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| {{#Wiki_filter:ATTACHMENT ARevisetheTechnical Specification pagesasfollows:Remove5.3-1Insert5.3-19003270K05P00204890031>popADOCKpnr-.=-P 5.35.3.1ReactorDesiFeaturesReactorCorea.Thereactorcorecontainsapproximately 45metrictonsofuraniumintheformofuraniumdioxidepellets.Thepelletsareencapsul'ated inZircaloy4tubingtoformfuelrods.Thereactorcoreismadeupof121fuelassemblies"'ith eachfuelassemblycontaining 179fuelrodlocations. | | {{#Wiki_filter:ATTACHMENT A Revise the Technical Specification pages as follows: Remove 5.3-1 Insert 5.3-1 9003270 K 05P002 048 90031>pop ADOCK pnr-.=-P 5.3 5.3.1 Reactor Desi Features Reactor Core a.The reactor core contains approximately 45 metric tons of uranium in the form of uranium dioxide pellets.The pellets are encapsul'ated in Zircaloy 4 tubing to form fuel rods.The reactor core is made up of 121 fuel assemblies"'ith each fuel assembly containing 179 fuel rod locations. |
| Fuelrodlocations atanytimeduringplantlife,mayconsistoffuelrodscladwithZircaloy-4orfillerrodsfabricated fromZircaloy-4orstainless steelifjustified bycycle-specific reloadanalysis.
| | Fuel rod locations at any time during plant life, may consist of fuel rods clad with Zircaloy-4 or filler rods fabricated from Zircaloy-4 or stainless steel if justified by cycle-specific reload analysis.Should more than 30, rods in the core, or 10 rods in any assembly be replaced per refueling, a report describing the number of rods replaced and associated cycle-specific evaluation shall be submitted to the Commission prior to criticality. |
| Shouldmorethan30,rodsinthecore,or10rodsinanyassemblybereplacedperrefueling, areportdescribing thenumberofrodsreplacedandassociated cycle-specific evaluation shallbesubmitted totheCommission priortocriticality.
| | Each fuel assembly also contains 16 guide tubes and one instrumentation thimble all arranged in a 14 x 14 array to form a fuel assembly.b.The enrichment of reload fuel shall be no more than 3.5 weight per cent U-235 for regions delivered prior to January 1, 1984 (Regions 1-15), 4.25 weight per cent U-235 for regions delivered after January 1, 1984, or their equivalents in terms of reactivity. |
| Eachfuelassemblyalsocontains16guidetubesandoneinstrumentation thimbleallarrangedina14x14arraytoformafuelassembly.
| | c.There are 29 full-length assemblies in the reactor core.Each RCC assembly contains 16 144 inch lengths of silver-indium-cadmium alloy clad with stainless steel which act as neutron absorbers when inserted into the core."'asis The DNBRs for the reconstituted assemblies are conservatively determined by assuming the filler rods are operating at the highest power in the reconstituted fuel assembly.5.3-1 Proposed Rochester Gas and Electric (RG&E)desires the flexibility to reconstitute fuel assemblies in order to reduce coolant activity and utilize the remaining energy in fuel assemblies which contain small numbers of defective fuel rods.In the reconstitution process, the fuel rods which are known to be defective will be removed and replaced with dummy rods (Zircaloy or stainless steel).This reconstitution will be accomplished by either removing the top nozzle or by removing the bottom nozzle after inverting the assembly, inspecting and removing the defective rods, replacing the failed rods with dummy rods and reattaching the nozzle.If a fuel assembly skeleton is damaged, serviceable fuel rods and dummy rods may be transferred to a new skeleton.Fuel and dummy rod insertion and nozzle removal/reattachment remain the same as in the reconstitution process previously discussed. |
| b.Theenrichment ofreloadfuelshallbenomorethan3.5weightpercentU-235forregionsdelivered priortoJanuary1,1984(Regions1-15),4.25weightpercentU-235forregionsdelivered afterJanuary1,1984,ortheirequivalents intermsofreactivity. | | The reconstituted assembly will meet the original assembly design criteria.The R.E.Ginna Nuclear Power Plant"Technical Specification 5.3.1.a describes the reactor core as consisting of assemblies containing 179 fuel rods.In order to allow for the insertion of reconstituted assemblies with dummy rods, this statement must be modified as proposed in Attachment A.The use of reconstituted fuel assemblies in a reload core is considered acceptable because each reload that contains reconstituted assemblies will be evaluated using standard methods as described in Reference 1.The reload analysis will evaluate the effect of the actual reconstitution on core performance parameters, peaking factors, core average linear