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Category:TECHNICAL SPECIFICATIONS
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 ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions 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 ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys 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 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 ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors 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. ML17335A2691998-10-0808 October 1998 Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5 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 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 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 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 ML17333A9851997-08-11011 August 1997 Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17333A9891997-08-11011 August 1997 Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI 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. ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 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 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 ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA ML17333A4221996-04-0808 April 1996 Revised Proposed Ts,Moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3571996-03-12012 March 1996 Proposed Tech Specs,Removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3,4 & 5 ML17333A3301996-02-29029 February 1996 Proposed Tech Specs Re Boric Acid Storage Sys Boron Concentration ML17333A3231996-02-26026 February 1996 Proposed TS 5.6.2 Re Increase in Max Nominal Fuel Assembly Enrichment Limit,Taking Credit for Use of Integral Fuel Burnable Absorber Matl ML17333A3221996-02-22022 February 1996 Proposed Tech Specs,Proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3171996-02-22022 February 1996 Proposed Tech Specs,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 ML17333A3121996-02-16016 February 1996 Proposed Tech Specs Section 3.6.1.6,removing Words Structure & Steel Liner to Be Consistent W/Unit 2 Containment Sys Wording ML17333A2671996-01-12012 January 1996 Proposed Tech Specs,Modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2411995-12-19019 December 1995 Proposed Tech Specs 3/4.6.1.2,3/4.6.1.3,3/4.6/1/6 & 3/4.6.1.7,replacing Option a Scheduling Requirements for Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) W/Requirement Per 10CFR50 App J Option B ML17332B0131995-11-10010 November 1995 Proposed Tech Specs Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9991995-10-20020 October 1995 Proposed Tech Specs Adding Exemption to TS 4.0.4 in SR for MSIV ML17332A9151995-08-0808 August 1995 Proposed Tech Specs Re Deletion of Component Cyclic or Transient Limit Table ML17332A8751995-08-0404 August 1995 Proposed Tech Specs for Repair of Hybrid Expansion Joint Sleeved SG Tubes ML17332A8291995-06-30030 June 1995 Proposed Tech Specs Re Fuel Reconstitution,Per GL 90-02 ML17332A8111995-06-20020 June 1995 Proposed Tech Specs Removing Fire Protection Systems from Licenses 1999-09-23
[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
[Table view] |
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t'@*44~~'"+S~)~~W,<<,t.k~'-J}~,...~aI,q~,'I~!~~w+i'=<il'J'Ii}"~)aw<v'~'L4s:~~VAttachment 2toAEP:NRC:1018 ProposedRevisedTechnical Specification Pages8703030051 870220PDRADOCK050003i5PPDR 0POWERDISRIBUTIONLIMITSSURVEILLANCE REQUIREMENTS (Continued) whereF(Z)-F(Z,g,)atg,forwhichF(Z,t)T(E,)F(Z)F(E)isamaximumatRforwhichF(Z,t.)isamaximumT(EE)F(Z)andF(Z)arefunctions ofcoreheight,Z,andcorrespond ateachLF(Z,i)ZtotherodiforwhichT(E)isamaximumatthatZV(Z)isacycledependent functionandisprovidedinthePeakingFactorLimitReport.K(Z)isdefinedinFigure3,2-2forExxonNuclearCompanyfuelandinFigure3.2-3forWestinghouse fuel.T(E)isdefinedinFigures3.2-4and3.2-f.Ep(Z)isanuncertainty factortoaccountforthereduction intheF(E<)curveduetoaccumulation ofexposurepriortothenextfluxmap.WestinhouseFueE(Z)1.0PEp(Z)1.0ExxonNuceaCoueEP(Z)1.0EP(Z)1'0+[.0040xF(Z)]0.0<EE<17.6217.62<ER<34.5E(Z)1.0PEp(Z)10+f0093xP(Z)jEp(Z)-1.0+[.0060xF(Z)jE(Z)1.0P34.5<E<42.242.2<E<48.048.0<E<51.0lD.C.COOK-UNIT13/42-7AMENDMENT NO.s~e~P POWERTIBUIONLIIeLIMITINGCONDITION FOROPERATION (Continued)
'SesttuhouseFuel~NCFuaF-1.0F1.0PF-1.0PF-1.0PFP1.0+[.0015xW]F1~0+[.0033xW]Fp1.0+[.0020 xW]F1.0P0.0gE~<17.6217.62<ER<34.534.5<E<42.242.2<E<48.048.0<E<51.0whereWisthenumberofeffective fullpowerweeks(roundeduptothenexthighestinteger)sincethelastfullcorefluxmap.indicated bytherelationships.*
- "-F(Z,g,)xV(Z)x100%Westinghouse FuelAPLminoverZofF(E)xK(Z)x100$ExxonNuclearCo.FuelLF(Zg)xV(Z)xEp(Z)whereF(Z,g)isthemeasuredF(Z,g,),including a3%manufacturing tolerance uncertainty anda5%m9asurement uncertainty, atthetimeoftargetfluxdetermination fromapowerdistribution mapusingthemovableincoredetectors.
