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| {{#Wiki_filter:ATTACHMENT 2TOAEP:NRC:1215 EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES9407Z50177 940719PDRADOCK05000315P.....PDR COHTAINHENT SYST:-~SCONTAINS=.HT LDKAC=LIl'IITING CONDITION rOR0."=RATIOH3.6.1.2Containmntleakagratesshallbelimitedto:a.Anoverallintegratdleakageratof<L,0.25prcntbyweightofthecontainment airper24hoursatP,12.0psig,andb.Acombindleakaoerateof<0.60LaforallpenetraionsandvalvessubjcttoTypeBandCtestswhnprssurizdtoPAPPLICABILiTY: | | {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 PDR ADOCK 05000315 P.....PDR COHTAINHENT SYST:-~S CONTAINS=.HT LDKAC=LIl'IITING CONDITION rOR 0."=RATIOH 3.6.1.2 Containm nt leakag rates shall be limited to: a.An overall integrat d leakage rat of<L, 0.25 p rc nt by weight of the containment air per 24 hours at P, 12.0 psig, and b.A combin d leakaoe rate of<0.60 La for all penetra ions and valves subj ct to Type B and C tests wh n pr ssuriz d to P APPLICABILiTY: |
| YIODES1,2,3and4.ACTION:Mitheithr(a)thmasuredovrailintratedcon,ainmnt1akagerateexceeding 0.75Laor(b)withthemeasuredcombinedleakagerateforallpnetrations andvalvssubjecttoTypesBandCtestsexceding0.60Lrstorethleakagrate(s)towithinthelimit(s)priortoincreasing theRacorCoolantSystmtmpratureabove200'F.SURYEILLAHC" REQUIRE,"!="H S4.6.1.2Th~con.ainmntleakagratsshallbdmonstratdatthfollowing t~stscheduleandshallbedetermined inconforrance withthecritriaspcifidinAppendixJof10CFR50usingthemthodsandprovisions ofANSIN45.4-1972:
| | YIODES 1, 2, 3 and 4.ACTION: Mith eith r (a)th m asured ov rail int rated con,ainm nt 1 akage rate exceeding 0.75 La or (b)with the measured combined leakage rate for all p netrations and valv s subject to Types B and C tests exc eding 0.60 L r store th leakag rate(s)to within the limit(s)prior to increasing the R ac or Coolant Syst m t mp rature above 200'F.SURYEILLAHC" REQUIRE,"!="H S 4.6.1.2 Th~con.ainm nt leakag rat s shall b d monstrat d at th following t~st schedule and shall be determined in conforrance with the crit ria sp cifi d in Appendix J of 10 CFR 50 using the m thods and provisions of ANSI N45.4-1972: |
| a. shu4de6QlQ(Qy~~TM~p~~CL, MALCh'\0~ 4I~ lgg5g) 4k04wW.+W~~i~e.n~+ 5s~i~i~~~~~g,pi~+ aqpnouedw<~p4>< Ipt<+<~Q~<p)~<I<ghee-ll~ VECLgKEAg~PtI++~~\> 6Sp~t<'+ goz~~~a+~)p).~4~~ | | a. shu4de 6 Ql Q (Qy~~TM~p~~CL, MA LCh'\0~ 4 I~ lgg 5 g) 4k 04 wW.+W~~i~e.n~+ 5 s~i~i~~~~~g,pi~+ aqpnoued w<~p4>< I p t<+<~Q~<p)~<I<ghee-ll~ VEC LgKEA g~PtI++~~\> 6 Sp~t<'+ g o z~~~a+~)p).~4~~$~ I 41 (.~4>~D.C.COOK-UNIT 1 3/ 4 6- 2 Amendment Ho.+8-) |
| $~I41(.~4>~D.C.COOK-UNIT 13/46-2Amendment Ho.+8-) | | uheequent-Typ~~est s-s~k-b o-sense sos-me.~ae-the-aha |
| uheequent | | ~ay-be-resumed a'ach containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3-%45 pR-i~Yon4i>~~g,h~(+ |
| -Typ~~ests-s~k-bo-sensesos-me.~ae-the-aha | | b)AQIc COOK NUCLEAR PLANT-UNIT 1 3/4 6-3 AMENDMENT NO.~- |