heat rate effects, and for the effect of the reconstitution on the LOCA-related analyses to ensure the existing safety criteria and design limits are met.In addition, reconstituted assemblies will meet the original assembly design criteria.The report requirement of 30 and 10 is arbitrarily chosen as a value above which the cycle-specific evaluation will be submitted to the Staff.In accordance with 10CFR50.91, these changes to the Technical Specifications have been evaluated to determine if the operation of the facility in accordance with the proposed, Amendment would: 1.involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.involve a significant reduction in the margin of safety.The reconstituted fuel assemblies meet the same design requirements and satisfy the same design criteria as the original fuel assemblies. |
| c.Thereare29full-length assemblies inthereactorcore.EachRCCassemblycontains16144inchlengthsofsilver-indium-cadmium alloycladwithstainless steelwhichactasneutronabsorbers wheninsertedintothecore."'asis TheDNBRsforthereconstituted assemblies areconservatively determined byassumingthefillerrodsareoperating atthehighestpowerinthereconstituted fuelassembly. | | Cycle specific reload evaluations will apply existing safety criteria and design limits.Therefore use of reconstituted fuel assemblies does not involve a significant increase in.the probability or consequences of an accident previously evaluated.. |
| 5.3-1Proposed Rochester GasandElectric(RG&E)desirestheflexibility toreconstitute fuelassemblies inordertoreducecoolantactivityandutilizetheremaining energyinfuelassemblies whichcontainsmallnumbersofdefective fuelrods.Inthereconstitution process,thefuelrodswhichareknowntobedefective willberemovedandreplacedwithdummyrods(Zircaloy orstainless steel).Thisreconstitution willbeaccomplished byeitherremovingthetopnozzleorbyremovingthebottomnozzleafterinverting theassembly, inspecting andremovingthedefective rods,replacing thefailedrodswithdummyrodsandreattaching thenozzle.Ifafuelassemblyskeletonisdamaged,serviceable fuelrodsanddummyrodsmaybetransferred toanewskeleton. | | 4 I~%The reconstituted fuel assemblies satisfy the original design criteria and the reload in which the fuel assemblies are used is~evaluated to ensure existing safety criteria and design limits are met.Therefore, the possibility of a new or different kind of accident is not created by the use of reconstituted fuel.The required cycle specific reload analysis will ensure existing safety criteria and'esign limits are met.This will ensure there is no reduction in a margin of safety.Based on the above discussions, Rochester Gas and Electric submits that the issues associated with this Amendment request are outside the criteria of 10CPR50.91 and a no significant hazards finding is warranted. |
| Fuelanddummyrodinsertion andnozzleremoval/reattachment remainthesameasinthereconstitution processpreviously discussed.
| | Reference 1.WCAP-9273A"Westinghouse Reload Safety Evaluation Methodology", July 1985 B-2 |
| Thereconstituted assemblywillmeettheoriginalassemblydesigncriteria.
| | ~~'TABLE 1 DETAILED TECHNICAL SPECIFICATION CHANGES Location Descri tion of Chan e Reason for Chan e Page 5.3-1"...may consist of fuel rods clad with Zircaloy-4 or filler rods fabricated from Zircaloy-4 or stainless steel if justified by cycle-specific reload analysis.Should more than 30 rods in the core, or 10 rods in any assembly be replaced per refueling, a report describing the number of rods replaced and associated cycle-specific evaluation shall be submitted to the Commission prior to criticality." Allow use of reconstituted fuel.Replaced"are" with"all" Deleted"The reactor core is made up of 121 fuel fuel assemblies.""'ording Used in the above insertion. |
| TheR.E.GinnaNuclearPowerPlant"Technical Specification 5.3.1.adescribes thereactorcoreasconsisting ofassemblies containing 179fuelrods.Inordertoallowfortheinsertion ofreconstituted assemblies withdummyrods,thisstatement mustbemodifiedasproposedinAttachment A.Theuseofreconstituted fuelassemblies inareloadcoreisconsidered acceptable becauseeachreloadthatcontainsreconstituted assemblies willbeevaluated usingstandardmethodsasdescribed inReference 1.Thereloadanalysiswillevaluatetheeffectoftheactualreconstitution oncoreperformance parameters, peakingfactors,coreaveragelinearheatrateeffects,andfortheeffectofthereconstitution ontheLOCA-related analysestoensuretheexistingsafetycriteriaanddesignlimitsaremet.Inaddition, reconstituted assemblies willmeettheoriginalassemblydesigncriteria.