V(Z)isthefunctiongiveninthePeakingFactorLimitReport.Theabovelimitisnotapplicable inthefollowing coreplaneregions.1.Lowercoreregion0%to10%inclusive.
2.Uppercoreregion90%to100%inclusive.
- TheAPDMSmaybeoutofservicewhensurveillance fordetermining powerdistribution mapsisbeingperformed.
D.C.COOK-UNIT13/42-20AMENDMENT NO.
2.22.1(0,2.04)(17.62,2;04) 2.0~-'===-:(34.5,1.95)
-(42.2,1.86)
~1.94CV1.81.7LFQ(ER)LFQ(Ea)LFQ(Ea)0.0<ER<17.62==2.134-.005333 Ep,17.62<Eg,<34.5=2.353-.01169 Ea34.5<Eg,<42.2(48.0,1.82)
(51.0,1.82)1.61.5LF(ER)=2.151-.006897KQF(EI)~182Q42.2<EK<48.048.0<EK<51.01.0~9(0,1.0)(17.62,1.0)~~'~~(34.5,0.956)
.0,0.:(42.2,0.912)
~=(48892).8.7T(Eg,)~1.0T(ER)~1.046-.002614 ERT(Eg,)~1.154-.00573 Eg,T(Eg,)=1.054-003381 Eg,T(Eg,)~0.8920.0(ER17.62<E(34.5<Eg,42.2<EE48.0<Ea<17.62:--=~<34.5'42.2<48.0<51.0.rI'(51.0,0.892',.6II~~tl~~=~~~0102030PeakPelletExposureini&Q/KG4050FIGURE3.2-4ExposureDependent FQLimit,FL(Eg),andNormalized LimitT(ER)asafunctionofPeakPPlletBurnupforExxonNuclearCompanyFue)D.C.COOK-UNIT13/42>>23A,KNDHENT NO.
Attachment 3toAEP:NRC:1018 ANFEvaluation ofLOCAConsiderations
~~<<,'
NQV.f].'Stg1S:4sE78+ONNUCLEARCOMPANY,INC.600100THAVEffVK>C.POSOXS0777.SSU.EVIlK.WA SS009(2N>GO~00November11,1986ENC/AEP-0535 Hr.RickBennett,EngineerNuclearHater1als 5FuelHanagement Ind1ana5HichiganElectricCompanyc/oAmericanElectricPowerServiceCorp.OneRiverside Plaza,20thFloorColumbus, OH43216-6631
DearHr.8ennett:
Attachedisarecommended changetotheD.C.CookUnitlTechnical Specification onFtoallowoperation ofENCfueltopeakpelletexposures ofglGGD)NT.Adustification ofthischangeisalsoattachedforyouruse1nobtaining NRCapprovalforth1schange.Ifyouhaveanyquestions regarding theattachment, pleasecontactourHr.J.S,Holm(telephone 509375-8142).
