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| | issue date = 08/19/1997 | | | issue date = 08/19/1997 |
| | title = Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values | | | title = Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 7 | | | page count = 7 |
| | | project = |
| | | stage = Request |
| }} | | }} |
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| {{#Wiki_filter:UNITEDSTATESOFAlVKRICANUCLEARREGULATORYCOMMSSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATIONFORAMENDMENTTPERATLIEKPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RG8cE),holderofFacilityOperatingLicense¹.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixA,tothatlicense,beamended.ThisrequestforchangeistocorrectthespecifiedaccumulatorboratedwatervolumevaluesinSR3.5.1.2tomatchtheassociatedaccumulatorpercentlevelvalues.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchanges,anosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentI.Thisevaluationdemonstratesthattheproposedchangesdonotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeftluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangesalsodonotinvolveasignificanthazardsconsideration.9708270i989708i9]PORADOCK05000244PPDR AmarkedupcopyoftheGinnaStationTechnicalSpecificationswhichshowtherequestedchangesissetforthinAttachmentII.TheproposedrevisedtechnicalspecificationsareprovidedinAttachmentIII.WHEREFORE,ApplicantrespectfullyrequeststhatFacilityOperatingLicenseNo.DPR-18,andAttachmentAtothatlicense,beamendedintheformattachedheretoasAttachmentIII.RochesterGasandElectricCorporationByRobertC.MecreyVicePresidentNuclearOperationsSubscribedandsworntobeforemeonthis19thdayofAugust1997.NotaryPublicDEBORAHA.PIPERNINotaryPublicmtheStateofNewYorkONTARIOCOUNTYCommissionCxpiresNov.23,19,.7.7. | | {{#Wiki_filter:UNITED STATES OF AlVKRICA NUCLEAR REGULATORY COMMSSION In the Matter of ) |
| AttachmentIR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestCorrectionofAccumulatorBoratedWaterVolume(SR3.5.1.2)Thisattachmentprovidesadescriptionofthelicenseamendmentrequest(LAR)andthenecessaryjustificationstosupportcorrectionoftheaccumulatorboratedwatervolumesspecifiedinSR3.5.1.2.Thisattachmentisdividedintosixsectionsasfollows.SectionAsummarizesallchangestotheGinnaStationImprovedTechnicalSpecifications(ITS)whileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesthejustificationsassociatedwiththeseproposedchanges.AnosignificanthazardsconsiderationevaluationandenvironmentalconsiderationoftherequestedchangestotheGinnaStationTechnicalSpecificationsareprovidedinSectionsDandE,respectively.SectionFlistsallreferencesusedinthisattachment.A.DESCRIPTIONOFTECHNICALSPECIFICATIONCHANGESThisLARproposestorevisetheGinnaStationITSassummarizedbelowandshowninAttachmentII.1.LCO3.5.1SR3.5.1.2isrevisedtocorrectthespecifiedaccumulatorboratedwatervolumevaluesinordertomatchwiththeassociatedaccumulatorpercentlevelvalues.B.BACKGROUNDOnFebruary13,1996,theNRCissuedAmendmentNo.61totheGinnaStationtechnicalspecifications.ThisamendmentreplacedtheexistingGinnaStationtechnicalspecificationsintheirentiretywithITSthatwerebasedonNUREG-1431.IncludedwithintheITSwastheadditionofspecificaccumulatorboratedwatervolumestomatchwiththeexistingaccumulatorpercentlevelvalues.Thatis,theprevioustechnicalspecificationsalreadyrequiredanaccumulatorinventorybasedonpercentlevel.ThewatervolumesincubicfeetthatwereaddedtoSR3.5.2.1wereintendedtobethesameaccumulatorinventoriesandwerethosecalledoutintheaccidentanalyses.However,asidentifiedinRG&EActionReport97-0960,ithassincebeendeterminedthatthewatervolumesasspecifiedintheITSdonotcorrectlymatchupwiththepercentlevelvalues.Thiswasduetoanerrorintheaccumulatorwallthicknessusedinthecalculation.