| | Added, Basis: "The DNBRs for the reconstituted assemblies are conservatively determined by assuming the filler rods are operating at the highest power in the reconstituted fuel assembly." Requested by NRC Reviewer |
| Thereportrequirement of30and10isarbitrarily chosenasavalueabovewhichthecycle-specific evaluation willbesubmitted totheStaff.Inaccordance with10CFR50.91, thesechangestotheTechnical Specifications havebeenevaluated todetermine iftheoperation ofthefacilityinaccordance withtheproposed, Amendment would:1.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3.involveasignificant reduction inthemarginofsafety.Thereconstituted fuelassemblies meetthesamedesignrequirements andsatisfythesamedesigncriteriaastheoriginalfuelassemblies.
| | ~~i>4 m V 1}} |
| Cyclespecificreloadevaluations willapplyexistingsafetycriteriaanddesignlimits.Therefore useofreconstituted fuelassemblies doesnotinvolveasignificant increasein.theprobability orconsequences ofanaccidentpreviously evaluated..
| |
| 4I~%Thereconstituted fuelassemblies satisfytheoriginaldesigncriteriaandthereloadinwhichthefuelassemblies areusedis~evaluated toensureexistingsafetycriteriaanddesignlimitsaremet.Therefore, thepossibility ofanewordifferent kindofaccidentisnotcreatedbytheuseofreconstituted fuel.Therequiredcyclespecificreloadanalysiswillensureexistingsafetycriteriaand'esign limitsaremet.Thiswillensurethereisnoreduction inamarginofsafety.Basedontheabovediscussions, Rochester GasandElectricsubmitsthattheissuesassociated withthisAmendment requestareoutsidethecriteriaof10CPR50.91 andanosignificant hazardsfindingiswarranted.
| |
| Reference 1.WCAP-9273A "Westinghouse ReloadSafetyEvaluation Methodology", | |
| July1985B-2
| |
| ~~'TABLE1DETAILEDTECHNICAL SPECIFICATION CHANGESLocationDescritionofChaneReasonforChanePage5.3-1"...mayconsistoffuelrodscladwithZircaloy-4orfillerrodsfabricated fromZircaloy-4orstainless steelifjustified bycycle-specific reloadanalysis. | |
| Shouldmorethan30rodsinthecore,or10rodsinanyassemblybereplacedperrefueling, areportdescribing thenumberofrodsreplacedandassociated cycle-specificevaluation shallbesubmitted totheCommission priortocriticality."
| |
| Allowuseofreconstituted fuel.Replaced"are"with"all"Deleted"Thereactorcoreismadeupof121fuelfuelassemblies.""'ording Usedintheaboveinsertion.
| |
| Added,Basis:"TheDNBRsforthereconstituted assemblies areconservatively determined byassumingthefillerrodsareoperating atthehighestpowerinthereconstituted fuelassembly." | |
| Requested byNRCReviewer | |
| ~~i>4mV1}} | |
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Text
ATTACHMENT A Revise the Technical Specification pages as follows: Remove 5.3-1 Insert 5.3-1 9003270 K 05P002 048 90031>pop ADOCK pnr-.=-P 5.3 5.3.1 Reactor Desi Features Reactor Core a.The reactor core contains approximately 45 metric tons of uranium in the form of uranium dioxide pellets.The pellets are encapsul'ated in Zircaloy 4 tubing to form fuel rods.The reactor core is made up of 121 fuel assemblies"'ith each fuel assembly containing 179 fuel rod locations.
Fuel rod locations at any time during plant life, may consist of fuel rods clad with Zircaloy-4 or filler rods fabricated from Zircaloy-4 or stainless steel if justified by cycle-specific reload analysis.Should more than 30, rods in the core, or 10 rods in any assembly be replaced per refueling, a report describing the number of rods replaced and associated cycle-specific evaluation shall be submitted to the Commission prior to criticality.
