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| {{#Wiki_filter:ATTACHMENT BMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnical Specifications Includedpages:4.4-7.9503160210 950313PDRADOCK05000244PDR b.CeIfrepairsarenotcompleted andconformance totheacceptance criterion of4.4.2.2isnot,demonstrated within48hours,thereactorshallbeshutdownanddepressurized untilrepairsareeffectedandthelocalleakagemeetstheacceptance criterion. | | {{#Wiki_filter:ATTACHMENT B Marked Up Copy of R.E.Ginna Nuclear Power Plant Technical Specifications Included pages: 4.4-7.9503160210 950313 PDR ADOCK 05000244 PDR b.Ce If repairs are not completed and conformance to the acceptance criterion of 4.4.2.2 is not, demonstrated within 48 hours, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion. |
| Ifitisdetermined
| | If it is determined |
| 'hattheleakagethroughamini-purge supplyandexhaustlineisgreaterthan0.05Laanengineering evaluation shallbeperformed and,.plansforcorrective actiondeveloped. | | 'hat the leakage through a mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and ,.plans for corrective action developed. |
| 44.2.4TestFreuencina.~o4o.viCa f''Q0~App~CLi&+~~P~vQg~~Ha~aeb.betesteeachreactorshutdownrrefueling, orotherconvtervals,butinnontervalsgreaterthantwoyears.Thecontainment equipment hatch,fueltransfertube,steamgenerator inspection/maintenance penetration, andshutdownpurgesystemflangesshallbetestedateachrefueling shutdownoraftereachuse,ifthatbesooner.Exceptasspecified inb.andc.below,individual penetrations andcontainment isolation valvesshallAmendment No.ZS4.4-7
| | 4 4.2.4 Test Fre uenc in a.~o4o.viCa f''Q 0~A pp~CLi&+~~P~vQ g~~Ha~a e b.be teste each reactor shutdown r refueling, or other conv tervals, but in no ntervals greater than two years.The containment equipment hatch, fuel transfer tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.Except as specified in b.and c.below, individual penetrations and containment isolation valves shall Amendment No.ZS 4.4-7 |
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| ATTACHMENT CProposedRevisedR.E.GinnaNuclearPowerPlantTechnical Specifications Revisethepagesasfollows:RemoveInsert4.4-74.4-7 b.c~Ifrepairsarenotcompleted andconformance totheacceptance criterion of4.4.2.2isnotdemonstrated within48hours,thereactorshallbeshutdownanddepressurized untilrepairsareeffectedandthelocalleakagemeetstheacceptance criterion. | | ATTACHMENT C Proposed Revised R.E.Ginna Nuclear Power Plant Technical Specifications Revise the pages as follows: Remove Insert 4.4-7 4.4-7 b.c~If repairs are not completed and conformance to the acceptance criterion of 4.4.2.2 is not demonstrated within 48 hours, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion. |
| Ifitisdetermined thattheleakagethroughamini-purge supplyandexhaustlineisgreaterthan0.05Laanengineering evaluation shallbeperformed andplansforcorrective actiondeveloped.
| | If it is determined that the leakage through a mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and plans for corrective action developed. |
| 4.4.2.4TestFreuenca~b.Exceptasspecified inb.andc.below,individual penetrations andcontainment isolation valvesshallbetestedinaccordance with10CFR50,AppendixJ,asmodifiedbyapprovedexemptions. | | 4.4.2.4 Test Fre uenc a~b.Except as specified in b.and c.below, individual penetrations and containment isolation valves shall be tested in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions. |
| Thecontainment equipment hatch,fueltransfertube,steamgenerator inspection/maintenance penetration, andshutdownpurgesystemflangesshallbetestedateachrefueling shutdownoraftereachuse,ifthatbesooner.Amendment No.4.4-7Proposed Fc~}}
| | The containment equipment hatch, fuel transfer tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.Amendment No.4.4-7 Proposed F c~}} |
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[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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Rev 6 to Technical Requirements Manual.
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Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr
ML17265A3721998-07-16016 July 1998
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ML17265A3151998-06-0404 June 1998
Proposed Tech Specs Basis Re Main Steam Isolation Setpoint
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Tech Specs Consisting of Submittal Changes for 1998
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ML17264A9391997-07-0707 July 1997
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[Table view] |
Text
ATTACHMENT B Marked Up Copy of R.E.Ginna Nuclear Power Plant Technical Specifications Included pages: 4.4-7.9503160210 950313 PDR ADOCK 05000244 PDR b.Ce If repairs are not completed and conformance to the acceptance criterion of 4.4.2.2 is not, demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion.
If it is determined
'hat the leakage through a mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and ,.plans for corrective action developed.
4 4.2.4 Test Fre uenc in a.~o4o.viCa fQ 0~A pp~CLi&+~~P~vQ g~~Ha~a e b.be teste each reactor shutdown r refueling, or other conv tervals, but in no ntervals greater than two years.The containment equipment hatch, fuel transfer tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.Except as specified in b.and c.below, individual penetrations and containment isolation valves shall Amendment No.ZS 4.4-7
ATTACHMENT C Proposed Revised R.E.Ginna Nuclear Power Plant Technical Specifications Revise the pages as follows: Remove Insert 4.4-7 4.4-7 b.c~If repairs are not completed and conformance to the acceptance criterion of 4.4.2.2 is not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be shutdown and depressurized until repairs are effected and the local leakage meets the acceptance criterion.
If it is determined that the leakage through a mini-purge supply and exhaust line is greater than 0.05 La an engineering evaluation shall be performed and plans for corrective action developed.
4.4.2.4 Test Fre uenc a~b.Except as specified in b.and c.below, individual penetrations and containment isolation valves shall be tested in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.
The containment equipment hatch, fuel transfer tube, steam generator inspection/maintenance penetration, and shutdown purge system flanges shall be tested at each refueling shutdown or after each use, if that be sooner.Amendment No.4.4-7 Proposed F c~