| ~ay-be-resumed a'achcontainment airlockshallbeverifiedtobeincompliance withtherequirements ofSpecification 3.6.1.3-%45pR-i~Yon4i>~~g,h~(+ | | CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of<L, 0.25 percent by weight of the containment air per 24 hours at P, 12 psig.b.A combined leakage rate of<0.60 L for all penetrations and valves subject to Type B and C test3, when pressurized to P.a'PPLICABILITY: |
| b)AQIcCOOKNUCLEARPLANT-UNIT13/46-3AMENDMENT NO.~- | | MODES 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the overall integrated leakage rate to<0.75 L and the coimttbined leakage rate for all penetrations and valves subjec$to Type B and C tests to<0.60 L prior to increasing the Peactor Coolant System temperature above$00'F.SURVEI LLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: |
| CONTAINMENT SYSTEMSCONTAINMENT LEAKAGELIMITINGCONDITION FOROPERATION 3.6.1.2Containment leakageratesshallbelimitedto:a.Anoverallintegrated leakagerateof<L,0.25percentbyweightofthecontainment airper24hoursatP,12psig.b.Acombinedleakagerateof<0.60Lforallpenetrations andvalvessubjecttoTypeBandCtest3,whenpressurized toP.a'PPLICABILITY: | | Yl~~A-4~'-4 4s 4a4e-)-chal-1 |
| MODES1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegrated containment leakagerateexceeding 0.75L,or(b)withthemeasuredcombinedleakagerateforallpenetrations andvalvessubjecttoTypesBandCtestsexceeding 0.60L,restoretheoverallintegrated leakagerateto<0.75Landthecoimttbined leakagerateforallpenetrations andvalvessubjec$toTypeBandCteststo<0.60Lpriortoincreasing thePeactorCoolantSystemtemperature above$00'F.SURVEILLANCEREOUIREMENTS 4.6.1.2Thecontainment leakageratesshallbedemonstrated atthefollowing testscheduleandshallbedetermined inconformance withthecriteriaspecified inAppendixJof10CFR50usingthemethodsandprovisions ofANSIN45.4-1972:
| |
| Yl~~A-4~'-44s4a4e-)-chal-1 | |
| -be-cenducted-at t-N-month-iMa.val~uHng. | | -be-cenducted-at t-N-month-iMa.val~uHng. |
| skukdeer+od;.et-aha-l-l-be-cenduct-ed-du.r4og
| | skukde er+od;.et-aha-l-l-be-cenduct-ed-du.r4og |
| -theshv4dewTb~SA,8,C,<g6Eo~agg.X~QrP~Qed amelLCC.+hr~bI~Lee-4~P~~l+es4,~ | | -the shv4dew Tb~S A, 8, C,<g 6 Eo~agg.X~QrP~Qed amel LCC.+hr~bI~Lee-4~P~~l+es4,~ |
| <k~ba-.~~d~~(r~md.A-weem<+4reIbAA-Irem~%s s~i4'I'~1~+~<diz~4otocta.~o,'cA> | | <k~ba-.~~d~~(r~m d.A-wee m<+4 reIbAA-Irem~%s s~i4'I'~1~+~<diz~4o to ct a.~o,'cA>wodI4I~+~>+~~~~mw~p flows.4.E~a.O~Wni~~+ |
| wodI4I~+~>+~~~~mw~pflows.4.E~a.O~Wni~~+ | | O.ir 1I cJC-5kCJUL~g~Ig,~+~Q.iA a~P Ii~~~+1~N f 8 C*I~La~0%'i+ic9M 5~4+~<41 ch+Io&QO, Q~r~~g+Qpti~p+I'c~~aqe.o~ps+Stan I-S)D.C.COOK-UNIT 2 3/4 6-2 CON TAIHHEHT SYSTEMS SURVEILLANCE RE UERMEhTS Continued g~g~~4-4o-be-e~~eat |
| O.ir1IcJC-5kCJUL~g~Ig,~+~Q.iAa~PIi~~~+1~Nf8C*I~La~0%'i+ic9M5~4+~<41ch+Io&QO,Q~r~~g+Qpti~p+I'c~~aqe.o~ps+StanI-S)D.C.COOK-UNIT23/46-2 CONTAIHHEHTSYSTEMSSURVEILLANCE REUERMEhTSContinued g~g~~4-4o-be-e~~eat | | -t measured-l-eatage-r ndu~Mw Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.er~nmb&~+em, The provisions of Specification 4.0.2 are not applicable. |