Each fuel assembly also contains 16 guide tubes and one instrumentation thimble all arranged in a 14 x 14 array to form a fuel assembly.b.The enrichment of reload fuel shall be no more than 3.5 weight per cent U-235 for regions delivered prior to January 1, 1984 (Regions 1-15), 4.25 weight per cent U-235 for regions delivered after January 1, 1984, or their equivalents in terms of reactivity.
c.There are 29 full-length assemblies in the reactor core.Each RCC assembly contains 16 144 inch lengths of silver-indium-cadmium alloy clad with stainless steel which act as neutron absorbers when inserted into the core."'asis The DNBRs for the reconstituted assemblies are conservatively determined by assuming the filler rods are operating at the highest power in the reconstituted fuel assembly.5.3-1 Proposed Rochester Gas and Electric (RG&E)desires the flexibility to reconstitute fuel assemblies in order to reduce coolant activity and utilize the remaining energy in fuel assemblies which contain small numbers of defective fuel rods.In the reconstitution process, the fuel rods which are known to be defective will be removed and replaced with dummy rods (Zircaloy or stainless steel).This reconstitution will be accomplished by either removing the top nozzle or by removing the bottom nozzle after inverting the assembly, inspecting and removing the defective rods, replacing the failed rods with dummy rods and reattaching the nozzle.If a fuel assembly skeleton is damaged, serviceable fuel rods and dummy rods may be transferred to a new skeleton.Fuel and dummy rod insertion and nozzle removal/reattachment remain the same as in the reconstitution process previously discussed.
The reconstituted assembly will meet the original assembly design criteria.The R.E.Ginna Nuclear Power Plant"Technical Specification 5.3.1.a describes the reactor core as consisting of assemblies containing 179 fuel rods.In order to allow for the insertion of reconstituted assemblies with dummy rods, this statement must be modified as proposed in Attachment A.The use of reconstituted fuel assemblies in a reload core is considered acceptable because each reload that contains reconstituted assemblies will be evaluated using standard methods as described in Reference 1.The reload analysis will evaluate the effect of the actual reconstitution on core performance parameters, peaking factors, core average linear heat rate effects, and for the effect of the reconstitution on the LOCA-related analyses to ensure the existing safety criteria and design limits are met.In addition, reconstituted assemblies will meet the original assembly design criteria.The report requirement of 30 and 10 is arbitrarily chosen as a value above which the cycle-specific evaluation will be submitted to the Staff.In accordance with 10CFR50.91, these changes to the Technical Specifications have been evaluated to determine if the operation of the facility in accordance with the proposed, Amendment would: 1.involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.create the possibility of a new or different kind of accident from any accident previously evaluated; or 3.involve a significant reduction in the margin of safety.The reconstituted fuel assemblies meet the same design requirements and satisfy the same design criteria as the original fuel assemblies.
Cycle specific reload evaluations will apply existing safety criteria and design limits.Therefore use of reconstituted fuel assemblies does not involve a significant increase in.the probability or consequences of an accident previously evaluated..
4 I~%The reconstituted fuel assemblies satisfy the original design criteria and the reload in which the fuel assemblies are used is~evaluated to ensure existing safety criteria and design limits are met.Therefore, the possibility of a new or different kind of accident is not created by the use of reconstituted fuel.The required cycle specific reload analysis will ensure existing safety criteria and'esign limits are met.This will ensure there is no reduction in a margin of safety.Based on the above discussions, Rochester Gas and Electric submits that the issues associated with this Amendment request are outside the criteria of 10CPR50.91 and a no significant hazards finding is warranted.
Reference 1.WCAP-9273A"Westinghouse Reload Safety Evaluation Methodology", July 1985 B-2
~~'TABLE 1 DETAILED TECHNICAL SPECIFICATION CHANGES Location Descri tion of Chan e Reason for Chan e Page 5.3-1"...may consist of fuel rods clad with Zircaloy-4 or filler rods fabricated from Zircaloy-4 or stainless steel if justified by cycle-specific reload analysis.Should more than 30 rods in the core, or 10 rods in any assembly be replaced per refueling, a report describing the number of rods replaced and associated cycle-specific evaluation shall be submitted to the Commission prior to criticality." Allow use of reconstituted fuel.Replaced"are" with"all" Deleted"The reactor core is made up of 121 fuel fuel assemblies.""'ording Used in the above insertion.
Added, Basis: "The DNBRs for the reconstituted assemblies are conservatively determined by assuming the filler rods are operating at the highest power in the reconstituted fuel assembly." Requested by NRC Reviewer
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