~Sincerely A'.~H.G.ShawContractAdministrator Attachment cc:H.P.AlexfchJ.H.Cleveland D.H.MalinY.YanderBurg J.S.Holm(ENC)RARlPAPtPAGB/'Pa.,ass,,srgCfgsa0~00sse0stafs0ss
/f40Vli'.8615'47E7P.3.C.CKRef:(1)XN-NF-85-115, Rev.),"D.C.CookUnit1LimitingBreakK(Z)LOCA/ECCS Analysis,"
November1986.(2)XN-NF-85-68(P),
Rev.1,"DonaldC.CookUnit2LimitingBreakLOCA/ECCS
- Analysis, lOXSteamGenerator TubePlugging, andK(Z)Curve,"April1986.(3)XN-NF-85-117, Supp.1)"St.LucieUnit1RevisedLOCA/ECCS Analysiswith15%SteamGenerator TubePlugging8reakSpectrumandExposureResults,"
December1985,ALOCA/ECCS analysisJustifying theoperation ofENCfuelcurrently intheD.C.CookUnit1reactorispresented inReference 1.TheanalysisinthatreportsupportsapeakF~of2.04withanaxialdependence asshowninFigure1.Thisanalysisisapplicable totheENCfuelcurrently intheD.C.CookUnit1reactor,withaminimumpeakrodaverageexposuregreaterthan20GWd/HTandanticipated tobelessthan47GWd/HT.Justification foranexposuredependent F~forD.C.CookUnit1isbasedonanexposureanalysisforD.C.CookUnit2(Reference 2).Peakcladdingtemperatures aredependent uponfuelrodinitialstoredenergy,whichfortheEXEH/PMRmodelsincreases from0toabout2GWd/HTHandthendecreases withexposure.
TheanalysisforD.C,CookUnit2with17x17fuelgeometrydemonstrated thatovertheexposurerangeof0to41GMd/HTH,thepeakcladdingtemperature decreased withexposureforexposures beyondthepeakstoredenergyexposure.
AsimilartrendwasobservedforSt,LucieUnit1with15x15fuelgeometry(Reference 3).SimilarresultswouldbeexpectedforD.C.CookUnit1with15x15fuelgeometryusingEXEH/PWRmodelsBasedonthetrendofdecreasing peakcladdingtemperature withincreasing
- exposure, theanalysisinReference 1isconservative andsupportsanFofatleast1.95forENCfuelatpeakrodaverageexposures between20anII47GMd/HTH,Apeakrodaverageexposureof47GMd/HTHisequivalent toapeakpelletexposureof51GWd/HTH.Therecommended D.C.CookUnit1exposuredependent FTechnical Specification Figure3.2-4isattached.
ThisfigureisthetameasthefigureinthecurrentD.C.CookUnit1Technical Specification bu'iththeadditionofaconstantFlimitof1.82from48.0GWd/HTto51GWd/HTpeakpelletexposure, Forc3)nsistency withthecurrentD.C.CookUnit1Technical Specification, thecurvehasbeenmaintained intermsofpeakpelletburnvp,HAPlFAXNO'PAGEAT'TN.
I.21.D(6.0,1.0)DO0f2345I780,18ki12COREHEIGHTCFT>P~OFigure1IhtChannelFactorNormalized Operating
- Envelope, Fq=2.04,K{Z)Function 2.2Z.l2.0(0,2.04)(,17.62,2.04)
(34.5,1.95) 1,9(42.2,1.86) 1.71.61.5Ft(EE)"2.04Fq(Ea)=2,134-.005333 Eg,F)(ER)~2.353-.01159 55Fq(Ek)=2.151-.006897 EaLFq(ER)=1.82L0.0<E9.<17.617.62<EK<34.534.5<ER<42,242.2<,Eg,<48.048,0<Ea<51.0(48.0,1.82)
(51.0,1,82 1,0(17.62,1.0)(34,5,.956)(42.2,.912)(48.0,.892)(51.0,.89.8.7T{Ea)-1.00.0<Eg<17.62T{Eg,)=1.046-.002614 Eg,17.62<ER<34.5T(EI()1,154-,00573 ER34.5<EIl,<<42,2T(Eg)~1,054-.003381 Q,42.2<Eg.<48.0TEg,)0.89248.0<EE<51.01020PeakPelletExposurein%ID/KG405060Figure3.2-4ExposureOependent FqLimit,Fq(Ea),andNormalized Limit~LT(ER)asafunctionofPeakPellet8urnupforExxonNuclearCo..panyF.e1O.C.Cook-Unit13/42-23Amendment No.RAPIFAXATTIL4 AFFIDAVIT*STATEOFWASHINGTON
)ss.COUNTYOFBENTON)I,H.E.Williamson beingdulysworn,herebysayanddepose:l.IamManager,Licensing andSafetyEngineering, forAdvancedNuclearFuelsCorporation
("ANF"),andassuchIamauthorized toexecutethisAffidavit.
