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| {{#Wiki_filter:ATTACHMENT 2TOAEP:NRC:1245 EXISTINGTECHNICAL SPECIFICATION PAGESMARKEDTOREFLECTPROPOSEDCHANGES96i2270ii2 96i220PDRADQCK050003i5(IPPDR REACTORCCOLAHTSYS~c.3'l4;4.IQ;STRUCTURAL LhTEGRITY ASHECODECLASSI2and3CCHPOHEHTS LIHITIHGCOHDITIOH FOROPERATIOH 3.4.10.1Thestruc-.ural integrity ofBSHECodeClass1,2and3camoonents shallbemaintained inacŽ"roance withSpeci,icatian4.4.10.1~APPLICABILITY: | | {{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1245 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 96i2270ii2 96i220 PDR ADQCK 050003i5 (I P PDR REACTOR CCOLAHT SYS~c.3'l4;4.IQ;STRUCTURAL LhTEGRITY ASHE CODE CLASS I 2 and 3 CCHPOHEHTS LIHITIHG COHDITIOH FOR OPERATIOH 3.4.10.1 The struc-.ural integrity of BSHE Code Class 1, 2 and 3 camoonents shall be maintained in acŽ"roance with Speci, icatian 4.4.10.1~APPLICABILITY: |
| AfLBODESACT.QM:)IIa.b.Viththestructural integrity afanyASHECadeClass1comoonent(s) notconforming tatheabaverequirements, resmrethestruc:ural integri-y aftheaffectedcomponent,'s) tawithinitslimitorisolatetheaffec=edcamoonent(s) priortancreasing theReac.orCoolantSystemtemoerature mor.han50'Faoaveweminimumtemperature requiredbyHGTc"nsiderat cns.Mith".estr=-.ralintegri:y afanvASH=CadeClass2conoonent(s) notconforming a:..eaboverecuirements,restorethestrcturalintegriyof:heaf..edc"moonent',s)
| | Af L BODES ACT.QM:)I I a.b.Vith the structural integrity af any ASHE Cade Class 1 comoonent(s) not conforming ta the abave requirements, resmre the struc:ural integri-y af the affected component,'s) ta within its limit or isolate the affec=ed camoonent(s) prior ta ncreasing the Reac.or Coolant System temoerature mor.han 50'F aoave we minimum temperature required by HGT c"nsiderat cns.Mith".e str=-.ral integri:y af anv ASH=Cade Class 2 conoonent(s) not conforming a:..e above recui rements, restore the str ctural integri y of:he af..ed c"moonent',s) |
| =-withiniwlimitarisclatetheaffec=edc"moonent(s} | | =-within i w limit ar isclate the affec=ed c"moonent(s} |
| or.'cr:":ncrzasngtheRectorCcolantSystemtemoerature | | or.'cr:":ncrzas ng the Re ctor Ccolant System temoerature |
| ~"ove2CC."-.Viththes".ru~ural integri.yc,any'SHcnotconfoming tatheabcverecuirements, integrity oft,.".eaf,e'cted c"moonent',s) | | ~"ove 2CC."-.Vith the s".ru~ural integri.y c, any'SHc not confoming ta the abcve recuirements, integrity of t,.".e af,e'cted c"moonent',s) |
| :=the.affec-adc"mpcnent(s) fr.mservice.'."ce C'iass3c";.,cc,.en,'s)rosorethestrc:uralithinits1imi:orisolated.Theprovisions ofSoecificat-on 3.0.4arnotapplicable. | | :=the.affec-ad c"mpcnent(s) fr.m service.'."ce C'iass 3 c";.,cc,.en,'s)ros ore the str c:ural i thi n i ts 1 imi: or isolate d.The provisions of Soecificat-on 3.0.4 ar not applicable. |