| | ) |
| ToensurecontinuedcompliancewiththeexistingSR3.5.2.1requirements,RG8'cEiscurrentlymaintainingRWSTlevelbetween67%and82%level(versusthespecified50%to82%level).Thisbandwasdeterminedbasedonmeetingthemostlimitingofthespecifiedcubicfeetandpercentlevelvalues.RG&EandWestinghousehavesincere-evaluatedtheaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)usingthecorrectcubicfeetvalueswithrespecttothe50%and82%levelsasspecifiedinSR3.5.2.1anddeterminedanegligiblechangeresults(i.e.,theresultsareacceptable).ItshouldbenotedthatasdescribedonITSbasespageB3.5-4,onlyanominalaccumulatorlevelisusedintheaccidentanalysisduetocompetingeffectsofhigherversuslowerlevels.Thatis,theaccidentanalysisdoesnotusetheupperandloweraccumulatorvolumes,onlyanaverage.Consequently,thepurposeofthisLARistocorrecttheconversionerror.NomodificationsarerequiredinordertoimplementthisLAR.C.JUSTIFICATIONOFCHANGESThissectionprovidesthejustificationforallchangesdescribedinSectionAaboveandshowninAttachmentII.Thejustificationsareorganizedbasedonwhetherthechangeis:morerestrictive(M),lessrestrictive(L),administrative(A),ortherequirementisrelocated(R).Thejustificationslistedbelowarealsoreferencedinthetechnicalspecification(s)whichareaffected(seeAttachmentII).ItisnotedthatthereareonlyadministrativechangesassociatedwiththisLAR.C.1miniraiv1.TheaccumulatorboratedwatervolumeincubicfeetiscorrectedinordertomatchwiththespecifiedaccumulatorpercentlevelinSR3.5.2.1.Thischangeisrequiredtocorrectanerrorthatwascausedbyusinganincorrectaccumulatorwallthickness.Theaffectedaccidentanalyses(e.g.,smallandlargeLOCAandsteamlinebreaks)havebeenre-evaluatedbyRG&;EandWestinghouseusingthecorrectcubicfeetvalueswithrespecttothe50%and82%levels.Theresultsindicatethattherewasanegligliblechangesuchthatallrequirementswithrespecttotheemergencycorecoolingsystemremainmet(e.g.,10CFR50,AppendixK).Therearenotlessrestrictive(L),morerestrictive(M),orrelocated(R)changesassociatedwiththisLAR.
| | Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant) ) |
| D.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsasidentifiedinSectionAandjustifiedinSectionChavebeenevaluatedwithrespectto,10CFR50.92(c)andshowntonotinvolveasignificanthazardsconsiderationasdescribedbelow.ThissectionisorganizedbasedonSectionCabove.D.1linfminirihnTheadministrativechangesdiscussedinSectionC.ldonotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Thechangeisonlytocorrectaconversionerrorwithrespecttoaccumulatorboratedwatervolume.Thisdoesnotincreasetheprobabilityofanyaccidentpreviouslyevaluatedsincetheaccumulatorwatervolumeprovidesmitigationcapabilityonly(i.e.,doesnotinitiateanyaccident).Theaffectedaccidentanalyseswithrespecttotheaccumulator(e.g.,smallandlargeLOCAandsteamlinebreak)havebeenre-evaluatedusingthecorrectaccumulatorwatervolumevalueswithacceptableresults.Therefore,thesechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangesdonotinvolveaphysicalalterationoftheplant(i.e.,nonewordifferenttypeofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation.GinnaStationoperatorsverifyaccumulatorwatervolumeviapercentlevel(versuscubicfeet)whichremainsunchanged.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.Theproposedchangesonlycorrectaconversionerror.Theerrorhasbeenre-evaluatedwithacceptableresults.Assuch,noquestionofsafetyisinvolved,andthechangedoesnotinvolveasignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedchangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.
