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| | issue date = 03/14/1989 | | | issue date = 03/14/1989 |
| | title = Application for Amends to Licenses DPR-58 & DPR-74,allowing Posting of Designated Individuals to Substitute for Locked Doors for High Radiation Areas Required by Tech Spec 6.12.2. Justification & Analysis Encl | | | title = Application for Amends to Licenses DPR-58 & DPR-74,allowing Posting of Designated Individuals to Substitute for Locked Doors for High Radiation Areas Required by Tech Spec 6.12.2. Justification & Analysis Encl |
| | 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 INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | 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:1~ACCELERATED II+RIBUTI 0%DEMONSTTIDYSYSTEM4REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:8903220176 DOC.DATE: | | {{#Wiki_filter:1 |
| 89/03/14NOTARIZED: | | ~ |
| NODOCKETPTFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,Xndiana&0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,Indiana&05000316AUTH.NAMEAUTHORAFFILIATION ALEXICH,M.P.
| | ACCELERATED II+RIBUTI0% DEMON ST TIDY SYSTEM 4 |
| .IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECXP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:8903220176 DOC.DATE: 89/03/14 NOTARIZED: NO DOCKET PT FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Xndiana & 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 & Michigan Ele RECXP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Application foramendstoLicensesDPR-58&DPR-74,allowing postingofindividuals tosubstitute forlockeddoors.DISTRIBUTION CODE:A001DCOPXESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: | | Application for amends to Licenses DPR-58 & DPR-74,allowing posting of individuals to substitute for locked doors. |
| GeneralDistribution NOTES:RECIPXENT IDCODE/NAME PD3-1LASTANG,JINTERNAL:
| | DISTRIBUTION CODE: A001D COPXES RECEIVED:LTR ENCL SIZE: |
| ARM/DAF/LFMB NRR/DEST/CEB 8HNRR/DEST/MTB 9HNRR/DEST/SICB NU~GSABSCTLE01EXTERNALLPDRNSXCCOPIESLTTRENCL10111011111111111111RECIPIENT IDCODE/NAME PD3-1PDNRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/RSB 8ENRR/DOEA/TSB 11OGC/HDS1RES/DSIR/EXB NRCPDRCOPIESLTTRENCL2211111111101111DNOTE'IOAXZ-"RZDS"RZCZPIENIS. | | TITLE: OR Submittal: General Distribution NOTES: |
| PIZASEHELPUS1OREDUCEWASTE.'GNI'ACT
| | RECIPXENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 2 2 STANG,J 1 1 D INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SICB 1 1 NRR/DOEA/TSB 11 1 1 NU~GS ABS CT 1 1 OGC/HDS1 1 0 LE 01 1 1 RES/DSIR/EXB 1 1 EXTERNAL LPDR 1 1 NRC PDR 1 1 NSXC 1 1 D |
| 'IHEDOCUMEMI'GNIROL DESK,ROOMPl-37(EXT.20079)KOEIZMZNATE YOURNAMEFRYDISTIKBVTIGN LISTSFORDOCUMENIS YOUDON'TNEED!DSDDSTOTALNUMBEROFCOPIESREQUIRED: | | S D |
| LTTR19ENCL16 IndianaMichigan~PowerCompany~P.O.Box16631Columbus, OH43216AEP:NRC:1039 DonaldC.CookNuclearPlantUnits1and2DocketNos.50-315and50-316LicenseNos.DPR-58andDPR-74T/SCHANGEREQUESTONLOCKINGOFHIGHRADIATION AREASU.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Attn:T.E.MurleyMarch14,1989
| | D NOTE 'IO AXZ- "RZDS" RZCZPIENIS. |
| | S PIZASE HELP US 1O REDUCE WASTE.'GNI'ACT 'IHE DOCUMEMI'GNIROL DESK, ROOM Pl-37 (EXT. 20079) KO EIZMZNATE YOUR NAME FRY DISTIKBVTIGN LISTS FOR DOCUMENIS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16 |
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| ==DearDr.Murley:==
| | Indiana Michigan Power Company |
| Thisletterconstitutes anapplication foramendment totheTechnical Specifications (T/Ss)fortheDonaldC.CookNuclearPlantUnits1and2.Specifically, weareproposing toallowthepostingofdesignated individuals tosubstitute forthelockeddoorsforhighradiation areasrequiredbyT/S6.12.2~Adetaileddescription oftheproposedchangeandouranalysisconcerning significant hazardsconsiderations arecontained inAttachment 1.TheproposedrevisedT/Spagesarecontained inAttachment 2.Webelievethattheproposedchangewillnotresultin(1)asignificant changeinthetypesofeffluents orasignificant increaseintheamountofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
| | ~ |
| TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedbytheNuclearSafetyandDesignReviewCommittee attheirnextregularly scheduled meeting.Incompliance withtherequirements of10CFR50.91(b)(1),
| | ~ |
| copiesofthisletteranditsattachments havebeentransmitted toMr.R.C.CallenoftheMichiganPublicServiceCommission andMr.G.Bruchmann oftheMichiganDepartment ofPublicHealth.489'03220176 85'0314PDRADOCK05'000325 PDCgoo Dr.T.E.Murley-2-AEP:NRC:1039 Thisdocumenthasbeenpreparedfollowing Corporate procedures thatincorporate areasonable setofcontrolstoensureitsaccuracyandcompleteness priortosignature bytheundersigned.
