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| | issue date = 04/07/1989 | | | issue date = 04/07/1989 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74,revising Tech Specs Re Reporting Requirements on Primary Coolant Iodine Spikes,Per Generic Ltr 85-19 | | | title = Application for Amends to Licenses DPR-58 & DPR-74,revising Tech Specs Re Reporting Requirements on Primary Coolant Iodine Spikes,Per Generic Ltr 85-19 |
| | author name = ALEXICH M P | | | author name = Alexich M |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = MURLEY T E | | | addressee name = Murley T |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000315, 05000316 | | | docket = 05000315, 05000316 |
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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 = 9 | | | page count = 9 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:gcCELZRATED D1SIRIBU'EON DEMONSTRATIO'.i SYSTEMREGULRTCINFORMATION DISTRIBUTION+STEM (RIDE)ACCESSION NBR:8904210210 | | {{#Wiki_filter:gc CELZRATED D1SIRIBU'EON DE MON STRATIO'.i SYSTEM REGULRTC INFORMATION DISTRIBUTION+STEM (RIDE) |
| ,DOC.DATE: | | ACCESSION NBR:8904210210 ,DOC.DATE: 89/04/07 NOTARIZED: NO DOCKET FACIL:50-31$ Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana a Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411 |
| 89/04/07NOTARIZED: | |
| NODOCKETFACIL:50-31$
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| DonaldC.CookNuclearPowerPlant,Unit1,Indiana60500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.
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| IndianaMichiganPowerCo.(formerly IndianaaMichiganEleRECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
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| OfficeofNuclearReactorRegulation, Director(Post870411
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstoLicensesDPR-58&DPR-74,revising TechSpecs.DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR JENCLJSIZE:+"gTITLE:ORSubmittal: | | Application for amends to Licenses DPR-58 & DPR-74,revising Tech Specs. |
| GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LASTANGFJINTERNAL:
| | DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL J SIZE: +"g NOTES: |
| NRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/MTB 9HNRR/DOEA/TSB 11OCEGFILE01EXTERNAL: | | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANGFJ 5 5 INTERNAL: NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NUDOCS-ABSTRACT ~ |
| LPDRNSICCOPIESLTTRENCL11551111111110111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DEST/CEB 8HNRR/DEST/ICSB NRR/DEST/RSB 8ENUDOCS-ABSTRACT OGC/HDS1RES/DSIR/EIB NRCPDRCOPIESLTTRENCL11111111~11101111NOXK'IOALL'RZDS>>RECIPIENTS g~8PIZASEHELPUS'Z0REDUCEgASTE!(EHIACT'IHEDOCXMWZCONI'ROLDESKRXNPl-37(EXT.20079)mELXMZHKTB YOURNAMEPBCHDIPI%UBlOTIGN LISTSFORDOCUMEHIS KXJDGNFTNEZD!TOTALNUMBEROFCOPIESREQUIRED:
| | 1 1 OC 1 0 OGC/HDS1 1 0 EG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 g~8 NOXK 'IO ALL 'RZDS>> RECIPIENTS PIZASE HELP US 'Z0 REDUCE gASTE! (EHIACT 'IHE DOCXMWZ CONI'ROL DESK RXN Pl-37 (EXT. 20079) m ELXMZHKTB YOUR NAME PBCH DIPI%UBlOTIGN LISTS FOR DOCUMEHIS KXJ DGNFT NEZD! |
| LTTR22ENCL20 IndianaMichiganPowerCompanyP.O.Box16631Columbus, OH432168AEP:NRC:0979 DonaldC.CookNuclearPlantUnits1and2DocketNos.DPR-58andDPR-74.LicenseNos.50-315and50-316TECHNICAL SPECIFICATION CHANGEREQUEST:REPORTING REQUIREMENTS ONPRIMARYCOOLANTIODINESPIKES(GENERICLETTER85-19)Attn:T.E.MurleyApril7,1989
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20 |
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| ==DearDr.Murley:== | | Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 8 |