| | APPLICATIONFOR AMENDMENT T P ERAT LI E K Pursuant to Section 50.90 of the regulations of the U.S. Nuclear Regulatory Commission (NRC), Rochester Gas and Electric Corporation (RG8cE), holder of Facility Operating License ¹. |
| E.ENVIRONMENTALCONSIDERATIONRGBhasevaluatedtheproposedchangesanddeterminedthat:1.ThechangesdonotinvolveasignificanthazardsconsiderationasdocumentedinSectionDabove;2.Thechangesdonotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeftluentsthatmaybereleasedoffsitesincenospecificationsrelatedtooffsitereleasesareaffected;and3.ThechangesdonotinvolveasignificantincreaseinindividualorcumulativeoccupationalradiationexposuresincenonewordifferenttypeofequipmentarerequiredtobeinstalledasaresultofthisLAR.Accordingly,theproposedchangesmeettheeligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired.F.REFERENCESNone.
| | DPR-18, hereby requests that the Technical Specifications set forth in Appendix A, to that license, be amended. This request for change is to correct the specified accumulator borated water volume values in SR 3.5.1.2 to match the associated accumulator percent level values. |
| | A description of the amendment request, necessary background information, justification of the requested changes, a no significant hazards and environmental considerations are provided in Attachment I. This evaluation demonstrates that the proposed changes do not involve a significant change in the types or a significant increase in the amounts of eftluents or any change in the authorized power level of the facility. The proposed changes also do not involve a significant hazards consideration. |
| | 9708270i98 9708i9] |
| | POR ADOCK 05000244 P PDR |
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| }} | | A marked up copy of the Ginna Station Technical Specifications which show the requested changes is set forth in Attachment II. The proposed revised technical specifications are provided in Attachment III. |
| | WHEREFORE, Applicant respectfully requests that Facility Operating License No. DPR-18, and Attachment A to that license, be amended in the form attached hereto as Attachment III. |
| | Rochester Gas and Electric Corporation By Robert C. Mecre y Vice President Nuclear Operations Subscribed and sworn to before me on this 19th day of August 1997. |
| | Notary Public DEBORAH A.PIPERNI Notary Public m the State of New York ONTARIO COUNTY Commission Cxpires Nov. 23, 19,.7.7. |
| | |
| | Attachment I R.E. Ginna Nuclear Power Plant License Amendment Request Correction of Accumulator Borated Water Volume (SR 3.5.1.2) |
| | This attachment provides a description of the license amendment request (LAR) and the necessary justifications to support correction of the accumulator borated water volumes specified in SR 3.5.1.2. |
| | This attachment is divided into six sections as follows. Section A summarizes all changes to the Ginna Station Improved Technical Specifications (ITS) while Section B provides the background and history associated with the changes being requested. Section C provides the justifications associated with these proposed changes. A no significant hazards consideration evaluation and environmental consideration of the requested changes to the Ginna Station Technical Specifications are provided in Sections D and E, respectively. Section F lists all references used in this attachment. |
| | A. DESCRIPTION OF TECHNICAL SPECIFICATION CHANGES This LAR proposes to revise the Ginna Station ITS as summarized below and shown in Attachment II. |
| | : 1. LCO 3.5.1 SR 3.5.1.2 is revised to correct the specified accumulator borated water volume values in order to match with the associated accumulator percent level values. |
| | B. BACKGROUND On February 13, 1996, the NRC issued Amendment No. 61 to the Ginna Station technical specifications. This amendment replaced the existing Ginna Station technical specifications in their entirety with ITS that were based on NUREG-1431. Included within the ITS was the addition of specific accumulator borated water volumes to match with the existing accumulator percent level values. That is, the previous technical specifications already required an accumulator inventory based on percent level. The water volumes in cubic feet that were added to SR 3.5.2.1 were intended to be the same accumulator inventories and were those called out in the accident analyses. However, as identified in RG&E Action Report 97-0960, it has since been determined that the water volumes as specified in the ITS do not correctly match up with the percent level values. This was due to an error in the accumulator wall thickness used in the calculation. |
| | |
