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| {{#Wiki_filter:ATTACHMENT2TOAEP:NRC:1215EXISTINGTECHNICALSPECIFICATIONPAGESMARKEDTOREFLECTPROPOSEDCHANGES9407Z50177940719PDRADOCK05000315P.....PDR COHTAINHENTSYST:-~SCONTAINS=.HTLDKAC=LIl'IITINGCONDITIONrOR0."=RATIOH3.6.1.2Containmntleakagratesshallbelimitedto:a.Anoverallintegratdleakageratof<L,0.25prcntbyweightofthecontainmentairper24hoursatP,12.0psig,andb.Acombindleakaoerateof<0.60LaforallpenetraionsandvalvessubjcttoTypeBandCtestswhnprssurizdtoPAPPLICABILiTY:YIODES1,2,3and4.ACTION:Mitheithr(a)thmasuredovrailintratedcon,ainmnt1akagerateexceeding0.75Laor(b)withthemeasuredcombinedleakagerateforallpnetrationsandvalvssubjecttoTypesBandCtestsexceding0.60Lrstorethleakagrate(s)towithinthelimit(s)priortoincreasingtheRacorCoolantSystmtmpratureabove200'F.SURYEILLAHC"REQUIRE,"!="HS4.6.1.2Th~con.ainmntleakagratsshallbdmonstratdatthfollowingt~stscheduleandshallbedeterminedinconforrancewiththecritriaspcifidinAppendixJof10CFR50usingthemthodsandprovisionsofANSIN45.4-1972: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~~$~I41(.~4>~D.C.COOK-UNIT13/46-2AmendmentHo.+8-) | | {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 P..... |
| uheequent-Typ~~ests-s~k-bo-sensesos-me.~ae-the-aha~ay-be-resumeda'achcontainmentairlockshallbeverifiedtobeincompliancewiththerequirementsofSpecification3.6.1.3-%45pR-i~Yon4i>~~g,h~(+b)AQIcCOOKNUCLEARPLANT-UNIT13/46-3AMENDMENTNO.~- | | PDR ADOCK 05000315 PDR |
| CONTAINMENTSYSTEMSCONTAINMENTLEAKAGELIMITINGCONDITIONFOROPERATION3.6.1.2Containmentleakageratesshallbelimitedto:a.Anoverallintegratedleakagerateof<L,0.25percentbyweightofthecontainmentairper24hoursatP,12psig.b.Acombinedleakagerateof<0.60LforallpenetrationsandvalvessubjecttoTypeBandCtest3,whenpressurizedtoP.a'PPLICABILITY:MODES1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegratedcontainmentleakagerateexceeding0.75L,or(b)withthemeasuredcombinedleakagerateforallpenetrationsandvalvessubjecttoTypesBandCtestsexceeding0.60L,restoretheoverallintegratedleakagerateto<0.75Landthecoimttbinedleakagerateforallpenetrationsandvalvessubjec$toTypeBandCteststo<0.60LpriortoincreasingthePeactorCoolantSystemtemperatureabove$00'F.SURVEILLANCEREOUIREMENTS4.6.1.2ThecontainmentleakageratesshallbedemonstratedatthefollowingtestscheduleandshallbedeterminedinconformancewiththecriteriaspecifiedinAppendixJof10CFR50usingthemethodsandprovisionsofANSIN45.4-1972:Yl~~A-4~'-44s4a4e-)-chal-1-be-cenducted-at-40-t-N-month-iMa.val~uHng.skukdeer+od;.et-aha-l-l-be-cenduct-ed-du.r4og-theshv4dewTb~SA,8,C,<g6Eo~agg.X~QrP~QedamelLCC.+hr~bI~Lee-4~P~~l+es4,~<k~ba-.~~d~~(r~md.A-weem<+4reIbAA-Irem~%ss~i4'I'~1~+~<diz~4otocta.~o,'cA>wodI4I~+~>+~~~~mw~pflows.4.E~a.O~Wni~~+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 CONTAIHHEHTSYSTEMSSURVEILLANCEREUERMEhTSContinuedg~g~~4-4o-be-e~~eat-tmeasured-l-eatage-rndu~MwEachcontainmentairlockshallbeverifiedtobeincompliancewiththerequirementsofSpecification3.6.1.3.er~nmb&~+em,TheprovisionsofSpecification4.0.2arenotapplicable.fOne-timeexemptionto10CFR50,AppendixJ,SectionsIII.D.2(a)andIII.D.3,which.allowstheprovisionsofTechnicalSpecification4.0.8tobeapplicable.COOKNUCLEARPLANT-UNIT23/46-3ARE%)MENTNO.444.
