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| | issue date = 02/09/1996 | | | issue date = 02/09/1996 |
| | title = 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 | | | title = 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 |
| | 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:UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATIONFORAMENDMENTTPKRATINLlEEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(the"Commission"),RochesterGasandElectricCorporation("RGEcE"),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixAtothatLicensebeamended.ThisrequestforchangeinTechnicalSpecificationsistoreviseTable3.3.2-1,Function5b,"FeedwaterIsolation,SGWaterLevel-High"toraisetheallowablevalueandtripsetpoint.ThischangereflectsdesignimprovementsinthereplacementsteamgeneratorsbeinginstalledatGinnaStationduringthe1996RefuelingOutage.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchange,safetyevaluationandnosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentA.AmarkedupcopyoftheproposedGinnaStationTechnicalSpecificationswhichshowstherequestedchangeissetforinAttachmentB.TheproposedrevisedTechnicalSpecificationsareprovidedinAttachmentC.'7602130462960209'DRADQCK05000244PDR TheevaluationsetforthinAttachmentAdemonstratesthattheproposedchangedoesnotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangealsodoesnotinvolveasignificanthazardsconsideration.WHEREFORE,ApplicantrespectfullyrequeststhatAppendixAtoFacilityOperatingLicenseNo.DPR-18beamendedintheformattachedheretoasAttachmentC.RochesterGasandElectricCorporationRobertC.MecredyVicePresidentNuclearProductionSubscribedandsworntobeforemeonthis9thdayofFebruary,1996.g~MNotaryPublicJOANNES.GORMANNotaryPublicintheStateofNewYorkOrleansCountyCommissionExpiresNov.19 | | {{#Wiki_filter:UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ) |
| /Qpflf><,$~1>IIPO(V.'ll~t ATTACHMENTAR.E.GINNANUCLEARPOWERPLANTLICENSEAMENDMENTREQUESTTECHNICALSPECIFICATIONSTABLE3.3.2-1Thisattachmentprovidesadescriptionoftheamendmentrequestandnecessaryjustificationfortheproposedchanges.Theattachmentisdividedintosixsectionsasfollows.SectionAidentifiesallchangestothecurrentGinnaStationTechnicalSpecificationswhileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesdetailedjustificationfortheproposedchanges.Asafetyevaluation,significanthazardsconsiderationevaluationandenvironmentalconsiderationoftherequestedchangesareprovidedinSectionsD,E,andF,respectively.A.DESCRIPTIONOFAlVKNDMENTREQUESTThisLicenseAmendmentRequest(LAR)proposestoreviseGinnaStationTechnicalSpecificationsTable3.3.2-1asfollows(seeAttachmentBandC):1.TechnicalSpecificationTable3.3.2-1,FunctionSb.i.Theallowablevalueischangedfrom<68%to<94%.ii.Thetripsetpointvalueischangedfrom<67%to<85%.B.BACKGROUND1.HistoryTheSteamGeneratorWaterLevel-Highfeedwaterisolationsetpointisdesignedtopreventexcessivemoisturecarryovertothemainsteamsystem,whichwouldcauseexcessivewearonthemainturbine.SteamGeneratorsseparatewaterintwostages,aPrimarystageandasecondarystage.Primaryseparatorsarelocatedinthesteamdrumofthegeneratorbelowthesecondaryseparators,andgenerallyworkonthecentrifugalprinciple.Thehighwaterlevelsetpointischosensuchthatwaterinthedowncomerisnotabovethetopoftheseprimaryseparatorswhichwouldfloodthemanddegradetheirperformance. GinnaStationisplanningtoreplaceitssteamgeneratorsduringthe1996RefuelingOutage.TheoriginalsteamgeneratorsareWestinghouseModel44steamgenerators.Theprimaryseparatorfloodpointforthesegeneratorsisatapproximately75%narrowrangewaterlevel.Consequently,asetpointsufficientlybelowthisvaluetoallowforinstrumentandprocessmeasurementuncertaintyischosenforthecurrentsetpointvalueof67%narrowrange.ReplacementsteamgeneratorsarebeingmanufacturedbyBabcockandWilcoxInternational.Thefloodpointfortheprimaryseparatorsonthesegeneratorsisabove100%narrowrangelevel.Consequently,newsetpointssufficientlybelow100%toaccountforprocessmeasurementuncertaintyarechosenforanallowablevalue(94%),andinstrumentuncertaintyforasetpointvalue(85%).Thisexpandedrangeallowstheoperatormoretimetorestoreleveltonominalconditionsusingcontrolledmeanspriortoinitiationoffeedwaterisolation.HardwareModificationsPriortoimplementingthisTechnicalSpecificationchangethesteamgeneratorsmustbereplaced.Nootherhardwarechangesarerequired.C.JUSTIFICATIONThedesignofthereplacementsteamgeneratorsissuchthattheprimarysteamseparatorsarelocatedatahigherelevationinthesteamdrumthanintheexistingsteamgenerators.Thebottomoftheactualseparatorisapproximately14inchesabovetheuppernarrowrangeleveltap.Therefore,itisacceptabletooperatewithwaterlevelsabove100%narrowrangelevelwithoutdegradingseparatorperformance.Sincewaterlevelabove100%cannotbemonitored,100%ischosenasthelimit.ThUPSAliidlyhdIhipi(Si15..6,~i"denertrAmshericReliefValveanFeewernrllveFailire)currentlyuseavalueof100%narrowrangelevel.Therefore,theaccidentanalysisisnotaffectedbythisproposedchange.Minimizingthechallengestothissetpointisbeneficial.Fastswingsinfeedwatervalvepositioncausedbyactuation/clearingofthissetpointmakeitdifficulttocontrolthefeedwatersystem,levelintheothersteamgenerator,andprimarysidetemperature.Byraisingthissetpointthenumberofchallengesarereduced.D.SAFETYEVALUATIONTheSteamGeneratorWaterLevel-Highfeedwaterisolationfunctionisdesignedtopreventexcessivemoisturecarryovertothemainsteamsystem.Theproposedsetpointchangedoesnotdegradethecapabilityofthemoistureseparatorsandthereforethisfunctionisunchanged. TheUFSARaccidentanalysesthatmodelthisfunction(UFSARSection15.1.6)useavalueof100%narrowrangelevel.Thereforetheaccidentanalysisisnotaffectedbythisproposedchange.Basedontheabove,theproposedamendmentdoesnotinvolveanunreviewedsafetyquestionandwillnotadverselyaffectorendangerthehealthandsafetyofthegeneralpublic.E.