| SlRV'EILANCc RcQUIRPBYS 4.4.10.1InadditionwtherequirmentsofSoecif'.cation 4.0.5,eachreactorcoolantpumpfi~neelshallbeinspec=ed D.C.COOK-UNXT13/44-33Amendment No.98 insertAbyeitherqualified in-placeUTexamination overthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (magnetic particletestingand/orpenetrant testing)ofexposedsurfacesdefinedbythevolumeofthedisassembled flywheels onceevery10years. | | SlRV'EILANCc RcQUIRPBYS 4.4.10.1 In addition w the requir ments of Soecif'.cation 4.0.5, each reactor coolant pump fi~neel shall be inspec=ed D.C.COOK-UNXT 1 3/4 4-33 Amendment No.98 insert A by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years. |
| Pc&CHlRCCOU8TSY~3.4.10~iUCTURAL IHTcGRI7f ASHYCQQECLASS1.2and3CQHPQHBlTS L~H6CQHOITZOH FOROPHATTOHL/3.4.10.1Thes~wraIfn~~ri.gofAMhdaClassI,2and3c~onenwsha11bemafntained inaccordswithSpecificat',on 4.4.10.1. | | Pc&CHlR CCOU8T SY~3.4.10~iUCTURAL IHTcGRI7f ASHY CQQE CLASS 1.2 and 3 CQHPQHBlTS L~H6 CQHOITZOH FOR OPHATTOH L/3.4.10.1 The s~wraI fn~~ri.g of AM hda Class I, 2 and 3 c~onenw sha11 be mafntained in accords with Specificat',on 4.4.10.1.Appuua>I.an: |
| Appuua>I.an: | | Au.mam~iONi Vith~%a strucmra1<ntegrity of any ASIDE Ccc!e C1ass 1 c~onen (s)not conforming to the above mq'uirments, res-"m the strururaI integ.ity of Ne affec~ct ccamonent(s} |
| Au.mam~iONiVith~%astrucmra1 | | M w$'Min i~I'mt or fsQIaM~e af ected ceaccnent,'s) prior ts incr asian"e Reac"r Coolant Sys~~erasure mre~SO~7 above"~mini~~eratu~~unbred by NOT considerations. |
| <ntegrity ofanyASIDECcc!eC1ass1c~onen(s)notconforming totheabovemq'uirments, res-"mthestrururaI integ.ity ofNeaffec~ctccamonent(s} | | 8th~~a st.W~ra1 fntagrfty of any ASIDE C"Ce Class 2 cwonent(s) not c"nforaing to Ale above requirements, answer tM st.~-raI fntegri y of the affected cccconent(s) w wi~5fn fts I'.sit or isoIata the af ec~caeyonent(s) prior to increasing Ne Rear"'r Coo1an: Sys~tennerztura above 8lQ~F.c 0th".e s~-.ac-"raI inta~i~g of any APE no-c"nforaing to Ne move~ufrmnts, integri.o.C..e a, ared anent(s)-- |
| Mw$'Mini~I'mtorfsQIaM~eafectedceaccnent,'s) priortsincrasian"eReac"rCoolantSys~~erasuremre~SO~7above"~mini~~eratu~~unbredbyNOTconsiderations.
| | t0e af i ac~~onent(5)fr<<2 service.Cede Class 3 c~onent(s) res"w e v~'retral wit:,in ia lid"".isoIa->i,e provisions of Spec";fcaticn 3.0.'r not acpI',cable. |
| 8th~~ast.W~ra1fntagrfty ofanyASIDEC"CeClass2cwonent(s) notc"nforaing toAleaboverequirements, answertMst.~-raIfntegriyoftheaffectedcccconent(s) wwi~5fnftsI'.sitorisoIatatheafec~caeyonent(s) priortoincreasing NeRear"'rCoo1an:Sys~tennerztura above8lQ~F.c0th".es~-.ac-"raI inta~i~gofanyAPEno-c"nforaing toNemove~ufrmnts, integri.o.C..ea,aredanent(s)-- | |
| t0eafiac~~onent(5) fr<<2service.CedeClass3c~onent(s) res"wev~'retral wit:,inialid"".isoIa->i,eprovisions ofSpec";fcaticn3.0.'rnotacpI',cable.
| |
| RPgE:~re:- | | RPgE:~re:- |
| RUR~PPi5<.4.10.1lnadd'.ionatherequireena ofSpecifiat'.cn 4.0."-,each~ac-"rcoolanpa=lywnee1shallbeinsaec~+~5c~P InsertBbyeitherqualified in-placeUTexamination overthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (magnetic particletestingand/orpenetrant testing)ofexposedsurfacesdefinedbythevolumeofthedisassembled flywheels onceevery10years.