| -tmeasured-l-eatage-r ndu~MwEachcontainment airlockshallbeverifiedtobeincompliance withtherequirements ofSpecification 3.6.1.3.er~nmb&~+em,Theprovisions ofSpecification 4.0.2arenotapplicable. | | f One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which.allows the provisions of Technical Specification 4.0.8 to be applicable. |
| fOne-timeexemption to10CFR50,AppendixJ,SectionsIII.D.2(a) andIII.D.3,which.allowstheprovisions ofTechnical Specification 4.0.8tobeapplicable.
| | COOK NUCLEAR PLANT-UNIT 2 3/4 6-3 ARE%)MENT NO.444. |
| COOKNUCLEARPLANT-UNIT23/46-3ARE%)MENT NO.444.
| | ATTACHMENT 3 TO AEP:NRC:1215 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of sL~, 0.25 percent by weight of the containment air per 24 hours at P12.0 psig, and b.A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,.APPLICABILITY: |
| ATTACHMENT 3TOAEP:NRC:1215 PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES CONTAINMENT SYSTEMSCONTAINMENT LEAKAGELIMITINGCONDITION FOROPERATION 3.6.1.2Containment leakageratesshallbelimitedto:a.Anoverallintegrated leakagerateofsL~,0.25percentbyweightofthecontainment airper24hoursatP12.0psig,andb.Acombinedleakagerateofs0.60L,forallpenetrations andvalvessubjecttoTypesBandCtestswhenpressurized toP,.APPLICABILITY: | | Modes 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L~restore the leakage rate(s)to within the limit(s)prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6'.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: |
| Modes1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegrated containment leakagerateexceeding 0.75L,or(b)withthemeasuredcombinedleakagerateforallpenetrations andvalvessubjecttoTypesBandCtestsexceeding 0.60L~restoretheleakagerate(s)towithinthelimit(s)priortoincreasing theReactorCoolantSystemtemperature above200'F.SURVEILLANCE REUIREMENTS 4.6'.2Thecontainment leakageratesshallbedemonstrated atthefollowing testscheduleandshallbedetermined inconformance withthecriteriaspecified inAppendixJof10CFR50usingthemethodsandprovisions ofANSIN45.4-1972:
| | a~Types A, B, and C (Overall Integrated and Local Combined Leakage Rate)testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions. |
| a~TypesA,B,andC(OverallIntegrated andLocalCombinedLeakageRate)testingshallbeconducted inaccordance withtherequirements specified inAppendixJto10CFR50,asmodifiedbyapprovedexemptions. | | b.Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.The provisions of Specification 4.0.2 are not applicable. |
| b.Eachcontainment airlockshallbeverifiedtobeincompliance withtherequirements ofSpecification 3.6.1.3.Theprovisions ofSpecification 4.0.2arenotapplicable. | | COOK NUCLEAR PLANT-UNIT 1 3/4 6-2 AMENDMENT NO. |
| COOKNUCLEARPLANT-UNIT13/46-2AMENDMENT NO.