2.IamfamiliarwithANF'sdetaileddocumentcontrolsystemandpolicieswhichgoverntheprotection andcontrolofinformation.
3.IamfamiliarwiththeLetterHGS-87-55(P) entitled"DCCookUnitIPeakPelletBurnupExtension" referredtoas"Document."
Information contained inthisDocumenthasbeenclassified byANFasproprietary inaccordance withthecontrolsystemandpoliciesestablished CbyANFforthecontrolandprotection ofinformation.
4.Thedocumentcontainsinformation ofaproprietary andconfidential naturean'disofthetypecustomarily heldinconfidence byANFandnotmadeavailable tothepublic.Basedonmyexperience, Iamawarethatothercompanies regardinformation ofthekindcontained intheDocumentasproprietary andconfidential, 5.*TheDocumenthasbeenmadeavailable totheU.S.NuclearRegulatory Commission inconfidence, withtherequestthattheinformation contained intheDocumentwillnotbedisclosed ordivulged.
6.TheDocumentcontainsinformation whichisvitaltoacompetitive advantage ofANFandwouldbehelpfultocompetitors ofANFwhencompeting withANF.7.Theinformation contained intheDocumentisconsidered tobeproprietary byANFbecauseitrevealscertaindistinguishing aspectsofPWRFuelDesignmethodology whichsecurecompetitive advantage toANFforfueldesignoptimization andmarketability, andincludesinformation utilizedbyANFinitsbusinesswhichaffordsANFanopportunity toobtainacompetitive advantage overitscompetitors whodonotormaynotknoworusetheinformation contained intheDocument.
8.Thedisclosure oftheproprietary information contained intheDocumenttoacompetitor wouldpermitthecompetitor toreduceitsexpenditure ofmoneyandmanpowerandtoimproveitscompetitive positionbygivingitextremely valuableinsightsintoPWRFuelDesignmethodology andwouldresultinsubstantial harmtothecompetitive positionofANF.9.TheDocumentcontainsproprietary information whichisheldinconfidence byANFandisnotavailable inpublicsources.10.Inaccordance withANF'spoliciesgoverning theprotection andcontrolofinformation, proprietary information contained intheDocumenthasbeenmadeavailable, onalimitedbasis,toothersoutsideANFonlyasrequiredandundersuitableagreement providing fornon-disclosure andlimiteduseoftheinformation.
11.ANFpolicyrequiresthatproprietary information bekeptinasecuredfileorareaanddistributed onaneed-to-know basis.
12.ThisDocumentprovidesinformation whichrevealsPWRFuelDesignmethodology developed byANFoverthepastseveralyears.ANFhasinvestedthousands ofdollarsandseveralman-months ofeffortindeveloping thePWRFuelDesignmethodology revealedintheDocument.
Assumingacompetitor hadavailable thesamebackground dataandincentives asANF,thecompetitor might,ataminimum,developtheIinformation forthesameexpenditure ofmanpowerandmoneyasANF.THATthestatements madehereinabove are,tothebestofmyknowledge, information, andbelief,truthfulandcomplete.
FURTHERAFFIANTSAYETHNOT.SWORNTOANDSUBSCRIBED beforemethis~d~dayof198.NOfARYPUBLIC y~
Attachment 5toAEP:NRC:1018 ANFEvaluation (Non-Proprietary) ofMechanical DesignConsiderations forPeakPelletExposures upto48.7Mwd/kg x*NON-PROPRIETARY x*HGS-87-055 (P),Attachment 2Page1of2DCCookUnit1-PeakPelletBurnuExtension BBackBround:ThelastreloadofANF(formerly ENC)fuelsuppliedfortheDCCookUnit1reactoriscurrently initslastcycleofoperation.
Aburnupextension analysishadbeenperformed forthisfuelin1984inordertosupportburnuplevelsof41.0,43.7,and48.0GWD/MtUrespectively forpeakassembly, peakrod,andpeakpellet.Reactoroperating conditions sincethattimehaveresultedinhigheraxialpeakingthanoriginally projected.
Consequently, thepeakpelletburnupisnowexpectedtoapproachalevelof48.5GWD/MtU.Thepeakrodandpeakassemblyburnuplevelsarenotaffected.