| | |
| ATTACHMENT3TOAEP:NRC:1215PROPOSEDREVISEDTECHNICALSPECIFICATIONPAGES CONTAINMENTSYSTEMSCONTAINMENTLEAKAGELIMITINGCONDITIONFOROPERATION3.6.1.2Containmentleakageratesshallbelimitedto:a.AnoverallintegratedleakagerateofsL~,0.25percentbyweightofthecontainmentairper24hoursatP12.0psig,andb.Acombinedleakagerateofs0.60L,forallpenetrationsandvalvessubjecttoTypesBandCtestswhenpressurizedtoP,.APPLICABILITY:Modes1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegratedcontainmentleakagerateexceeding0.75L,or(b)withthemeasuredcombinedleakagerateforallpenetrationsandvalvessubjecttoTypesBandCtestsexceeding0.60L~restoretheleakagerate(s)towithinthelimit(s)priortoincreasingtheReactorCoolantSystemtemperatureabove200'F.SURVEILLANCEREUIREMENTS4.6'.2ThecontainmentleakageratesshallbedemonstratedatthefollowingtestscheduleandshallbedeterminedinconformancewiththecriteriaspecifiedinAppendixJof10CFR50usingthemethodsandprovisionsofANSIN45.4-1972:a~TypesA,B,andC(OverallIntegratedandLocalCombinedLeakageRate)testingshallbeconductedinaccordancewiththerequirementsspecifiedinAppendixJto10CFR50,asmodifiedbyapprovedexemptions.b.EachcontainmentairlockshallbeverifiedtobeincompliancewiththerequirementsofSpecification3.6.1.3.TheprovisionsofSpecification4.0.2arenotapplicable.COOKNUCLEARPLANT-UNIT13/46-2AMENDMENTNO.
| | COHTAINHENT SYST:-~S CONTAINS=.HT LDKAC= |
| Thispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT13/46-3AMENDMENTNO.440, CONTAINMENTSYSTEMSCONTAINMENTLEAKAGELIMITINGCONDITIONFOROPERATION3.6.1.2Containmentleakageratesshallbelimitedto:a.AnoverallintegratedleakagerateofsL0.25percentbyweightofthecontainmentairper24hoursatP12.0psig,andb.Acombinedleakagerateofs0.60L,forallpenetrationsandvalvessubjecttoTypesBandCtestswhenpressurizedtoP,.APPLICABILITY:Modes1,2,3and4.ACTION:Witheither(a)themeasuredoverallintegratedcontainmentleakagerateexceeding0.75L~,or(b)withthemeasuredcombinedleakagerateforallpenetrationsandvalvessubjecttoTypesBandCtestsexceeding0.60Lrestoretheoverallintegratedleakageratetos0.75L,andthecombinedleakagerateforallpenetrationsandvalvessubjecttoTypeBandCteststoz0.60L,priortoincreasingtheReactorCoolantSystemtemperatureabove200'F.SURVEILLANCEREUIREMENTS4.6.1.2ThecontainmentleakageratesshallbedemonstratedatthefollowingtestscheduleandshallbedeterminedinconformancewiththecriteriaspecifiedinAppendixJof10CFR50usingthemethodsandprovisionsofANSIN45.4-1972:a.TypesA,B,andC(OverallIntegratedandLocalCombinedLeakageRate)testingshallbeconductedinaccordancewiththerequirementsspecifiedinAppendixJto10CFR50,asmodifiedbyapprovedexemptions.tb.EachcontainmentairlockshallbeverifiedtobeincompliancewiththerequirementsofSpecification3.6.1.3.c~TheprovisionsofSpecification4.0.2arenotapplicable.One-timeexemptionto10CFR50,AppendixJ,SectionsIII.D.2(a)andIII.D.3,whichallowstheprovisionsofTechnicalSpecification4.0.8tobeapplicable.COOKNUCLEARPLANT-UNIT23/46-2AMENDMENTNO.46&,
| | 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: 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. |
| | ghee-ll shu4de lgg 5 g 6) 4k 04 Ql Q (Qy~~ TM~p~~ CL,MA LCh'\ 0~4 I~ |
| | wW. +W ~~i~e.n ~+5 s~i~i~ ~~ |
| | ~~g,pi~ + aqpnoued w<~p4>< |
| | p t < + < ~Q ~<p )~< I< ~ VEC LgKEA I |
| | g~PtI++~ ~\ >6 Sp~t<'+ |
| | ~~ ~)p).~4~~ |
| | $ ~ I 41 (.~4 >~ g o z ~a+ |
| | 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 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 . |
| | MODES 1, 2, 3 and 4. a'PPLICABILITY: |
| | 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 Yl ~~ ~'-4 criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972: |