| | P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1039 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 T/S CHANGE REQUEST ON LOCKING OF HIGH RADIATION AREAS U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley March 14, 1989 |
| Sincerely, MP.AlxichVicePresident CEM/ehAttachments cc:D.H.Williams, Jr.W.G.Smith,Jr.-BridgmanR.C.CallenG.Bruchmann G.CharnoffNRCResidentInspector
| |
| -BridgmanA.B.Davis-RegionIII
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| ATTACHMENT 1TOAEP:NRC:1039 REASONSAND10CFR50.92ANALYSISFORCHANGESTOTHEDONALDC.COOKNUCLEARPLANTUNITNO.1ANDUNITNO.2TECHNICAL SPECIFICATIONS 1
| | ==Dear Dr. Murley:== |
| Attachment 1toAEP:NRC:1039 Page1DESCRIPTION OFCHANGETechnical Specification (T/S)6.12.2requiresthatlockeddoorsbeprovidedtopreventunauthorized entryintohighradiation areasinwhichtheintensity ofradiation isgreaterthan1000mrem/hr.Weareproposing toallowthepostingofadesignated individual toserveasasubstitute foralockeddoorinthoseinstances inwhichproviding alockeddoorisnotpossibleornotpractical duetoareasizeorconfiguration.
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| WehavenotedtheconcernsraisedinNRCInformation Notice88-79,"MisuseofFlashingLightsForHighRadiation AreaControls."
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| Themajorityoftheexamplesofmisusecitedinthisinformation noticeinvolvedusingtheflashinglights(1)whenconstructing alockableenclosure wasareasonable alternative or(2)whenlockinganexistingenclosure waspossible.
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| Asnotedabove,weintendtousetheproposedalternative ofpostingadesignated individual onlywhenitisnotpossibleornotpractical toprovidelockeddoors.Asexplained intheT/Ss,theintentofthelockeddoorsistopreventunauthorized entryintothesubjectarea.Webelievethat'postingadesignated individual providesalevelofprotection forpreventing unauthorized entrythatisequivalent toorbetterthantheprotection providedbytheflashinglightsallowedbythecurrentWestinghouse standardT/SsandtheT/Ssofsomeothernuclearplants.Per10CFR50.92,aproposedamendment willnotinvolveasignificant hazardsconsideration iftheproposedamendment doesnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, (2)createthepossibility ofanewordifferent kindofaccidentEromanyaccidentpreviously analyzedorevaluated, or(3)involveasignificant reduction inamarginofsafety.Criterion 1Changingtheaccesscontrolrequirements forhighradiation areasdoesnotimpactanyofthepreviously analyzedaccidents.
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| Therefore, webeli<":echatthischangewillnotinvolveasignificant increas'n theprobability orconsequences ofanaccidentpreviously valuated.
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| Attachment 1toAEP:NRC:1039 Page2Criterion 2Theproposedchangedoesnotinvolveachangeinplant'configuration oroperation andwillnotplacetheplantinanunanalyzed condition; therefore, webelievethechangewillnot.create thepossibility ofanewordifferent kindofaccidentfromanypreviously analyzedorevaluated. | | 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 to allow the posting of designated individuals to substitute for the locked doors for high radiation areas required by T/S 6.12.2 ~ A detailed description of the proposed change and our analysis concerning significant hazards considerations are contained in Attachment 1. The proposed revised T/S pages are contained in Attachment 2. |
| Criterion 3Webelievethatpostingadesignated individual isequivalent toorbetterthanthealternative (flashing lights)allowedbytheWestinghouse standardT/SsandtheT/Ssofsomeothernuclearplants.Basedonthisandsincewebelievethatthedesignated individuals willprovideadequateprotection againstunauthorized entry,webelievethechangewillnotinvolveasignificant reduction inamarginofsafety.TheCommission hasprovidedguidanceconcerning thedetermination ofsignificant hazardsbyproviding certainexamples(48FR14780)ofamendments considered not,likelytoinvolvesignificant hazardsconsiderations. | | We believe that the proposed change will not result in (1) a significant change in the types of effluents or a significant increase in the amount of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure. |
| Webelievetheproposedchangeislesslikelythanthesixthexampleintheaboveguidancetoinvolveasignificant hazardsconsideration.