| | This page intentionally left blank.COOK NUCLEAR PLANT-UNIT 1 3/4 6-3 AMENDMENT NO.440, CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of sL0.25 percent by weight of the containment air per 24 hours at P12.0 psig, and b.A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,.APPLICABILITY: |
| Thispageintentionally leftblank.COOKNUCLEARPLANT-UNIT13/46-3AMENDMENT NO.440, CONTAINMENT SYSTEMSCONTAINMENT LEAKAGELIMITINGCONDITION FOROPERATION 3.6.1.2Containment leakageratesshallbelimitedto:a.Anoverallintegrated leakagerateofsL0.25percentbyweightofthecontainment airper24hoursatP12.0psig,andb.Acombinedleakagerateofs0.60L,forallpenetrations andvalvessubjecttoTypesBandCtestswhenpressurized toP,.APPLICABILITY:
| | Modes 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L~, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 Lrestore the overall integrated leakage rate to s0.75 L, and the combined leakage rate for all penetrations and valves subject to Type B and C tests to z0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: |
| Modes1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegrated containment leakagerateexceeding 0.75L~,or(b)withthemeasuredcombinedleakagerateforallpenetrations andvalvessubjecttoTypesBandCtestsexceeding 0.60Lrestoretheoverallintegrated leakageratetos0.75L,andthecombinedleakagerateforallpenetrations andvalvessubjecttoTypeBandCteststoz0.60L,priortoincreasing theReactorCoolantSystemtemperature above200'F.SURVEILLANCE REUIREMENTS 4.6.1.2Thecontainment leakageratesshallbedemonstrated atthefollowing testscheduleandshallbedetermined inconformance withthecriteriaspecified inAppendixJof10CFR50usingthemethodsandprovisions ofANSIN45.4-1972:
| | a.Types A, B, and C (Overall Integrated and Local Combined Leakage Rate)testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.t b.Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.c~The provisions of Specification 4.0.2 are not applicable. |
| a.TypesA,B,andC(OverallIntegrated andLocalCombinedLeakageRate)testingshallbeconducted inaccordance withtherequirements specified inAppendixJto10CFR50,asmodifiedbyapprovedexemptions.t b.Eachcontainment airlockshallbeverifiedtobeincompliance withtherequirements ofSpecification 3.6.1.3.c~Theprovisions ofSpecification 4.0.2arenotapplicable. | | One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which allows the provisions of Technical Specification 4.0.8 to be applicable. |
| One-timeexemption to10CFR50,AppendixJ,SectionsIII.D.2(a) andIII.D.3,whichallowstheprovisions ofTechnical Specification 4.0.8tobeapplicable. | | COOK NUCLEAR PLANT-UNIT 2 3/4 6-2 AMENDMENT NO.46&, |
| COOKNUCLEARPLANT-UNIT23/46-2AMENDMENT NO.46&,
| |
| ) | | ) |
| Thispageintentionally leftblank.COOKNUCLEARPLANT-UNIT23/46-3AMENDMENT NO~}}
| | This page intentionally left blank.COOK NUCLEAR PLANT-UNIT 2 3/4 6-3 AMENDMENT NO~}} |
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ML17335A3581998-12-0303 December 1998
Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses
ML17335A3681998-12-0303 December 1998
Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys
ML17335A3651998-12-0303 December 1998
Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors
ML17335A3621998-12-0303 December 1998
Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos
ML17325B4431998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr
ML17335A4071998-11-0202 November 1998
Rev 4 to Cook Nuclear Plant Restart Plan.
ML17335A2781998-10-0808 October 1998
Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required
ML17335A2691998-10-0808 October 1998
Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5
ML17335A2651998-10-0808 October 1998
Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp.