| | 4a4e-)-chal-1 skukde A-4 be-cenducted-at 40-t et N-month iMa.val~uHng. |
| | aha-l-l-be-cenduct-ed-du.r4og 4s er+od;. |
| | the shv4dew Tb~S A, 8, C,<g 6 Eo~agg. X~QrP~Qed amel P~~l+es4,~ <k~ ba- .~~d ~~ LCC.+ |
| | (r ~m d.A-wee reIbAA-Irem~%s s~i4'I'~ 1~ +~<diz~ 4o to ct a.~o,'cA> wodI4I~+ |
| | hr~bI~ Lee-4~ |
| | m <+4 |
| | : 4. E~ ~ >+~~~ |
| | +1 ~N ~mw~p flows. |
| | a.O~Wni~~+ O.ir cJC -5kCJUL ~ g~Ig,~ +~ Q. iA a~P Ii~~~ |
| | 1I 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 hours at P 12.0 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 determined in conformance with the test schedule and shall be 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 sL 0.25 percent by weight of the containment air per 24 hours at P 12.0 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 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&, |
| | |
| ) | | ) |
| Thispageintentionallyleftblank.COOKNUCLEARPLANT-UNIT23/46-3AMENDMENTNO~}}
| | This page intentionally left blank. |
| | COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 AMENDMENT NO ~}} |
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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999 Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5611999-10-11011 October 1999 Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal ML17335A5431999-10-0101 October 1999 Proposed Tech Specs Re Containment Recirculation Sump Water Inventory ML17326A1591999-09-23023 September 1999 Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project ML17326A1461999-09-17017 September 1999 Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality ML17326A1181999-09-10010 September 1999 Proposed Tech Specs Pages,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 ML17326A0941999-08-17017 August 1999 Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section ML17326A1471999-05-28028 May 1999 Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2. ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5551999-04-19019 April 1999 Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. 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
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ATTACHMENT 2 TO AEP:NRC:1215 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9407Z50177 940719 P.....
PDR ADOCK 05000315 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.
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D. C. COOK-UNIT 1 3/4 6-2 Amendment Ho. +8-
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%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 .
MODES 1, 2, 3 and 4. a'PPLICABILITY:
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 Yl ~~ ~'-4 criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
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D. C. COOK - UNIT 2 3/4 6-2
CON TAIHHEHT SYSTEMS SURVEILLANCE RE UERMEhTS Continued g ~
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~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 P 12.0 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 determined in conformance with the test schedule and shall be 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.
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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 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 P 12.0 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 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&,
)
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COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 AMENDMENT NO ~