| | 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. |
| Specifically, webelievetheproposedchangewillnotresultinanincreaseintheprobability orconsequences ofapreviously analyzedaccidentorreduceamarginofsafety,sincewebelievethatpostingadesignated individual willprovideadequateprotection againstunauthorized entryforthoseinstances forwhichproviding alockedenclosure isnotpossibleornotpractical. | | 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. G. Bruchmann of the Michigan Department of Public Health. |
| Therefore, webelievethischangedoesnotinvolveasignificant hazardsconsideration asdefinedin10CFR50.92.}} | | goo 4 |
| | 89'03220176 PDR ADOCK 85'0314 05'000325 PDC |
| | |
| | Dr. T. E. Murley AEP:NRC:1039 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 P. Al xich Vice President CEM/eh Attachments cc: D. H. Williams, Jr. |
| | W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III |
| | |
| | ATTACHMENT 1 TO AEP:NRC:1039 REASONS AND 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 AND UNIT NO. 2 TECHNICAL SPECIFICATIONS |
| | |
| | 1 Attachment 1 to AEP:NRC:1039 Page 1 DESCRIPTION OF CHANGE Technical Specification (T/S) 6.12.2 requires that locked doors be provided to prevent unauthorized entry into high radiation areas in which the intensity of radiation is greater than 1000 mrem/hr. We are proposing to allow the posting of a designated individual to serve as a substitute for a locked door in those instances in which providing a locked door is not possible or not practical due to area size or configuration. |
| | We have noted the concerns raised in NRC Information Notice 88-79, "Misuse of Flashing Lights For High Radiation Area Controls." The majority of the examples of misuse cited in this information notice involved using the flashing lights (1) when constructing a lockable enclosure was a reasonable alternative or (2) when locking an existing enclosure was possible. As noted above, we intend to use the proposed alternative of posting a designated individual only when it is not possible or not practical to provide locked doors. |
| | As explained in the T/Ss, the intent of the locked doors is to prevent unauthorized entry into the subject area. We believe that |
| | 'posting a designated individual provides a level of protection for preventing unauthorized entry that is equivalent to or better than the protection provided by the flashing lights allowed by the current Westinghouse standard T/Ss and the T/Ss of some other nuclear plants. |
| | Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not: |
| | (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident Erom any accident previously analyzed or evaluated, or (3) involve a significant reduction in a margin of safety. |
| | Criterion 1 Changing the access control requirements for high radiation areas does not impact any of the previously analyzed accidents. |
| | Therefore, we beli<":e chat this change will not involve a significant increas'n the probability or consequences of an accident previously valuated. |
| | |
| | to AEP:NRC:1039 Page 2 Criterion 2 The proposed change does not involve a change in plant'configuration or operation and will not place the plant in an unanalyzed condition; therefore, we believe the change will not.create the possibility of a new or different kind of accident from any previously analyzed or evaluated. |
| | Criterion 3 We believe that posting a designated individual is equivalent to or better than the alternative (flashing lights) allowed by the Westinghouse standard T/Ss and the T/Ss of some other nuclear plants. Based on this and since we believe that the designated individuals will provide adequate protection against unauthorized entry, we believe the change will not involve a significant reduction in a margin of safety. |
| | The Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14780) of amendments considered not, likely to involve significant hazards considerations. We believe the proposed change is less likely than the sixth example in the above guidance to involve a significant hazards consideration. Specifically, we believe the proposed change will not result in an increase in the probability or consequences of a previously analyzed accident or reduce a margin of safety, since we believe that posting a designated individual will provide adequate protection against unauthorized entry for those instances for which providing a locked enclosure is not possible or not practical. Therefore, we believe this change does not involve a significant hazards consideration as defined in 10 CFR 50.92.}} |
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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
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ACCELERATED II+RIBUTI0% DEMON ST TIDY SYSTEM 4
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8903220176 DOC.DATE: 89/03/14 NOTARIZED: NO DOCKET PT FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Xndiana & 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 & Michigan Ele RECXP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-58 & DPR-74,allowing posting of individuals to substitute for locked doors.