| | To ensure continued compliance with the existing SR 3.5.2.1 requirements, RG8'cE is currently maintaining RWST level between 67% and 82% level (versus the specified 50% to 82% level). This band was determined based on meeting the most limiting of the specified cubic feet and percent level values. RG&E and Westinghouse have since re-evaluated the affected accident analyses (e.g., small and large LOCA and steam line breaks) using the correct cubic feet values with respect to the 50% and 82% levels as specified in SR 3.5.2.1 and determined a negligible change results (i.e., the results are acceptable). It should be noted that as described on ITS bases page B 3.5-4, only a nominal accumulator level is used in the accident analysis due to competing effects ofhigher versus lower levels. That is, the accident analysis does not use the upper and lower accumulator volumes, only an average. |
| | Consequently, the purpose of this LAR is to correct the conversion error. No modifications are required in order to implement this LAR. |
| | C. JUSTIFICATION OF CHANGES This section provides the justification for all changes described in Section A above and shown in Attachment II. The justifications are organized based on whether the change is: more restrictive (M), less restrictive (L), administrative (A), or the requirement is relocated (R). |
| | The justifications listed below are also referenced in the technical specification(s) which are affected (see Attachment II). It is noted that there are only administrative changes associated with this LAR. |
| | C.1 mini ra iv |
| | : 1. The accumulator borated water volume in cubic feet is corrected in order to match with the specified accumulator percent level in SR 3.5.2.1. This change is required to correct an error that was caused by using an incorrect accumulator wall thickness. |
| | The affected accident analyses (e.g., small and large LOCA and steam line breaks) have been re-evaluated by RG&;E and Westinghouse using the correct cubic feet values with respect to the 50% and 82% levels. The results indicate that there was a negliglible change such that all requirements with respect to the emergency core cooling system remain met (e.g., 10CFR50, Appendix K). |
| | There are not less restrictive (L), more restrictive (M), or relocated (R) changes associated with this LAR. |
| | D. SIGNIFICANT HAZARDS CONSIDERATION EVALUATION The proposed changes to the Ginna Station Technical Specifications as identified in Section A and justified in Section C have been evaluated with respect to, 10 CFR 50.92(c) and shown to not involve a significant hazards consideration as described below. This section is organized based on Section C above. |
| | D.1 l in f mini r i hn The administrative changes discussed in Section C.l do not involve a significant hazards consideration as discussed below: |
| | Operation of Ginna Station in accordance with the proposed changes does not involve a significant increase in the probability or consequences of an accident previously evaluated. The change is only to correct a conversion error with respect to accumulator borated water volume. This does not increase the probability of any accident previously evaluated since the accumulator water volume provides mitigation capability only (i.e., does not initiate any accident). The affected accident analyses with respect to the accumulator (e.g., small and large LOCA and steam line break) have been re-evaluated using the correct accumulator water volume values with acceptable results. Therefore, these changes do not involve a significant increase in the probability or consequences of an accident previously analyzed. |
| | Operation of Ginna Station in accordance with the proposed changes does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or changes in the methods governing normal plant operation. Ginna Station operators verify accumulator water volume via percent level (versus cubic feet) which remains unchanged. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | Operation of Ginna Station in accordance with the proposed changes does not involve a significant reduction in a margin of safety. The proposed changes only correct a conversion error. The error has been re-evaluated with acceptable results. As such, no question of safety is involved, and the change does not involve a significant reduction in a margin of safety. |
| | Based upon the above information, it has been determined that the proposed changes to the Ginna Station Technical Specifications do not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of a new or different kind of accident previously evaluated, and does not involve a significant reduction in a margin of safety. Therefore, it is concluded that the proposed changes meet the requirements of 10 CFR 50.92(c) and do not involve a significant hazards consideration. |