| | R U R~PPi5<.4.10.1 ln add'.ion a the requireena of Specifiat'.cn 4.0."-, each~ac-"r coolan pa=lywnee1 shall be insaec~+~5c~P Insert B by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years. |
| 0 ATTACHMENT 3TOAEP:NRC:1245 PROPOSEDREVISEDTECHNICAL SPECIFICATION PAGES 3/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEM3/4.4.10STRUCTURAL INTEGRITY ASMECODECLASS12Gild3COMPONENTS LIMITINGCONDITION FOROPERATION 3.4.10.1Thestructural integrity oftheASMECodeClass1,2and3components shallbemaintained inaccordance withSpecification 4.4.10.1. | | 0 ATTACHMENT 3 TO AEP:NRC:1245 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 Gild 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.APPLICABILITY: |
| APPLICABILITY: | | ALL MODES ACTION: With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of th affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations. |
| ALLMODESACTION:Withthestructural integrity ofanyASMECodeClass1component(s) notconforming totheaboverequirements, restorethestructural integrity ofthaffectedcomponent(s) towithinitslimitorisolatetheaffectedcomponent(s) priortoincreasing theReactorCoolantSystemtemperature morethan50'Fabovetheminimumtemperature requiredbyNDTconsiderations.
| | With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.The provisions of Specification 3.0.4 are not applicable. |
| Withthestructural integrity ofanyASMECodeClass2component(s) notconforming totheaboverequirements, restorethestructural integrity oftheaffectedcomponent(s) towithinitslimitorisolatetheaffectedcomponent(s) priortoincreasing theReactorCoolantSystemtemperature above200'F.Withthestructural integrity ofanyASMECodeClass3component(s) notconforming totheaboverequirements, restorethestructural integrity oftheaffectedcomponent(s) towithinitslimitorisolatetheaffectedcomponent(s) fromservice.Theprovisions ofSpecification 3.0.4arenotapplicable.
| | SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.COOK NUCLEAR PLANT-UNIT I Page 3/4 4-33 |
| SURVEILLANCE REUIREMENTS 4.4.10.1Inadditiontotherequirements ofSpecification 4.0.5,eachreactorcoolantpumpflywheelshallbeinspected byeitherqualified in-placeUTexamination overthevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (magnetic particletestingand/orpenetrant testing)ofexposedsurfacesdefinedbythevolumeofthedisassembled flywheels onceevery10years.COOKNUCLEARPLANT-UNIT IPage3/44-33 | | ~"'/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 gild 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.APPLICABILITY: |
| ~"'/4LIMITINGCONDITIONS FOROPERATION ANDSURVEILLANCE REQUIREMENTS 3/4.4REACTORCOOLANTSYSTEM3/4.4.10STRUCTURAL INTEGRITY ASMECODECLASS12gild3COMPONENTS LIMITINGCONDITION FOROPERATION 3.4.10.1Thestructural integrity ofASMECodeClass1,2and3components shallbemaintained inaccordance withSpecification 4.4.10.1.APPLICABILITY: | | ALL MODES ACTION: ao With the structural integrity of any ASME Code Class 1 c"mponent(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations. |
| ALLMODESACTION:aoWiththestructural integrity ofanyASMECodeClass1c"mponent(s) notconforming totheaboverequirements, restorethestructural integrity oftheaffectedcomponent(s) towithinitslimitorisolatetheaffectedcomponent(s) priortoincreasing theReactorCoolantSystemtemperature morethan50'Fabovetheminimumtemperature requiredbyNDTconsiderations.
| | b.With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.c.With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.d.-The provisions of Specification 3.0.4 are not applicable. |
| b.Withthestructural integrity ofanyASMECodeClass2component(s) notconforming totheaboverequirements, restorethestructural integrity oftheaffectedcomponent(s) towithinitslimitorisolatetheaffectedcomponent(s) priortoincreasing theReactorCoolantSystemtemperature above200'F.c.Withthestructural integrity ofanyASMECodeClass3component(s) notconforming totheaboverequirements, restorethestructural integrity oftheaffectedcomponent(s) towithinitslimitorisolatetheaffectedcomponent(s) fromservice.d.-Theprovisions ofSpecification 3.0.4arenotapplicable. | | SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over.the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of..e disassembled flywheels once every 10 years.COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-31}} |