ML17335A2341998-09-14014 September 1998
Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm
ML17335A2301998-09-12012 September 1998
Rev 3 to Cook Nuclear Plant Restart Plan.
ML17335A2721998-09-0404 September 1998
Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project.
ML17335A2751998-09-0202 September 1998
Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly.
ML17335A1931998-08-28028 August 1998
Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000
ML17335A2731998-08-21021 August 1998
Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package.
ML17334A7301998-05-0606 May 1998
Rev 2 of Cook Nuclear Plant Restart Plan.
ML17325B5271998-04-0707 April 1998
Rev 1 to Cook Nuclear Plant Restart Plan.
ML17334B8041998-04-0303 April 1998
Rev 1 to Valve IST Program for DCP Third 10-Yr Interval.
ML17325B5261998-03-0707 March 1998
Rev 0 to Cook Nuclear Plant Restart Plan.
ML17334B7031998-03-0303 March 1998
Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases
ML20212A7051997-10-21021 October 1997
Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement
ML17333B0751997-10-0808 October 1997
Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR
ML17333B0451997-09-19019 September 1997
Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS
ML17333A9891997-08-11011 August 1997
Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI
ML17333A9851997-08-11011 August 1997
Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable
ML17335A2121997-08-0101 August 1997
Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig.
ML17333A8301997-03-26026 March 1997
Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions
ML17333A8331997-03-26026 March 1997
Proposed Tech Specs Involving 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 in Prior Amend
ML17333A8261997-03-26026 March 1997
Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06
ML20135C3781997-02-24024 February 1997
Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements
ML17333A7161996-12-20020 December 1996
Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI
ML17333A7151996-12-20020 December 1996
Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A5161996-07-22022 July 1996
Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge
ML17334B5951996-07-11011 July 1996
Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt
ML17333A4771996-06-19019 June 1996
Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05
ML17333A4841996-06-11011 June 1996
ISI & Testing.
ML17333A4651996-06-11011 June 1996
Proposed Tech Specs Re Administrative Controls Related to QA
1999-09-23
[Table view] |
Text
ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 PDR ADOCK 05000315 P.....PDR COHTAINHENT SYST:-~S CONTAINS=.HT LDKAC=LIl'IITING CONDITION rOR 0."=RATIOH 3.6.1.2 Containm nt leakag rates shall be limited to: a.An overall integrat d leakage rat of<L, 0.25 p rc nt by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 12.0 psig, and b.A combin d leakaoe rate of<0.60 La for all penetra ions and valves subj ct to Type B and C tests wh n pr ssuriz d to P APPLICABILiTY:
YIODES 1, 2, 3 and 4.ACTION: Mith eith r (a)th m asured ov rail int rated con,ainm nt 1 akage rate exceeding 0.75 La or (b)with the measured combined leakage rate for all p netrations and valv s subject to Types B and C tests exc eding 0.60 L r store th leakag rate(s)to within the limit(s)prior to increasing the R ac or Coolant Syst m t mp rature above 200'F.SURYEILLAHC" REQUIRE,"!="H S 4.6.1.2 Th~con.ainm nt leakag rat s shall b d monstrat d at th following t~st schedule and shall be determined in conforrance with the crit ria sp cifi d in Appendix J of 10 CFR 50 using the m thods and provisions of ANSI N45.4-1972:
a.shu4de 6 Ql Q (Qy~~TM~p~~CL,MA LCh'\0~4 I~lgg 5 g)4k 04 wW.+W~~i~e.n~+5 s~i~i~~~~~g,pi~+aqpnoued w<~p4><I p t<+<~Q~<p)~<I<ghee-ll~VEC LgKEA g~PtI++~~\>6 Sp~t<'+g o z~~~a+~)p).~4~~$~I 41 (.~4>~D.C.COOK-UNIT 1 3/4 6-2 Amendment Ho.+8-)
uheequent-Typ~~est s-s~k-b o-sense sos-me.~ae-the-aha
~ay-be-resumed a'ach containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3-%45 pR-i~Yon4i>~~g,h~(+
b)AQIc COOK NUCLEAR PLANT-UNIT 1 3/4 6-3 AMENDMENT NO.~-
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of<L, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 12 psig.b.A combined leakage rate of<0.60 L for all penetrations and valves subject to Type B and C test3, when pressurized to P.a'PPLICABILITY:
MODES 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L, restore the overall integrated leakage rate to<0.75 L and the coimttbined leakage rate for all penetrations and valves subjec$to Type B and C tests to<0.60 L prior to increasing the Peactor Coolant System temperature above$00'F.SURVEI LLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
Yl~~A-4~'-4 4s 4a4e-)-chal-1
-be-cenducted-at t-N-month-iMa.val~uHng.