| | |
| | E. ENVIRONMENTALCONSIDERATION RGB has evaluated the proposed changes and determined that: |
| | : 1. The changes do not involve a significant hazards consideration as documented in Section D above; |
| | : 2. The changes do not involve a significant change in the types or significant increase in the amounts of any eftluents that may be released offsite since no specifications related to offsite releases are affected; and |
| | : 3. The changes do not involve a significant increase in individual or cumulative occupational radiation exposure since no new or different type of equipment are required to be installed as a result of this LAR. |
| | Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed changes is not required. |
| | F. REFERENCES None.}} |
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ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17265A6921999-06-28028 June 1999 Application for Amend to License DPR-18 to Revise ITS Associated with RCS Leakage Detection Instrumentation.Lar Proposed as Result of Commitment That Rg&E Submit as Part of Staff Review of Application of leak-before-break Status ML17265A5691999-03-0101 March 1999 Application for Amend to License DPR-18,proposing Change in ITS to Revise Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A4651998-11-24024 November 1998 Application for Amend to License DPR-18,revising Improved Tech Spec Description of Fuel Cladding Matl (TS 4.2.1) & Updating References Provided in TS 5.6.5 for COLR ML17265A2431998-04-27027 April 1998 Application for Amend to License DPR-18,revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17264B0431997-09-29029 September 1997 Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept ML17264B0381997-09-29029 September 1997 Application for Amend to License DPR-18,revising TS Re Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Revised Setpoint Analysis ML17264B0021997-08-19019 August 1997 Application for Amend to License DPR-18,allowing Testing of Certain ECCS motor-operated Valves in Mode 4 Which Currently Requires Entry in LCO 3.0.3 ML17264A9981997-08-19019 August 1997 Application for Amend to License DPR-18,correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A8661997-04-24024 April 1997 Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements ML17264A8471997-03-31031 March 1997 Application for Amend to License DPR-18,revising Spent Fuel Pool Storage Requirements ML20134D9911996-10-29029 October 1996 Application for Amend to License DPR-18,requesting Change to Mode of Applicability for Auxiliary Feedwater Pump Actuation on Main Feedwater Pump ML17264A7121996-10-29029 October 1996 Application for Amend to License DPR-18 Requesting Change to Required Actions for Inoperable Channels Associated with Auxiliary Feedwater Pump ML17264A5991996-09-13013 September 1996 Application for Amend to License DPR-18,revising RCS Pressure & Temp Limits Rept ML17264A4701996-05-0808 May 1996 Application for Amend to License DPR-18,correcting Typos ML17264A4041996-03-15015 March 1996 Application for Amend to License DPR-18,revising TS to Incorporate Methodology for Determining RCS P/T Limits & LTOP Limits in Administrative Controls Section of RCS P/T Limits Rept ML17264A3441996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS Table 3.3.2-1,Function 5b, Feedwater Isolation,Sg Water Level - High to Raise Allowable Value & Trip Setpoint ML17264A3381996-02-0909 February 1996 Application for Amend to License DPR-18,revising TS to Incorporate Ref to Methodology for Determining LTOP Limits Into Administrative Controls Section for RCS PT Limits Rept ML17264A3331996-02-0909 February 1996 Application for Amend to License DPR-18,revising Requirements for Containment Closure During Mode 6 to Allow Use of Installed Overhead Door Assembly to Isolate Equipment Hatch Opening ML17264A3221996-01-26026 January 1996 Application for Amend to License DPR-18,incorporating Changes Necessary to Reflect Revised Nuclear Fuel Loading ML17264A2521995-11-27027 November 1995 Application for Amend to License DPR-18,revising TS to Implement 10CFR50,App J,Option B ML17264A2551995-11-20020 November 1995 Application for Amend to License DPR-18,submitting Changes to TS Instrumentation Requirements & Conversion to Improved TS ML17264A1501995-08-31031 August 1995 Application for Amend to License DPR-18,proposing Ts,By Implementing WCAP-10271,its Assoc Suppls & Other Re Changes W/Respect to RTS & ESFAS ML17263B0671995-05-26026 May 1995 Application for Amend to License DPR-18,revising TSs in Entirety to Convert to Improved TSs ML17263A9771995-03-13013 March 1995 Application for Amend to License DPR-18,to Revise TS 4.4.2.4.a to