inchannel." | | Donald C. Cook Nuclear Plant Units 1 and 2 RELOCATION OF TECHNICAL SPECIFICATION TABLES OF INSTRUMENT RESPONSE TIME LIMITS (GENERIC LETTER 93-08) |
| Footnotes associated withprevioussurveillance intervalextensions weredeletedfromUnit2pages3/43-1and3/43-14.SODJUSTIFCATION0CGESGenericLetter(GL)93-08wasissuedbytheNRCtoprovideguidancetolicensees forrequesting alicenseamendment torelocatetablesofinstrument responsetimelimitsfromtheT/SstotheUFSAR.TheNRCdeveloped thislineitemimprovement inresponsetoT/Sproposals byapplicants foroperating licenses. | | This letter and its attachments constitute an application for amendment of the technical specifications (T/Ss) for the Donald C. |
| Asdiscussed intheGL,licensees'were encouraged toproposeT/Schangesthatareconsistent withtheguidancegivenintheenclosures totheGL.Thelimitingconditions foroperation (LCOs)forthereactortripandengineered safetyfeaturesactuation system(ESFAS)instruments requirethatthesesystemsbeoperablewithresponsetimesasspecified intheT/Stables.Thesurveillance requirements specifythatthelicenseetestthesesystemsandverifythattheresponse ATTACHMENT 1TOAEP'NRC'1210 Page2timeofeachfunctioniswithinitslimits.Relocating thetablesofthereactortripandESFASinstrument responsetimelimitsfromtheT/SstotheUFSARwillnotalterthesesurveillance requirements.
| | Cook Nuclear Plant units 1 and 2. Specifically, we propose to modify T/Ss 3/4.3.1 (Reactor Trip System Instrumentation) and 3/4.3.2 (Engineered Safety Feature Actuation System Instrumentation) and their accompanying Bases, to relocate the tables of response time limits to the UFSAR. These changes are submitted as a line item improvement in accordance with the guidance of Generic Letter 93-08. |
| TheUFSARwillnowaddresstheresponsetimelimitsforthereactortripandESFASinstruments, including thosechannelsforwhichtheresponsetimelimitisindicated as"notapplicable."
| | Attachment 1 provides a detailed description of the proposed changes, justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment 3 contains the proposed revised T/S pages. |
| TheUFSARwillalsoclarifyresponsetimelimitswherefootnotes areincludedinthetablesthatdescribehowthoselimitsareapplied.ThisT/Schangeallowsustoadministratively control"changestotheresponsetimelimitsforthereactortripandESFASinstruments inaccordance withtheprovisions of10CFR50.59withouttheneedtoprocessaT/Samendment request.Thepresenttimeresponsesurveillance requirements (T/Ss4.3.1.1.3 and4.3.2.1.3) donotreference theresponsetimetables.Therefore, thesurveillance requirements didnotneedtobemodifiedtoimplement thechanges.However,afootnoteinthereactortripresponsetimetable(Table3.3-2)containsastatement exempting neutrondetectors fromresponsetimetesting.Sothatthisexemption willbemaintained, wehavemodifiedsurveillance requirement 4.3.1.1.3 toincludethetextcurrently inthefootnote.
| | We believe that the proposed changes will not result in (1) a significant change in the types of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| Thisisinaccordance withtherecommendations ofGL93-08.Asrecommended byGL93-08,wehaveconfirmed thatplantprocedures forresponsetimetestingincludeacceptance criteriathatreflectthereactortripandESFAS.response timelimitsinthetablesbeingrelocated fromtheT/SstotheUFSAR.Following NRCapproval, theresponsetimelimitswillbeincludedintheUFSARinaccordance with10CFR50.71(e).
| | The proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee. |
| 0C50EVLUATONPer10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or(3)involveasignificant reduction inamarginofsafety.
| | 950b0b0449 95052b PDR ADQCK,050003i5 |
| ATTACHMENT 1TOAEP:NRC:1210 Page3Criterion 1Theproposedchangeswillnotinvolveasignificant increaseintheprobability ofanaccidentpreviously evaluated becausethechangeswillnotresultinachangetoanyoftheprocessvariables thatmightinitiateanaccident. | | "'DR P |
| Therearenophysicalchangestotheplantassociated withthisT/Schange.Theconsequences ofanaccidentpreviously evaluated willnotbeincreased becausethechangessimplyallowrelocation ofresponsetimelimitstotheUFSAR.TimeresponsetestingwillcontinuetoberequiredbytheT/Ss.Anychangestotheresponsetimevalueswillbemadeinaccordance withtherequirements of10CFR50.59.ItisnotedthattheseT/Schangeshavepreviously beendetermined acceptable bytheNRCinGL93-08.CRITERION 2Theproposedchangeswillnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated becausethechangeswillinvolvenophysicalchangestotheplantnoranychangesinplantoperations.