| Thisletterconstitutes anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing changestotheT/Srequirements associated withspecificactivityoftheprimarycoolant.Thechangesbeingproposedareinaccordance withchangesendorsedbytheNRCstaffinGenericLetter85-19.Adetaileddescription ofthechangesandouranalysesconcerning significant hazardsarecontained inAttachment 1.Attachment 2containstheproposedrevisedT/Spages.Webelievethattheproposedchangeswillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountsofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
| | AEP:NRC:0979 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. DPR-58 and DPR-74. |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee attheirnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),
| | License Nos. 50-315 and 50-316 TECHNICAL SPECIFICATION CHANGE REQUEST: REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES (GENERIC LETTER 85-19) |
| copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.GeorgeBruchmann oftheMichiganDepartment ofPublicHealth.89<<2~0a>O 89OO07PDRADQCK05000315flPN~U Dr.T.E.Murley-2-AEP:NRC:0979 Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.,
| | Attn: T. E. Murley April 7, 1989 |
| Sincerely, M..Alexch.VicePresident ldpAttachments cc:D.H.Williams, Jr.W.G.Smith,Jr.-BridgmanG.Bruchmann R.C.CallenG.CharnoffA.B.Davis-RegionIIINRCResidentInspector | | |
| -Bridgman 1It)if ATTACHMENT 1TOAEP:NRC:0979 DESCRIPTION AND10CFR50.92SIGNIFICANT HAZARDSEVALUATION FORCHANGESTOTHETECHNICAL SPECIFICATIONS FORTHEDONALDC.COOKNUCLEARPLANTUNITS1AND2 Attachment 1toAEP:NRC:0979 Page1DescritionofChaneAspartofacontinuing programtodeleteunnecessary reporting requirements, theNRCstaffreviewedthereporting requirements relatedtoprimarycoolantspecificactivitylevelsanddetermined thatthesereporting requirements couldbemodifiedtorequirereporting intheAnnualOperating Reportratherthaninashortertermreport(SpecialReportorLicenseeEventReport).Thestaffendorsement ofthisapproachwasprovidedinGenericLetter85-19.GenericLetter85-19alsoendorsedelimination oftheplantshutdownrequirements forthecaseinwhichtheiodineactivitylimitsareexceededfor800hoursina12-monthperiod.Thislaterendorsement wasinresponsetotheNRCstaff'seffortstoeliminate unnecessary T/Srequirements. | | ==Dear Dr. Murley:== |
| WebelievethechangesendorsedbyGenericLetter85-19wouldbebeneficial totheCookNuclearPlant,andwearetherefore proposing changestoourT/Sswhichfollowtheguidanceprovidedinthegenericletter.Wehavenotdeviatedfromthegenericletterguidanceinanyway;ourproposedchangesexactlyfollowthemodelspecification forWestinghouse plantsprovidedinthegenericletter.Wehavealsomadeappropriate changestotheBasesforthespecificactivitylimits.InmakingourT/Ssconsistent withthe'odelT/Ss,thefollowing changeswerenecessary.
| | |
| 1)"3/4.4.8" wasaddedtothe'titleof,.thespecification. | | This letter constitutes an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Units 1 and 2. Specifically, we are proposing changes to the T/S requirements associated with specific activity of the primary coolant. The changes being proposed are in accordance with changes endorsed by the NRC staff in Generic Letter 85-19. A detailed description of the changes and our analyses concerning significant hazards are contained in Attachment 1. Attachment 2 contains the proposed revised T/S pages. |
| 2)Thephrase"primarycoolant"waschangedto"reactorcoolant." | | We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| 3)Thelessthanorequaltosymbols(<),thegreaterthanorequaltosymbols(>),thegreaterthansymbols(>),andthelessthansymbols(<),wereconverted towords.4)The"1.0"waschangedto"1"inSpecification 3.4.8.a.5)Thephrase"uCi/gram" waschangedto"microCuries/gram." | | These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting. |