| SURVEILLANCE REUIREMENTS 4.4.10.1Inadditiontotherequirements ofSpecification 4.0.5,eachreactorcoolantpumpflywheelshallbeinspected byeitherqualified in-placeUTexamination over.thevolumefromtheinnerboreoftheflywheeltothecircleofone-halftheouterradiusorasurfaceexamination (magnetic particletestingand/orpenetrant testing)ofexposedsurfacesdefinedbythevolumeof..edisassembled flywheels onceevery10years.COOKNUCLEARPLANT-UNIT 2Page3/44-31}} | |
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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:1245 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 96i2270ii2 96i220 PDR ADQCK 050003i5 (I P PDR REACTOR CCOLAHT SYS~c.3'l4;4.IQ;STRUCTURAL LhTEGRITY ASHE CODE CLASS I 2 and 3 CCHPOHEHTS LIHITIHG COHDITIOH FOR OPERATIOH 3.4.10.1 The struc-.ural integrity of BSHE Code Class 1, 2 and 3 camoonents shall be maintained in acŽ"roance with Speci, icatian 4.4.10.1~APPLICABILITY:
Af L BODES ACT.QM:)I I a.b.Vith the structural integrity af any ASHE Cade Class 1 comoonent(s) not conforming ta the abave requirements, resmre the struc:ural integri-y af the affected component,'s) ta within its limit or isolate the affec=ed camoonent(s) prior ta ncreasing the Reac.or Coolant System temoerature mor.han 50'F aoave we minimum temperature required by HGT c"nsiderat cns.Mith".e str=-.ral integri:y af anv ASH=Cade Class 2 conoonent(s) not conforming a:..e above recui rements, restore the str ctural integri y of:he af..ed c"moonent',s)
=-within i w limit ar isclate the affec=ed c"moonent(s}
or.'cr:":ncrzas ng the Re ctor Ccolant System temoerature
~"ove 2CC."-.Vith the s".ru~ural integri.y c, any'SHc not confoming ta the abcve recuirements, integrity of t,.".e af,e'cted c"moonent',s)
- =the.affec-ad c"mpcnent(s) fr.m service.'."ce C'iass 3 c";.,cc,.en,'s)ros ore the str c:ural i thi n i ts 1 imi: or isolate d.The provisions of Soecificat-on 3.0.4 ar not applicable.
SlRV'EILANCc RcQUIRPBYS 4.4.10.1 In addition w the requir ments of Soecif'.cation 4.0.5, each reactor coolant pump fi~neel shall be inspec=ed D.C.COOK-UNXT 1 3/4 4-33 Amendment No.98 insert A by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
Pc&CHlR CCOU8T SY~3.4.10~iUCTURAL IHTcGRI7f ASHY CQQE CLASS 1.2 and 3 CQHPQHBlTS L~H6 CQHOITZOH FOR OPHATTOH L/3.4.10.1 The s~wraI fn~~ri.g of AM hda Class I, 2 and 3 c~onenw sha11 be mafntained in accords with Specificat',on 4.4.10.1.Appuua>I.an:
Au.mam~iONi Vith~%a strucmra1<ntegrity of any ASIDE Ccc!e C1ass 1 c~onen (s)not conforming to the above mq'uirments, res-"m the strururaI integ.ity of Ne affec~ct ccamonent(s}
M w$'Min i~I'mt or fsQIaM~e af ected ceaccnent,'s) prior ts incr asian"e Reac"r Coolant Sys~~erasure mre~SO~7 above"~mini~~eratu~~unbred by NOT considerations.
8th~~a st.W~ra1 fntagrfty of any ASIDE C"Ce Class 2 cwonent(s) not c"nforaing to Ale above requirements, answer tM st.~-raI fntegri y of the affected cccconent(s) w wi~5fn fts I'.sit or isoIata the af ec~caeyonent(s) prior to increasing Ne Rear"'r Coo1an: Sys~tennerztura above 8lQ~F.c 0th".e s~-.ac-"raI inta~i~g of any APE no-c"nforaing to Ne move~ufrmnts, integri.o.C..e a, ared anent(s)--
t0e af i ac~~onent(5)fr<<2 service.Cede Class 3 c~onent(s) res"w e v~'retral wit:,in ia lid"".isoIa->i,e provisions of Spec";fcaticn 3.0.'r not acpI',cable.
RPgE:~re:-
R U R~PPi5<.4.10.1 ln add'.ion a the requireena of Specifiat'.cn 4.0."-, each~ac-"r coolan pa=lywnee1 shall be insaec~+~5c~P Insert B by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
0 ATTACHMENT 3 TO AEP:NRC:1245 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 Gild 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.APPLICABILITY:
ALL MODES ACTION: With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of th affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.COOK NUCLEAR PLANT-UNIT I Page 3/4 4-33
~"'/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 gild 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.APPLICABILITY:
ALL MODES ACTION: ao With the structural integrity of any ASME Code Class 1 c"mponent(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
b.With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.c.With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.d.-The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over.the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of..e disassembled flywheels once every 10 years.COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-31