Replace Specific Leakage Testing Frequencies for Containment Isolation Valves ML17309A5501994-07-15015 July 1994 Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431 ML17263A7141994-06-24024 June 1994 Application for Amend to License DPR-18,re Upgrading of Administrative Controls Section 6 ML17263A7071994-06-15015 June 1994 Notarized Application for Amend to License DPR-18 Re Reactor Coolant Activity ML17263A6551994-05-23023 May 1994 Application for Amend to License DPR-18,increasing Allowable Reactor Coolant Activity Levels to Improved TS (NUREG-1431) ML17263A6411994-05-13013 May 1994 Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS ML17263A3181993-07-13013 July 1993 Application for Amend to License Revisions for License DPR-18 Re Removing Containment Isolation Valve Table 3.6-1 from TS ML17263A2081993-04-0505 April 1993 Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR ML17262B1171992-12-17017 December 1992 Application for Amend to License DPR-19,revising TS Sections 3.2 & 3.3 to Eliminate Use of High Concentration Boric Acid as safety-related Source of SI Pumps & Increasing Allowable Outage Times ML17262B0991992-11-30030 November 1992 Application for Amend to License DPR-18,revising TS to Remove Table of Containment Isolation Valves & Provide Ref in Bases to UFSAR ML17262B0571992-10-0808 October 1992 Corrected Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Consisting of Notarized Page Two ML17262B0431992-10-0808 October 1992 Application for Amend to License DPR-18,adding Addl Requirements to Auxiliary Electrical Sys TS & Action Statements for Instrument Bus Sys,Per Guidance Provided in GL 91-11 Re Resolution of GI 48 ML17262B0201992-09-15015 September 1992 Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94 ML17262A9121992-06-22022 June 1992 Application for Amend to License DPR-18,revising TS 4.3.1 Per Guidance Provided in Generic Ltr 91-01, Removal of Schedule for Withdrawal of Reactor Vessel Matl Specimens from Ts. ML17262A8311992-04-23023 April 1992 Application for Amend to License DPR-18,changing TSs to Redefine Snubber Visual Insp Schedule,Per Generic Ltr 90-09 Guidance ML17262A8211992-04-21021 April 1992 Application for Amend to License DPR-18,instituting Std License Condition for Fire Protection Program & Removing Requirements for Fire Protection Sys from Tss,Per Guidance in Generic Ltrs 86-10 & 88-12 ML17262A7861992-03-23023 March 1992 Application for Amend to License DPR-18,revising Tech Spec Section 6.5.1, Plant Operations Review Committee Function. ML17262A7801992-03-20020 March 1992 Application for Amend to License DPR-18,revising TS 5.1 Figure 5.1-1 to Describe Rather than Depict Site Area Boundary to Evaluate Radiological Releases to Unrestricted Area ML17262A7901992-03-20020 March 1992 Application for Amend to License DPR-18,revising Tech Specs 6.9.1.2 & 6.9.2.5 ML17262A6321991-10-25025 October 1991 Application for Amend to License DPR-18 to Delete TS 5.1 & Figure 5.1-1 ML17262A5331991-06-20020 June 1991 Application for Amend to License DPR-18,to Incorporate Changes to Specifications & Action Statements for Offsite & Onsite Power Sources Available for Operation of Plant Auxiliaries ML17262A4121991-03-0808 March 1991 Application for Amend to License DPR-18,removing Table 3.6-1 Re Containment Isolation Valves from Tech Specs ML17262A3831991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Specs to Modify Method of Locking Open Motor Operated Valve 856, Refueling Water Storage Tank Delivery Valve When Reactor Coolant Sys at or Above 350 F ML17262A3751991-02-15015 February 1991 Application for Amend to License DPR-18,revising Heatup/Cooldown Curves & Associated Low Temp Overpressure Protection Setpoint to Implement Reg Guide 1.99,Rev 2 Methodology ML17262A3721991-02-15015 February 1991 Application for Amend to License DPR-18,providing Clarification of Which QA Activities Subj to Audit Considerations & Changing Audit Frequency Described in Tech Spec 6.5.2.8d ML17262A3871991-02-15015 February 1991 Application for Amend to License DPR-18,revising Tech Spec Tables 3.5-5 & 4.1-5 Based on Mods to Radiation Monitoring Sys ML17262A2951991-01-14014 January 1991 Application for Amend to License DPR-18,changing Tech Specs to Limit Containment Internal Pressure to 1 Psig Vs 6 Psig Per Initial Condition Assumptions in Containment Integrity Analysis 1999-06-28
[Table view] |
Text
UNITED STATES OF AlVKRICA NUCLEAR REGULATORY COMMSSION In the Matter of )
)
Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant) )
APPLICATIONFOR AMENDMENT T P ERAT LI E K Pursuant to Section 50.90 of the regulations of the U.S. Nuclear Regulatory Commission (NRC), Rochester Gas and Electric Corporation (RG8cE), holder of Facility Operating License ¹.