skukde er+od;.et-aha-l-l-be-cenduct-ed-du.r4og
-the shv4dew Tb~S A, 8, C,<g 6 Eo~agg.X~QrP~Qed amel LCC.+hr~bI~Lee-4~P~~l+es4,~
<k~ba-.~~d~~(r~m d.A-wee m<+4 reIbAA-Irem~%s s~i4'I'~1~+~<diz~4o to ct a.~o,'cA>wodI4I~+~>+~~~~mw~p flows.4.E~a.O~Wni~~+
O.ir 1I cJC-5kCJUL~g~Ig,~+~Q.iA a~P Ii~~~+1~N f 8 C*I~La~0%'i+ic9M 5~4+~<41 ch+Io&QO, Q~r~~g+Qpti~p+I'c~~aqe.o~ps+Stan I-S)D.C.COOK-UNIT 2 3/4 6-2 CON TAIHHEHT SYSTEMS SURVEILLANCE RE UERMEhTS Continued g~g~~4-4o-be-e~~eat
-t measured-l-eatage-r ndu~Mw Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.er~nmb&~+em, The provisions of Specification 4.0.2 are not applicable.
f One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which.allows the provisions of Technical Specification 4.0.8 to be applicable.
COOK NUCLEAR PLANT-UNIT 2 3/4 6-3 ARE%)MENT NO.444.
ATTACHMENT 3 TO AEP:NRC:1215 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of sL~, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P12.0 psig, and b.A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,.APPLICABILITY:
Modes 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L~restore the leakage rate(s)to within the limit(s)prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6'.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a~Types A, B, and C (Overall Integrated and Local Combined Leakage Rate)testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.
b.Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.The provisions of Specification 4.0.2 are not applicable.
COOK NUCLEAR PLANT-UNIT 1 3/4 6-2 AMENDMENT NO.
This page intentionally left blank.COOK NUCLEAR PLANT-UNIT 1 3/4 6-3 AMENDMENT NO.440, CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: a.An overall integrated leakage rate of sL0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P12.0 psig, and b.A combined leakage rate of s0.60 L, for all penetrations and valves subject to Types B and C tests when pressurized to P,.APPLICABILITY:
Modes 1, 2, 3 and 4.ACTION: With either (a)the measured overall integrated containment leakage rate exceeding 0.75 L~, or (b)with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 Lrestore the overall integrated leakage rate to s0.75 L, and the combined leakage rate for all penetrations and valves subject to Type B and C tests to z0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F.SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a.Types A, B, and C (Overall Integrated and Local Combined Leakage Rate)testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions.t b.Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.c~The provisions of Specification 4.0.2 are not applicable.
One-time exemption to 10 CFR 50, Appendix J, Sections III.D.2(a) and III.D.3, which allows the provisions of Technical Specification 4.0.8 to be applicable.
COOK NUCLEAR PLANT-UNIT 2 3/4 6-2 AMENDMENT NO.46&,
)
This page intentionally left blank.COOK NUCLEAR PLANT-UNIT 2 3/4 6-3 AMENDMENT NO~