| 6)ActionaunderModes1,2and3*wasdeletedandActionbwaschangedtoActionaandActioncwaschangedtoActionb.7)TheportionofActionaunderModes1,2,3,4and5involving thereporting requirements wasdeleted.8)Thephrase"ofgrossradioactivity" wasaddedtoSpecification 3.4.8.b.9)Anadditional requirement hasbeenaddedtoSection6.9.1.5torequirethatinformation regarding anyinstances whentheI-131specificactivitylimitwasexceededbesubmitted intheannualreport. | | In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. George Bruchmann of the Michigan Department of Public Health. |
| Attachment 1toAEP:NRC:0979 Page2Justification forChaneAsstatedinGenericLetter85-19,NRChasreviewedthereporting requirements relatedtoprimarycoolantspecificactivitylevelsanddetermined thatrequiring ashore-term reportisunnecessary andendorsedincluding therequiredinformation intheAnnualOperating Report.TheNRCalsoendorseddeletionoftherequirement toshutdownaplantifthecoolantiodineactivitylimitsexceededaspecified annuallimit.Asstatedinthegenericletter,thislimitisnolongernecessary onthebasisthatproper'uel management bylicensees andexistingreporting requirements shouldprecludeeverapproaching thislimit.AllotherchangesproposedtomakeourT/Ssconsistent withthemodelT/Ssareeditorial innature.AnalsisofSinificantHazardsPer10CFR50.92,aproposedamendment willnotinvolvesignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofapreviously evaluated
| | 89<<2~0a>O 89OO07 PDR ADQCK 05000315 fl PN~U |
| : accident, (2)createthepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated, or(3)involveasignificant reduction inamarginofsafety.Criterion 1Theproposedchangesareconsistent withthoseendorsedbytheNRCinGenericLetter85-19.ForthereasonsstatedinGenericLetter85-19,webelievethedeletedrequirements areunnecessary restrictions.
| | |
| Theproposedchangeswouldnotaffecttheaccidentanalysisandthelimitsforthereactorcoolantremainthesame.TheT/Srequirement toshu'tdowntheplantifthecoolantiodineactivitylimitsareexceededformorethan10%oftheunit'sannualoperating timeisanoperating restriction "thatisnolongernecessary basedonademonstration ofsuccessful operating experience asindicated inGenericLetter85-19.Basedontheaboveinformation, webelievethatdeletionoftheserequirements wouldnotsignificantly increasetheprobability orconsequences ofapreviously analyzedaccident.
| | Dr. T. E. Murley AEP:NRC:0979 This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned., |
| Criterion 2Theproposedchangesareconsistent withthechangesendorsedbyGenericLetter85-19andwillnotrequirephysicalalteration oftheplantorchangesinparameters governing normalplant Attachment 1toAEP:NRC:0979 Page3operation. | | Sincerely, M. . Alex ch . |
| Wetherefore believethesechangeswouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously analyzedorevaluated.
| | Vice President ldp Attachments cc: D. H. Williams, Jr. |
| Criterion 3Theproposedchangesareconsistent withthechangesendorsedbyGenericLetter85-19andwouldnotmodifythepresentgrossactivitylimitordoseequivalent I-131limits.Wetherefore believetheproposedchangewouldnotsignificantly reduceamarginofsafety.Lastly,wenotethattheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14870)ofamendments considered notlikelytoinvolveasignificant hazardsconsideration. | | W. G. Smith, Jr. - Bridgman G. Bruchmann R. C. Callen G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman |
| Thesixthoftheseexamplesreferstochangeswhichmayre'suitinsomeincreasetotheprobability ofoccurrence orconsequences ofapreviously analyzedaccident, buttheresultsofwhicharewithinlimitsestablished asacceptable.
| | |
| Sincetheproposedchangesareconsistent withtheguidanceprovidedinGenericLetter85-13,we-believethesechangesfallwithinthescopeofthisexample.Thefourthoftheseexamplesreferstoreliefgrantedupondemonstration ofacceptable operation fromanoperating restriction thatwasimposedbecauseacceptable operation wasnotyetdemonstrated.
| | 1I t |
| Theproposeddeletionoftheshutdownrequirement iftheiodinelimitsareexceededformorethan10%oftheunit'sannualoperating timefallswithinthescopeofthisexample.Therefore webelievethesechangesdonotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.