| | |
| TimeresponsetestingwillcontinuetoberequiredbytheT/Ss.Anychangestothetimeresponsevalueswillbemadeinaccordance withtherequirements of10CFR50.59.Itisnotedthatthesechangeshavepreviously beendetermined acceptable bytheNRCinGL93>>08.CRITERION 3Theproposedamendment willnotinvolveasignificant reduction inamarginofsafetybecausetimeresponsetestingwillcontinuetoberequiredbytheT/Ss.Anychangestotheresponsetimevalueswillbemadeinaccordance withtherequirements of10CFR50.59.Itisnotedthatthesechangeshavepreviously beendetermined acceptable bytheNRCinGL93-08.}}
| | 0 1 |
| | |
| | U. S; Nuclear Regulatory Commission AEP'NRC:1210 Page 2 In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health. |
| | Sincerely, Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ~~@ DAY OF 1995 Notary Pu lic eh Attachments CC; A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett |
| | |
| | r 0 0 e gQ I/~ |
| | ~r H |
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| | ,P ~ |
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| | ATTACHMENT 1 TO AEP:NRC:1210 JUSTIFICATION AND 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS 95O6Q60449 II |
| | |
| | ATTACHMENT 1 TO AEP:NRC:1210 Page 1 DESCRIPTION OF CHANGES Units 1 and 2 technical specification (T/S) Tables 3. 3-2 (Reactor Trip System Instrumentation Response Times) and 3 3- ~ |
| | 5 (Engineered Safety Features Response Times) are deleted. |
| | As discussed below, the information currently contained in these tables will be relocated to the UFSAR. |
| | : 2. Units 1 and 2 T/Ss 3.3.1.1 and 3.3.2.1 are modified to remove reference to Tables 3.3-2 and 3.3-5, respectively. |
| | : 3. Units 1 and 2 Bases page B 2-7 is modified to remove specific time response information from the description of the reactor coolant bus undervoltage and underfrequency reactor trips. |
| | : 4. Unit 1 Bases page B 3/4 3-1 and unit 2 Bases pages B 3/4 3-1 and B 3/4 3-la are revised to delete discussion of response times designated as "not applicable" and response times associated with RWST and VCT valves. |
| | : 5. Units 1 and 2 T/S 4.3.1.1.3 is modified to include a footnote currently located in the response time table (Table 3.3-2). |
| | The footnote states: |
| | "Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel." |
| | Footnotes associated with previous surveillance interval extensions were deleted from Unit 2 pages 3/4 3-1 and 3/4 3-14. |
| | SO D JUSTIF CATION 0 C GES Generic Letter (GL) 93-08 was issued by the NRC to provide guidance to licensees for requesting a license amendment to relocate tables of instrument response time limits from the T/Ss to the UFSAR. The NRC developed this line item improvement in response to T/S proposals by applicants for operating licenses. As discussed in the GL, licensees'were encouraged to propose T/S changes that are consistent with the guidance given in the enclosures to the GL. |
| | The limiting conditions for operation (LCOs) for the reactor trip and engineered safety features actuation system (ESFAS) instruments require that these systems be operable with response times as specified in the T/S tables. The surveillance requirements specify that the licensee test these systems and verify that the response |
| | |
| | ATTACHMENT 1 TO AEP'NRC'1210 Page 2 time of each function is within its limits. Relocating the tables of the reactor trip and ESFAS instrument response time limits from the T/Ss to the UFSAR will not alter these surveillance requirements. The UFSAR will now address the response time limits for the reactor trip and ESFAS instruments, including those channels for which the response time limit is indicated as "not applicable." The UFSAR will also clarify response time limits where footnotes are included in the tables that describe how those limits are applied. This T/S change allows us to administratively control" changes to the response time limits for the reactor trip and ESFAS instruments in accordance with the provisions of 10 CFR 50.59 without the need to process a T/S amendment request. |
| | The present time response surveillance requirements (T/Ss 4.3.1.1.3 and 4.3.2.1.3) do not reference the response time tables. |
| | Therefore, the surveillance requirements did not need to be modified to implement the changes. However, a footnote in the reactor trip response time table (Table 3.3-2) contains a statement exempting neutron detectors from response time testing. So that this exemption will be maintained, we have modified surveillance requirement 4.3.1.1.3 to include the text currently in the footnote. This is in accordance with the recommendations of GL 93-08. |
| | As recommended by GL 93-08, we have confirmed that plant procedures for response time testing include acceptance criteria that reflect the reactor trip and ESFAS.response time limits in the tables being relocated from the T/Ss to the UFSAR. Following NRC approval, the response time limits will be included in the UFSAR in accordance with 10 CFR 50.71(e). |