DPR-18, hereby requests that the Technical Specifications set forth in Appendix A, to that license, be amended. This request for change is to correct the specified accumulator borated water volume values in SR 3.5.1.2 to match the associated accumulator percent level values.
A description of the amendment request, necessary background information, justification of the requested changes, a no significant hazards and environmental considerations are provided in Attachment I. This evaluation demonstrates that the proposed changes do not involve a significant change in the types or a significant increase in the amounts of eftluents or any change in the authorized power level of the facility. The proposed changes also do not involve a significant hazards consideration.
9708270i98 9708i9]
POR ADOCK 05000244 P PDR
A marked up copy of the Ginna Station Technical Specifications which show the requested changes is set forth in Attachment II. The proposed revised technical specifications are provided in Attachment III.
WHEREFORE, Applicant respectfully requests that Facility Operating License No. DPR-18, and Attachment A to that license, be amended in the form attached hereto as Attachment III.
Rochester Gas and Electric Corporation By Robert C. Mecre y Vice President Nuclear Operations Subscribed and sworn to before me on this 19th day of August 1997.
Notary Public DEBORAH A.PIPERNI Notary Public m the State of New York ONTARIO COUNTY Commission Cxpires Nov. 23, 19,.7.7.
Attachment I R.E. Ginna Nuclear Power Plant License Amendment Request Correction of Accumulator Borated Water Volume (SR 3.5.1.2)
This attachment provides a description of the license amendment request (LAR) and the necessary justifications to support correction of the accumulator borated water volumes specified in SR 3.5.1.2.
This attachment is divided into six sections as follows. Section A summarizes all changes to the Ginna Station Improved Technical Specifications (ITS) while Section B provides the background and history associated with the changes being requested. Section C provides the justifications associated with these proposed changes. A no significant hazards consideration evaluation and environmental consideration of the requested changes to the Ginna Station Technical Specifications are provided in Sections D and E, respectively. Section F lists all references used in this attachment.
A. DESCRIPTION OF TECHNICAL SPECIFICATION CHANGES This LAR proposes to revise the Ginna Station ITS as summarized below and shown in Attachment II.
- 1. LCO 3.5.1 SR 3.5.1.2 is revised to correct the specified accumulator borated water volume values in order to match with the associated accumulator percent level values.
B. BACKGROUND On February 13, 1996, the NRC issued Amendment No. 61 to the Ginna Station technical specifications. This amendment replaced the existing Ginna Station technical specifications in their entirety with ITS that were based on NUREG-1431. Included within the ITS was the addition of specific accumulator borated water volumes to match with the existing accumulator percent level values. That is, the previous technical specifications already required an accumulator inventory based on percent level. The water volumes in cubic feet that were added to SR 3.5.2.1 were intended to be the same accumulator inventories and were those called out in the accident analyses. However, as identified in RG&E Action Report 97-0960, it has since been determined that the water volumes as specified in the ITS do not correctly match up with the percent level values. This was due to an error in the accumulator wall thickness used in the calculation.