Areviewoftheoriginalanalysessupporting theburnupextension hasbeenconducted inordertodetermine theconsequences ofanincreaseinpeakpelletexposure.
Thereviewconsidered anadditional increaseinpeakpelletexposureto48.7GWD/MtUtoprovidemarginfor.apotential endofcyclecoastdown.
Summar.ofBurnuExtension AnalysisReview:Theoriginalburnupextension analysi,s, reportedinXN-NF-84-25, Rev.0(Reference 1),addressed thefollowing aspectsofdesign:(1)SteadyStateStress,(2)SteadyStateStrain,(3)CladdingCorrosion andHydrogenAbsorption, (4)Transient StressandStrainandCladdingFatigue,(5)CladdingCreepCollapse, (6)FuelRodInternalGasPressure, (7)FuelRodGrowth.(8)SpacerSpringForce,and(9)FuelAssemblyGrowth.Ofthese,onlySteadyStateStrain,Corrosion andHydrogenAbsorption, andFuelRodInternalPressurearesignificantly affectedbytheaxialprofileofthefuelrod.Theremainder oftheitemsareessentially independent ofthepeakpelletexposure.
TheresultsreportedinXN-NF-84-25, Rev.0remainvalidfortheseitems.Thepowerhistoryusedfor.theoriginalburnupextension analysiswasbasedonaconservative best-estimate ofthemaximumdischarge exposurerod,assumingfullpoweroperation.
Inrealitytheoperation ofthereactorhasbeenlimitedto90percentoffullpower.Therefore, theoriginalpower.historyprojection represents aboundingcasefor.thisfuel.Therevisedanalysisshowsthatcladstrain,corrosion andhydrogenabsorption remainwithinthedesignlimits,andthefuelrodpressureremainsbelowsystempressure.
'krNON-PROPRIETARY x+HGS-87-055 (P),Attachment 2Page2of2SteadStateStrain,CladdinCorrosion andHdroenAbsortion:Themaximumcladdingstrain,corrosion andhydrogenabsorption weredetermined tooccuratthepeakaxialregionintheoriginalburnupextension analysis.
Reviewofthisanalysisshowedtheresultsfromthepreviousanalysistohavebeentakenfor.apeakpelletexposureof48.3GWD/MtU.Becauseofthesubstantial marginforthesedesigncriteriaasimpleextrapolation wasusedtoprojecttheconditions forapeakpelletexposureof48.7GWD/MtU.Extrapolating theresultsoftheoriginalanalysisandincluding anuncertainty offivepercentyieldsthefollowing results:~Pr'o'ctedCriteriaTotalPositiveStrain,(0)MaximumPositiveStrainIncrease, (8)CladdingCorrosion, (inch)HydrogenAbsorption, (ppm)Therefore.
thefuelwillremainwellwithinthecriteriafortheseitems.FuelRodInternalPressure:
AnewRODEX2.(Reference 2)analysiswasperformed
.usingtheapprovedmethodology for'nternal gaspressuredetermination andtheboundingpower,history.Theaxialpeakingfactorfromtheoriginalextension analysiswasincreased by2'8atthemaximumaxialregioninordertoboundthe1.5%increaseinhurnupfrom48.0to48.7GWD/MtU.Theresultsofthisanalysisshowedapealeinternalpressureof(]psiaoverthedesignlifeofthefuel.Thisvalueiswellwithinthecriterialimitofthe2250psiareactoroperating pressureasgiveninXN-NF-84-25, Rev.0.Conclusion:
ReviewoftheanalysisfortheANFfuelsuppliedtotheDCCookUnit1reactorhasshownthefuelcapableofmeetinga11designcriteriaatapeakpelletexposureof48.7GWD/MtU.Theresultspresented intheextendedburnupreportXN-NF-84-25.
Rev.0withtheadditionoftheresultspresented inthisletterremainvalidforthefuel.Ref:(1)XN-iVF-84-25.
Revision0,Mechanical Desi.nReortSulement.forDCCookUnit1ExtendedBurnuFuelAssemblies, April1984.4(2)XN-NF-81-58
{P)(A)~Revision2.RODEX2FuelRodThermal-Mechanical ResonseEvaluation Model,March1984.