| | ) |
| ATTACHMENT 2TOAEP:NRC:0979 PROPOSEDTECHNICAL SPECIFICATION PAGES}} | | if |
| | |
| | ATTACHMENT 1 TO AEP:NRC:0979 DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 to AEP:NRC:0979 Page 1 Descri tion of Chan e As part of a continuing program to delete unnecessary reporting requirements, the NRC staff reviewed the reporting requirements related to primary coolant specific activity levels and determined that these reporting requirements could be modified to require reporting in the Annual Operating Report rather than in a shorter term report (Special Report or Licensee Event Report). The staff endorsement of this approach was provided in Generic Letter 85-19. |
| | Generic Letter 85-19 also endorsed elimination of the plant shutdown requirements for the case in which the iodine activity limits are exceeded for 800 hours in a 12-month period. This later endorsement was in response to the NRC staff's efforts to eliminate unnecessary T/S requirements. |
| | We believe the changes endorsed by Generic Letter 85-19 would be beneficial to the Cook Nuclear Plant, and we are therefore proposing changes to our T/Ss which follow the guidance provided in the generic letter. We have not deviated from the generic letter guidance in any way; our proposed changes exactly follow the model specification for Westinghouse plants provided in the generic letter. We have also made appropriate changes to the Bases for the specific activity limits. |
| | In making our T/Ss consistent with the'odel T/Ss, the following changes were necessary. |
| | : 1) "3/4.4.8" was added to the 'title of,. the specification. |
| | : 2) The phrase "primary coolant" was changed to "reactor coolant." |
| | : 3) The less than or equal to symbols (<), the greater than or equal to symbols (>), the greater than symbols (>), |
| | and the less than symbols (<), were converted to words. |
| | : 4) The "1.0" was changed to "1" in Specification 3.4.8.a. |
| | : 5) The phrase "uCi/gram" was changed to "microCuries/gram." |
| | : 6) Action a under Modes 1, 2 and 3* was deleted and Action b was changed to Action a and Action c was changed to Action b. |
| | : 7) The portion of Action a under Modes 1, 2, 3, 4 and 5 involving the reporting requirements was deleted. |
| | : 8) The phrase "of gross radioactivity" was added to Specification 3.4.8.b. |
| | : 9) An additional requirement has been added to Section 6.9.1.5 to require that information regarding any instances when the I-131 specific activity limit was exceeded be submitted in the annual report. |
| | to AEP:NRC:0979 Page 2 Justification for Chan e As stated in Generic Letter 85-19, NRC has reviewed the reporting requirements related to primary coolant specific activity levels and determined that requiring a shore-term report is unnecessary and endorsed including the required information in the Annual Operating Report. The NRC also endorsed deletion of the requirement to shutdown a plant if the coolant iodine activity limits exceeded a specified annual limit. As stated in the generic letter, this limit is no longer necessary on the basis that proper'uel management by licensees and existing reporting requirements should preclude ever approaching this limit. |
| | All other changes proposed to make our T/Ss consistent with the model T/Ss are editorial in nature. |
| | Anal sis of Si nificant Hazards Per 10 CFR 50.92, a proposed amendment will not involve significant hazards consideration if the proposed amendment does not: |
| | (1) involve a significant increase in the probability or consequences of a previously evaluated accident, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety. |
| | Criterion 1 The proposed changes are consistent with those endorsed by the NRC in Generic Letter 85-19. For the reasons stated in Generic Letter 85-19, we believe the deleted requirements are unnecessary restrictions. The proposed changes would not affect the accident analysis and the limits for the reactor coolant remain the same. |
| | The T/S requirement to shu't down the plant if the coolant iodine activity limits are exceeded for more than 10% of the unit's annual operating time is an operating restriction "that is no longer necessary based on a demonstration of successful operating experience as indicated in Generic Letter 85-19. Based on the above information, we believe that deletion of these requirements would not significantly increase the probability or consequences of a previously analyzed accident. |
| | Criterion 2 The proposed changes are consistent with the changes endorsed by Generic Letter 85-19 and will not require physical alteration of the plant or changes in parameters governing normal plant to AEP:NRC:0979 Page 3 operation. We therefore believe these changes would not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated. |