DISTRIBUTION CODE: A001D COPXES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPXENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 2 2 STANG,J 1 1 D INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SICB 1 1 NRR/DOEA/TSB 11 1 1 NU~GS ABS CT 1 1 OGC/HDS1 1 0 LE 01 1 1 RES/DSIR/EXB 1 1 EXTERNAL LPDR 1 1 NRC PDR 1 1 NSXC 1 1 D
S D
D NOTE 'IO AXZ- "RZDS" RZCZPIENIS.
S PIZASE HELP US 1O REDUCE WASTE.'GNI'ACT 'IHE DOCUMEMI'GNIROL DESK, ROOM Pl-37 (EXT. 20079) KO EIZMZNATE YOUR NAME FRY DISTIKBVTIGN LISTS FOR DOCUMENIS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 16
Indiana Michigan Power Company
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P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1039 Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 T/S CHANGE REQUEST ON LOCKING OF HIGH RADIATION AREAS U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Attn: T. E. Murley March 14, 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 to allow the posting of designated individuals to substitute for the locked doors for high radiation areas required by T/S 6.12.2 ~ A detailed description of the proposed change and our analysis concerning significant hazards considerations are contained in Attachment 1. The proposed revised T/S pages are contained in Attachment 2.
We believe that the proposed change will not result in (1) a significant change in the types of effluents or a significant increase in the amount of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed 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. G. Bruchmann of the Michigan Department of Public Health.
goo 4
89'03220176 PDR ADOCK 85'0314 05'000325 PDC
Dr. T. E. Murley AEP:NRC:1039 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 P. Al xich Vice President CEM/eh Attachments cc: D. H. Williams, Jr.
W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman A. B. Davis - Region III
ATTACHMENT 1 TO AEP:NRC:1039 REASONS AND 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNIT NO. 1 AND UNIT NO. 2 TECHNICAL SPECIFICATIONS
1 Attachment 1 to AEP:NRC:1039 Page 1 DESCRIPTION OF CHANGE Technical Specification (T/S) 6.12.2 requires that locked doors be provided to prevent unauthorized entry into high radiation areas in which the intensity of radiation is greater than 1000 mrem/hr. We are proposing to allow the posting of a designated individual to serve as a substitute for a locked door in those instances in which providing a locked door is not possible or not practical due to area size or configuration.
We have noted the concerns raised in NRC Information Notice 88-79, "Misuse of Flashing Lights For High Radiation Area Controls." The majority of the examples of misuse cited in this information notice involved using the flashing lights (1) when constructing a lockable enclosure was a reasonable alternative or (2) when locking an existing enclosure was possible. As noted above, we intend to use the proposed alternative of posting a designated individual only when it is not possible or not practical to provide locked doors.
As explained in the T/Ss, the intent of the locked doors is to prevent unauthorized entry into the subject area. We believe that
'posting a designated individual provides a level of protection for preventing unauthorized entry that is equivalent to or better than the protection provided by the flashing lights allowed by the current Westinghouse standard T/Ss and the T/Ss of some other nuclear plants.
Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident Erom any accident previously analyzed or evaluated, or (3) involve a significant reduction in a margin of safety.
Criterion 1 Changing the access control requirements for high radiation areas does not impact any of the previously analyzed accidents.
Therefore, we beli<":e chat this change will not involve a significant increas'n the probability or consequences of an accident previously valuated.
to AEP:NRC:1039 Page 2 Criterion 2 The proposed change does not involve a change in plant'configuration or operation and will not place the plant in an unanalyzed condition; therefore, we believe the change will not.create the possibility of a new or different kind of accident from any previously analyzed or evaluated.
Criterion 3 We believe that posting a designated individual is equivalent to or better than the alternative (flashing lights) allowed by the Westinghouse standard T/Ss and the T/Ss of some other nuclear plants. Based on this and since we believe that the designated individuals will provide adequate protection against unauthorized entry, we believe the change will not involve a significant reduction in a margin of safety.
The Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14780) of amendments considered not, likely to involve significant hazards considerations. We believe the proposed change is less likely than the sixth example in the above guidance to involve a significant hazards consideration. Specifically, we believe the proposed change will not result in an increase in the probability or consequences of a previously analyzed accident or reduce a margin of safety, since we believe that posting a designated individual will provide adequate protection against unauthorized entry for those instances for which providing a locked enclosure is not possible or not practical. Therefore, we believe this change does not involve a significant hazards consideration as defined in 10 CFR 50.92.