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| {{#Wiki_filter:Attachment A1.RevisetheTechnical Specifications byremovingexistingpages2.1-3and2.1-4andinserting theenclosedpage2.1-3.84070500PP44188407i7POP>DOCKpDpPI lit'tt!tlttltt-'t'r Sinceitispossibletohavesomewhatgreaterenthalpyrisehotchannelfactorsatpartpowerthanatfullpowerduetothedeepercontrolbankinsertion whichispermitted atpartpower,aconservative allowance hasbeenmadeinobtaining thecurvesinFigure2.1-1foranincreaseinFIHwithdecreasing powerlevels.Rodwithdrawal blockandloadrunbackoccursbeforereactortripsetpointsarereached.TheReactorControlandProtective Systemisdesignedtopreventanyanticipated combination oftransient conditions forreactorcoolantsystemtemperature, pressureandthermalpowerlevelthatwouldresultintherebeinglessthana95%probability ata95%confidence levelthatDNBwouldnotoccur.(2)(1)FSAR,Section3.2.2(2)SafetyEvaluation forR.E.GinnaTransition to14x14Optimized FuelAssemblies, Westinghouse ElectricCorporation, November1983.2.1-3ftleJ'mendment No.March30,1976PROPOSED C~4Attachment BInpreparation oftheproposedTechnical Specification relatedtotheuseofWestinghouse Optimized FuelasareloadfuelforGinna,whichwassubmitted onDecember20,1983,itwasintendedthattheinformation presented inTechnical Specification page2.1-3bedeleted.Thisinformation, theidentification ofnuclearhotchannelfactorswhichformedthebasisfortheprevioussafetylimitcurves,wasnolongercorrectandthecorrectbasiswasidentified ontheproposedpagechanges.Weunderstand thatbecausethisportionofthechangewasnotexplicitly identified inoursubmittal, theNRCdidnotapprovethischangeinitsissuanceofAmendment No.61datedMay1,1984.Theproposedchangeremediesthisinconsistency bydeletingtheincorrect information. | | {{#Wiki_filter:Attachment A 1.Revise the Technical Specifications by removing existing pages 2.1-3 and 2.1-4 and inserting the enclosed page 2.1-3.8407 0500PP44 18 8407i7 POP>DOCK pDp P I li t't t!tl t tl tt-'t'r Since it is possible to have somewhat greater enthalpy rise hot channel factors at part power than at full power due to the deeper control bank insertion which is permitted at part power, a conservative allowance has been made in obtaining the curves in Figure 2.1-1 for an increase in FIH with decreasing power levels.Rod withdrawal block and load runback occurs before reactor trip set points are reached.The Reactor Control and Protective System is designed to prevent any anticipated combination of transient conditions for reactor coolant system temperature, pressure and thermal power level that would result in there being less than a 95%probability at a 95%confidence level that DNB would not occur.(2)(1)FSAR, Section 3.2.2 (2)Safety Evaluation for R.E.Ginna Transition to 14 x 14 Optimized Fuel Assemblies, Westinghouse Electric Corporation, November 1983.2.1-3 f tl e J'mendment No.March 30, 1976 PROPOSED C~4 Attachment B In preparation of the proposed Technical Specification related to the use of Westinghouse Optimized Fuel as a reload fuel for Ginna, which was submitted on December 20, 1983, it was intended that the information presented in Technical Specification page 2.1-3 be deleted.This information, the identification of nuclear hot channel factors which formed the basis for the previous safety limit curves, was no longer correct and the correct basis was identified on the proposed page changes.We understand that because this portion of the change was not explicitly identified in our submittal, the NRC did not approve this change in its issuance of Amendment No.61 dated May 1, 1984.The proposed change remedies this inconsistency by deleting the incorrect information. |
| Inaddition, foradditional clarifi-cation,arevisedreference totheoptimized fuelanalysis, isprovided.