To ensure continued compliance with the existing SR 3.5.2.1 requirements, RG8'cE is currently maintaining RWST level between 67% and 82% level (versus the specified 50% to 82% level). This band was determined based on meeting the most limiting of the specified cubic feet and percent level values. RG&E and Westinghouse have since re-evaluated the affected accident analyses (e.g., small and large LOCA and steam line breaks) using the correct cubic feet values with respect to the 50% and 82% levels as specified in SR 3.5.2.1 and determined a negligible change results (i.e., the results are acceptable). It should be noted that as described on ITS bases page B 3.5-4, only a nominal accumulator level is used in the accident analysis due to competing effects ofhigher versus lower levels. That is, the accident analysis does not use the upper and lower accumulator volumes, only an average.
Consequently, the purpose of this LAR is to correct the conversion error. No modifications are required in order to implement this LAR.
C. JUSTIFICATION OF CHANGES This section provides the justification for all changes described in Section A above and shown in Attachment II. The justifications are organized based on whether the change is: more restrictive (M), less restrictive (L), administrative (A), or the requirement is relocated (R).
The justifications listed below are also referenced in the technical specification(s) which are affected (see Attachment II). It is noted that there are only administrative changes associated with this LAR.
C.1 mini ra iv
- 1. The accumulator borated water volume in cubic feet is corrected in order to match with the specified accumulator percent level in SR 3.5.2.1. This change is required to correct an error that was caused by using an incorrect accumulator wall thickness.
The affected accident analyses (e.g., small and large LOCA and steam line breaks) have been re-evaluated by RG&;E and Westinghouse using the correct cubic feet values with respect to the 50% and 82% levels. The results indicate that there was a negliglible change such that all requirements with respect to the emergency core cooling system remain met (e.g., 10CFR50, Appendix K).
There are not less restrictive (L), more restrictive (M), or relocated (R) changes associated with this LAR.
D. SIGNIFICANT HAZARDS CONSIDERATION EVALUATION The proposed changes to the Ginna Station Technical Specifications as identified in Section A and justified in Section C have been evaluated with respect to, 10 CFR 50.92(c) and shown to not involve a significant hazards consideration as described below. This section is organized based on Section C above.
D.1 l in f mini r i hn The administrative changes discussed in Section C.l do not involve a significant hazards consideration as discussed below:
Operation of Ginna Station in accordance with the proposed changes does not involve a significant increase in the probability or consequences of an accident previously evaluated. The change is only to correct a conversion error with respect to accumulator borated water volume. This does not increase the probability of any accident previously evaluated since the accumulator water volume provides mitigation capability only (i.e., does not initiate any accident). The affected accident analyses with respect to the accumulator (e.g., small and large LOCA and steam line break) have been re-evaluated using the correct accumulator water volume values with acceptable results. Therefore, these changes do not involve a significant increase in the probability or consequences of an accident previously analyzed.
Operation of Ginna Station in accordance with the proposed changes does not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or changes in the methods governing normal plant operation. Ginna Station operators verify accumulator water volume via percent level (versus cubic feet) which remains unchanged. Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Operation of Ginna Station in accordance with the proposed changes does not involve a significant reduction in a margin of safety. The proposed changes only correct a conversion error. The error has been re-evaluated with acceptable results. As such, no question of safety is involved, and the change does not involve a significant reduction in a margin of safety.
Based upon the above information, it has been determined that the proposed changes to the Ginna Station Technical Specifications do not involve a significant increase in the probability or consequences of an accident previously evaluated, does not create the possibility of a new or different kind of accident previously evaluated, and does not involve a significant reduction in a margin of safety. Therefore, it is concluded that the proposed changes meet the requirements of 10 CFR 50.92(c) and do not involve a significant hazards consideration.
E. ENVIRONMENTALCONSIDERATION RGB has evaluated the proposed changes and determined that:
- 1. The changes do not involve a significant hazards consideration as documented in Section D above;
- 2. The changes do not involve a significant change in the types or significant increase in the amounts of any eftluents that may be released offsite since no specifications related to offsite releases are affected; and
- 3. The changes do not involve a significant increase in individual or cumulative occupational radiation exposure since no new or different type of equipment are required to be installed as a result of this LAR.
Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed changes is not required.
F. REFERENCES None.