| | Criterion 3 The proposed changes are consistent with the changes endorsed by Generic Letter 85-19 and would not modify the present gross activity limit or dose equivalent I-131 limits. We therefore believe the proposed change would not significantly reduce a margin of safety. |
| | Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve a significant hazards consideration. The sixth of these examples refers to changes which may re'suit in some increase to the probability of occurrence or consequences of a previously analyzed accident, but the results of which are within limits established as acceptable. Since the proposed changes are consistent with the guidance provided in Generic Letter 85-13, we |
| | -believe these changes fall within the scope of this example. |
| | The fourth of these examples refers to relief granted upon demonstration of acceptable operation from an operating restriction that was imposed because acceptable operation was not yet demonstrated. The proposed deletion of the shutdown requirement if the iodine limits are exceeded for more than 10% of the unit's annual operating time falls within the scope of this example. Therefore we believe these changes do not involve a significant hazards consideration as defined in 10 CFR 50.92. |
| | |
| | ATTACHMENT 2 TO AEP:NRC:0979 PROPOSED TECHNICAL SPECIFICATION PAGES}} |
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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
gc CELZRATED D1SIRIBU'EON DE MON STRATIO'.i SYSTEM REGULRTC INFORMATION DISTRIBUTION+STEM (RIDE)
ACCESSION NBR:8904210210 ,DOC.DATE: 89/04/07 NOTARIZED: NO DOCKET FACIL:50-31$ Donald C. Cook Nuclear Power Plant, Unit 1, Indiana 6 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana & 05000316 AUTH. NAME AUTHOR AFFILIATION ALEXICH,M.P. Indiana Michigan Power Co. (formerly Indiana a Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411
SUBJECT:
Application for amends to Licenses DPR-58 & DPR-74,revising Tech Specs.
DISTRIBUTION CODE: A001D TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL J SIZE: +"g NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANGFJ 5 5 INTERNAL: NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NUDOCS-ABSTRACT ~
1 1 OC 1 0 OGC/HDS1 1 0 EG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 g~8 NOXK 'IO ALL 'RZDS>> RECIPIENTS PIZASE HELP US 'Z0 REDUCE gASTE! (EHIACT 'IHE DOCXMWZ CONI'ROL DESK RXN Pl-37 (EXT. 20079) m ELXMZHKTB YOUR NAME PBCH DIPI%UBlOTIGN LISTS FOR DOCUMEHIS KXJ DGNFT NEZD!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 8
AEP:NRC:0979 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. DPR-58 and DPR-74.
License Nos. 50-315 and 50-316 TECHNICAL SPECIFICATION CHANGE REQUEST: REPORTING REQUIREMENTS ON PRIMARY COOLANT IODINE SPIKES (GENERIC LETTER 85-19)
Attn: T. E. Murley April 7, 1989
Dear Dr. Murley:
This letter constitutes an application for amendment to the Technical Specifications (T/Ss) for the Donald C. Cook Nuclear Plant Units 1 and 2. Specifically, we are proposing changes to the T/S requirements associated with specific activity of the primary coolant. The changes being proposed are in accordance with changes endorsed by the NRC staff in Generic Letter 85-19. A detailed description of the changes and our analyses concerning significant hazards are contained in Attachment 1. Attachment 2 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 effluents or a significant increase in the amounts of any effluent 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 and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission and Mr. George Bruchmann of the Michigan Department of Public Health.
89<<2~0a>O 89OO07 PDR ADQCK 05000315 fl PN~U
Dr. T. E. Murley AEP:NRC:0979 This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.,
Sincerely, M. . Alex ch .
Vice President ldp Attachments cc: D. H. Williams, Jr.
W. G. Smith, Jr. - Bridgman G. Bruchmann R. C. Callen G. Charnoff A. B. Davis - Region III NRC Resident Inspector - Bridgman
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ATTACHMENT 1 TO AEP:NRC:0979 DESCRIPTION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR CHANGES TO THE TECHNICAL SPECIFICATIONS FOR THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 to AEP:NRC:0979 Page 1 Descri tion of Chan e As part of a continuing program to delete unnecessary reporting requirements, the NRC staff reviewed the reporting requirements related to primary coolant specific activity levels and determined that these reporting requirements could be modified to require reporting in the Annual Operating Report rather than in a shorter term report (Special Report or Licensee Event Report). The staff endorsement of this approach was provided in Generic Letter 85-19.
Generic Letter 85-19 also endorsed elimination of the plant shutdown requirements for the case in which the iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period. This later endorsement was in response to the NRC staff's efforts to eliminate unnecessary T/S requirements.