| | 0 C 50 EV LUAT ON Per 10 CFR 50.92, a proposed amendment will not involve a significant not: |
| | hazards consideration if the proposed amendment does (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. |
| | |
| | ATTACHMENT 1 TO AEP:NRC:1210 Page 3 Criterion 1 The proposed changes will not involve a significant increase in the probability of an accident previously evaluated because the changes will not result in a change to any of the process variables that might initiate an accident. There are no physical changes to the plant associated with this T/S change. The consequences of an accident previously evaluated will not be increased because the changes simply allow relocation of response time limits to the UFSAR. Time response testing will continue to be required by the T/Ss. Any changes to the response time values will be made in accordance with the requirements of 10 CFR 50.59. It is noted that these T/S changes have previously been determined acceptable by the NRC in GL 93-08. |
| | CRITERION 2 The proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated because the changes will involve no physical changes to the plant nor any changes in plant operations. Time response testing will continue to be required by the T/Ss. Any changes to the time response values will be made in accordance with the requirements of 10 CFR 50.59. It is noted that these changes have previously been determined acceptable by the NRC in GL 93>>08. |
| | CRITERION 3 The proposed amendment will not involve a significant reduction in a margin of safety because time response testing will continue to be required by the T/Ss. Any changes to the response time values will be made in accordance with the requirements of 10 CFR 50.59. |
| | It is noted that these changes have previously been determined acceptable by the NRC in GL 93-08.}} |
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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] |
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ACCESSION NBR:9506060449 DOC.DATE: 95/05/26 NOTARIZED: YES DOCKET N 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 P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) 5~
SUBJECT:
Application for amends to licenses DPR-58 6 DPR-74,modifyin tech specs 3/4.3.1 (Reactor Trip Sys Instrumentation) I 3/4.3.2 (ESFAS Instrumentation) S bases to relocate tables of response time limits to UFSAR,per GL 93-08. 0 DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR TITLE: OR Submittal: General Distribution l ENCL 7 SIZE: (0+'VV t
R NOTES:
I RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 J 1 1 INTER : FILE CE 1 1 NRR/DE/EMCB 1 1 CH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
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N NOTE TO ALL"BIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2083 ) TO ELIXIINATE YOUR XrhiIE PRO%I DISTRIBUTION LISTS I:OR DOC! 'MENTS YOU DON"I'EED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11
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Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 5
May 26, 1995 AEP'NRC:1210 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 RELOCATION OF TECHNICAL SPECIFICATION TABLES OF INSTRUMENT RESPONSE TIME LIMITS (GENERIC LETTER 93-08)
This letter and its attachments constitute an application for amendment of the technical specifications (T/Ss) for the Donald C.
Cook Nuclear Plant units 1 and 2. Specifically, we propose to modify T/Ss 3/4.3.1 (Reactor Trip System Instrumentation) and 3/4.3.2 (Engineered Safety Feature Actuation System Instrumentation) and their accompanying Bases, to relocate the tables of response time limits to the UFSAR. These changes are submitted as a line item improvement in accordance with the guidance of Generic Letter 93-08.
Attachment 1 provides a detailed description of the proposed changes, justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92. Attachment 2 contains the existing T/S pages marked to reflect the proposed changes. Attachment 3 contains the proposed revised T/S pages.
We believe that the proposed changes will not result in (1) a significant change in the types of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
The proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee.
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U. S; Nuclear Regulatory Commission AEP'NRC:1210 Page 2 In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.
Sincerely, Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ~~@ DAY OF 1995 Notary Pu lic eh Attachments CC; A. A. Blind G. Charnoff J. B. Martin NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett
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ATTACHMENT 1 TO AEP:NRC:1210 JUSTIFICATION AND 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS 95O6Q60449 II
ATTACHMENT 1 TO AEP:NRC:1210 Page 1 DESCRIPTION OF CHANGES Units 1 and 2 technical specification (T/S) Tables 3. 3-2 (Reactor Trip System Instrumentation Response Times) and 3 3- ~
5 (Engineered Safety Features Response Times) are deleted.