| | In addition, for additional clarifi-cation, a revised reference to the optimized fuel analysis, is provided.The proposed change merely corrects an administrative inconsistency in the basis.It does not revise any existing limits but is based on previously approved analyses., I'I Ih Jh 44 4 hl I'4 l L C~1 f.I b AI II 1 t Attachment C In accordance with 10 CFR 50.91, this change to the Technical Specifications has been evaluated against three criteria 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 a margin of safety.As outlined below, Rochester Gas and Electric submits that the issues associated with this amendment request are outside the criteria of 10 CFR 50.91, and therefore, a no significant hazards finding is warranted. |
| Theproposedchangemerelycorrectsanadministrative inconsistency inthebasis.Itdoesnotreviseanyexistinglimitsbutisbasedonpreviously approvedanalyses.,
| | The changes are all administrative in nature.Amendment No.61 approved use of Westinghouse'ptimized fuel based on the, analysis and proposed Technical'pecifications which were sub-" mitted.We understand that'ecause this portion: of the'hange was'ot explicitly identified in our submittal, the NRC did not approve this change in its'issuance of Amendment No.61 dated May 1, 1984.The proposed change remedies this inconsistency by deleting the incorrect information. |
| I'IIhJh444hlI'4lL C~1f.IbAIII1t Attachment CInaccordance with10CFR50.91,thischangetotheTechnical Specifications hasbeenevaluated againstthreecriteriatodetermine iftheoperation ofthefacilityinaccordance withtheproposedamendment would:1.involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or3.involveasignificant reduction inamarginofsafety.Asoutlinedbelow,Rochester GasandElectricsubmitsthattheissuesassociated withthisamendment requestareoutsidethecriteriaof10CFR50.91,andtherefore, anosignificant hazardsfindingiswarranted. | | In addition, for additional clarifi-cation, a revised reference to the optimized fuel analysis, is provided.The proposed change merely corrects an administrative inconsistency in the basis.It does not revise any existing limits but is based on previously approved analyses.The proposed changes are conformed to the Commission's example (i)of changes that do not involve a significant hazards consideration. |
| Thechangesarealladministrative innature.Amendment No.61approveduseofWestinghouse'ptimized fuelbasedonthe,analysisandproposedTechnical'pecifications whichweresub-"mitted.Weunderstand that'ecause thisportion:ofthe'hange was'otexplicitly identified inoursubmittal, theNRCdidnotapprovethischangeinits'issuance ofAmendment No.61datedMay1,1984.Theproposedchangeremediesthisinconsistency bydeletingtheincorrect information.
| | 4~S 4 T t~kh t tf t IL lt P J k}} |
| Inaddition, foradditional clarifi-cation,arevisedreference totheoptimized fuelanalysis, isprovided.
| |
| Theproposedchangemerelycorrectsanadministrative inconsistency inthebasis.Itdoesnotreviseanyexistinglimitsbutisbasedonpreviously approvedanalyses.
| |
| Theproposedchangesareconformed totheCommission's example(i)ofchangesthatdonotinvolveasignificant hazardsconsideration.
| |
| 4~S4Tt~khttftILltPJk}} | |
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[Table view] |
Text
Attachment A 1.Revise the Technical Specifications by removing existing pages 2.1-3 and 2.1-4 and inserting the enclosed page 2.1-3.8407 0500PP44 18 8407i7 POP>DOCK pDp P I li t't t!tl t tl tt-'t'r Since it is possible to have somewhat greater enthalpy rise hot channel factors at part power than at full power due to the deeper control bank insertion which is permitted at part power, a conservative allowance has been made in obtaining the curves in Figure 2.1-1 for an increase in FIH with decreasing power levels.Rod withdrawal block and load runback occurs before reactor trip set points are reached.The Reactor Control and Protective System is designed to prevent any anticipated combination of transient conditions for reactor coolant system temperature, pressure and thermal power level that would result in there being less than a 95%probability at a 95%confidence level that DNB would not occur.(2)(1)FSAR, Section 3.2.2 (2)Safety Evaluation for R.E.Ginna Transition to 14 x 14 Optimized Fuel Assemblies, Westinghouse Electric Corporation, November 1983.2.1-3 f tl e J'mendment No.March 30, 1976 PROPOSED C~4 Attachment B In preparation of the proposed Technical Specification related to the use of Westinghouse Optimized Fuel as a reload fuel for Ginna, which was submitted on December 20, 1983, it was intended that the information presented in Technical Specification page 2.1-3 be deleted.This information, the identification of nuclear hot channel factors which formed the basis for the previous safety limit curves, was no longer correct and the correct basis was identified on the proposed page changes.We understand that because this portion of the change was not explicitly identified in our submittal, the NRC did not approve this change in its issuance of Amendment No.61 dated May 1, 1984.The proposed change remedies this inconsistency by deleting the incorrect information.
In addition, for additional clarifi-cation, a revised reference to the optimized fuel analysis, is provided.The proposed change merely corrects an administrative inconsistency in the basis.It does not revise any existing limits but is based on previously approved analyses., I'I Ih Jh 44 4 hl I'4 l L C~1 f.I b AI II 1 t Attachment C In accordance with 10 CFR 50.91, this change to the Technical Specifications has been evaluated against three criteria 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 a margin of safety.As outlined below, Rochester Gas and Electric submits that the issues associated with this amendment request are outside the criteria of 10 CFR 50.91, and therefore, a no significant hazards finding is warranted.
The changes are all administrative in nature.Amendment No.61 approved use of Westinghouse'ptimized fuel based on the, analysis and proposed Technical'pecifications which were sub-" mitted.We understand that'ecause this portion: of the'hange was'ot explicitly identified in our submittal, the NRC did not approve this change in its'issuance of Amendment No.61 dated May 1, 1984.The proposed change remedies this inconsistency by deleting the incorrect information.
In addition, for additional clarifi-cation, a revised reference to the optimized fuel analysis, is provided.The proposed change merely corrects an administrative inconsistency in the basis.It does not revise any existing limits but is based on previously approved analyses.The proposed changes are conformed to the Commission's example (i)of changes that do not involve a significant hazards consideration.
4~S 4 T t~kh t tf t IL lt P J k