We believe the changes endorsed by Generic Letter 85-19 would be beneficial to the Cook Nuclear Plant, and we are therefore proposing changes to our T/Ss which follow the guidance provided in the generic letter. We have not deviated from the generic letter guidance in any way; our proposed changes exactly follow the model specification for Westinghouse plants provided in the generic letter. We have also made appropriate changes to the Bases for the specific activity limits.
In making our T/Ss consistent with the'odel T/Ss, the following changes were necessary.
- 1) "3/4.4.8" was added to the 'title of,. the specification.
- 2) The phrase "primary coolant" was changed to "reactor coolant."
- 3) The less than or equal to symbols (<), the greater than or equal to symbols (>), the greater than symbols (>),
and the less than symbols (<), were converted to words.
- 4) The "1.0" was changed to "1" in Specification 3.4.8.a.
- 5) The phrase "uCi/gram" was changed to "microCuries/gram."
- 6) Action a under Modes 1, 2 and 3* was deleted and Action b was changed to Action a and Action c was changed to Action b.
- 7) The portion of Action a under Modes 1, 2, 3, 4 and 5 involving the reporting requirements was deleted.
- 8) The phrase "of gross radioactivity" was added to Specification 3.4.8.b.
- 9) An additional requirement has been added to Section 6.9.1.5 to require that information regarding any instances when the I-131 specific activity limit was exceeded be submitted in the annual report.
to AEP:NRC:0979 Page 2 Justification for Chan e As stated in Generic Letter 85-19, NRC has reviewed the reporting requirements related to primary coolant specific activity levels and determined that requiring a shore-term report is unnecessary and endorsed including the required information in the Annual Operating Report. The NRC also endorsed deletion of the requirement to shutdown a plant if the coolant iodine activity limits exceeded a specified annual limit. As stated in the generic letter, this limit is no longer necessary on the basis that proper'uel management by licensees and existing reporting requirements should preclude ever approaching this limit.
All other changes proposed to make our T/Ss consistent with the model T/Ss are editorial in nature.
Anal sis of Si nificant Hazards Per 10 CFR 50.92, a proposed amendment will not involve significant hazards consideration if the proposed amendment does not:
(1) involve a significant increase in the probability or consequences of a previously evaluated accident, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety.
Criterion 1 The proposed changes are consistent with those endorsed by the NRC in Generic Letter 85-19. For the reasons stated in Generic Letter 85-19, we believe the deleted requirements are unnecessary restrictions. The proposed changes would not affect the accident analysis and the limits for the reactor coolant remain the same.
The T/S requirement to shu't down the plant if the coolant iodine activity limits are exceeded for more than 10% of the unit's annual operating time is an operating restriction "that is no longer necessary based on a demonstration of successful operating experience as indicated in Generic Letter 85-19. Based on the above information, we believe that deletion of these requirements would not significantly increase the probability or consequences of a previously analyzed accident.
Criterion 2 The proposed changes are consistent with the changes endorsed by Generic Letter 85-19 and will not require physical alteration of the plant or changes in parameters governing normal plant to AEP:NRC:0979 Page 3 operation. We therefore believe these changes would not create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated.
Criterion 3 The proposed changes are consistent with the changes endorsed by Generic Letter 85-19 and would not modify the present gross activity limit or dose equivalent I-131 limits. We therefore believe the proposed change would not significantly reduce a margin of safety.
Lastly, we note that the Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve a significant hazards consideration. The sixth of these examples refers to changes which may re'suit in some increase to the probability of occurrence or consequences of a previously analyzed accident, but the results of which are within limits established as acceptable. Since the proposed changes are consistent with the guidance provided in Generic Letter 85-13, we
-believe these changes fall within the scope of this example.
The fourth of these examples refers to relief granted upon demonstration of acceptable operation from an operating restriction that was imposed because acceptable operation was not yet demonstrated. The proposed deletion of the shutdown requirement if the iodine limits are exceeded for more than 10% of the unit's annual operating time falls within the scope of this example. Therefore we believe these changes do not involve a significant hazards consideration as defined in 10 CFR 50.92.
ATTACHMENT 2 TO AEP:NRC:0979 PROPOSED TECHNICAL SPECIFICATION PAGES