As discussed below, the information currently contained in these tables will be relocated to the UFSAR.
- 2. Units 1 and 2 T/Ss 3.3.1.1 and 3.3.2.1 are modified to remove reference to Tables 3.3-2 and 3.3-5, respectively.
- 3. Units 1 and 2 Bases page B 2-7 is modified to remove specific time response information from the description of the reactor coolant bus undervoltage and underfrequency reactor trips.
- 4. Unit 1 Bases page B 3/4 3-1 and unit 2 Bases pages B 3/4 3-1 and B 3/4 3-la are revised to delete discussion of response times designated as "not applicable" and response times associated with RWST and VCT valves.
- 5. Units 1 and 2 T/S 4.3.1.1.3 is modified to include a footnote currently located in the response time table (Table 3.3-2).
The footnote states:
"Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel."
Footnotes associated with previous surveillance interval extensions were deleted from Unit 2 pages 3/4 3-1 and 3/4 3-14.
SO D JUSTIF CATION 0 C GES Generic Letter (GL) 93-08 was issued by the NRC to provide guidance to licensees for requesting a license amendment to relocate tables of instrument response time limits from the T/Ss to the UFSAR. The NRC developed this line item improvement in response to T/S proposals by applicants for operating licenses. As discussed in the GL, licensees'were encouraged to propose T/S changes that are consistent with the guidance given in the enclosures to the GL.
The limiting conditions for operation (LCOs) for the reactor trip and engineered safety features actuation system (ESFAS) instruments require that these systems be operable with response times as specified in the T/S tables. The surveillance requirements specify that the licensee test these systems and verify that the response
ATTACHMENT 1 TO AEP'NRC'1210 Page 2 time of each function is within its limits. Relocating the tables of the reactor trip and ESFAS instrument response time limits from the T/Ss to the UFSAR will not alter these surveillance requirements. The UFSAR will now address the response time limits for the reactor trip and ESFAS instruments, including those channels for which the response time limit is indicated as "not applicable." The UFSAR will also clarify response time limits where footnotes are included in the tables that describe how those limits are applied. This T/S change allows us to administratively control" changes to the response time limits for the reactor trip and ESFAS instruments in accordance with the provisions of 10 CFR 50.59 without the need to process a T/S amendment request.
The present time response surveillance requirements (T/Ss 4.3.1.1.3 and 4.3.2.1.3) do not reference the response time tables.
Therefore, the surveillance requirements did not need to be modified to implement the changes. However, a footnote in the reactor trip response time table (Table 3.3-2) contains a statement exempting neutron detectors from response time testing. So that this exemption will be maintained, we have modified surveillance requirement 4.3.1.1.3 to include the text currently in the footnote. This is in accordance with the recommendations of GL 93-08.
As recommended by GL 93-08, we have confirmed that plant procedures for response time testing include acceptance criteria that reflect the reactor trip and ESFAS.response time limits in the tables being relocated from the T/Ss to the UFSAR. Following NRC approval, the response time limits will be included in the UFSAR in accordance with 10 CFR 50.71(e).
0 C 50 EV LUAT ON Per 10 CFR 50.92, a proposed amendment will not involve a significant not:
hazards consideration if the proposed amendment does (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.
ATTACHMENT 1 TO AEP:NRC:1210 Page 3 Criterion 1 The proposed changes will not involve a significant increase in the probability of an accident previously evaluated because the changes will not result in a change to any of the process variables that might initiate an accident. There are no physical changes to the plant associated with this T/S change. The consequences of an accident previously evaluated will not be increased because the changes simply allow relocation of response time limits to the UFSAR. Time response testing will continue to be required by the T/Ss. Any changes to the response time values will be made in accordance with the requirements of 10 CFR 50.59. It is noted that these T/S changes have previously been determined acceptable by the NRC in GL 93-08.
CRITERION 2 The proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated because the changes will involve no physical changes to the plant nor any changes in plant operations. Time response testing will continue to be required by the T/Ss. Any changes to the time response values will be made in accordance with the requirements of 10 CFR 50.59. It is noted that these changes have previously been determined acceptable by the NRC in GL 93>>08.
CRITERION 3 The proposed amendment will not involve a significant reduction in a margin of safety because time response testing will continue to be required by the T/Ss. Any changes to the response time values will be made in accordance with the requirements of 10 CFR 50.59.
It is noted that these changes have previously been determined acceptable by the NRC in GL 93-08.