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsdoesnotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedsetpointchangedoesnotdegradetheperformanceofanyplantequipmentTherefore,theprobabilityofanaccidentisnotincreased.Sincetherevisedtripsetpointandallowablevalueremainboundedbytheaccidentanalysisvalueof100%steamgeneratornarrowrangelevel,theconsequencesofanyaccidentarenotadverselyaffected.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangedoesnotinvolveaphysicalalterationtotheplant(i.e.,nonewordifferenttypesofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation,Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.Therevisedsetpointandallowablevalueremainboundedbytheaccidentanalysisassumptions.Theexistingvaluesarebasedon'designconsiderationsandnotaccidentanalysisparameters.ThereplacementsteamgeneratorsarenotrestrictedbythesamedesignconsiderationswithrespecttotheESFASSteamGeneratorWaterLevel-Highfunction.Therefore,thischangedoesnotinvolveareductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedchangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration. | | ) |
| F.ENVIRONMENTALCONSIDERATIONRGBhasevaluatedtheproposedchangesanddeterminedthat:ThechangesdonotinvolveasignificanthazardsconsiderationasdocumentedinSectionEabove;2.Thechangesdonotinvolveachangeinthetypesorincreaseintheamountsofanyeffluentsthatmaybereleasedoffsitesinceequipmentperformanceisunchanged,andtheaccidentanalysisisunchanged.ThechangesdonotinvolveanyincreaseinindividualorcumulativeoccupationalradiationexposuresincenonewordifferenttypeofequipmentarerequiredtobeinstalledasaresultofthisLAR,norareanyoperatingortestingpracticestobechanged.Accordingly,theproposedchangesmeettheeligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired. | | Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant) ) |
| }} | | APPLICATIONFOR AMENDMENT T PKRATIN Ll E E Pursuant to Section 50.90 of the regulations of the U.S. Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGEcE"), holder of Facility Operating License No. DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that License be amended. This request for change in Technical Specifications is to revise Table 3.3.2-1, Function 5b, "Feedwater Isolation, SG Water Level - High" to raise the allowable value and trip setpoint. This change reflects design improvements in the replacement steam generators being installed at Ginna Station during the 1996 Refueling Outage. |
| | A description of the amendment request, necessary background information, justification of the requested change, safety evaluation and no significant hazards and environmental considerations are provided in Attachment A. A marked up copy of the proposed Ginna Station Technical Specifications which shows the requested change is set for in Attachment B. The proposed revised Technical Specifications are provided in Attachment C. |
| | '7602130462 960209 |
| | 'DR ADQCK 05000244 PDR |
| | |
| | The evaluation set forth in Attachment A demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. The proposed change also does not involve a significant hazards consideration. |
| | WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No. DPR-18 be amended in the form attached hereto as Attachment C. |
| | Rochester Gas and Electric Corporation Robert C. Mecredy Vice President Nuclear Production Subscribed and sworn to before me on this 9th day of February, 1996. |
| | g~ M Notary Public JOANNE S. GORMAN Notary Public in the State of New York Orleans County Commission Expires Nov. 19 |
| | |
| | /Qpfl f><, $ ~1 > II PO( |
| | V.'ll ~ t |
| | |
| | ATTACHMENTA R.E. GINNANUCLEAR POWER PLANT LICENSE AMENDMENTREQUEST TECHNICAL SPECIFICATIONS TABLE 3.3.2-1 This attachment provides a description of the amendment request and necessary justification for the proposed changes. The attachment is divided into six sections as follows. Section A identifies all changes to the current Ginna Station Technical Specifications while Section B provides the background and history associated with the changes being requested. Section C provides detailed justification for the proposed changes. A safety evaluation, significant hazards consideration evaluation and environmental consideration of the requested changes are provided in Sections D, E, and F, respectively. |
| | A. DESCRIPTION OF AlVKNDMENTREQUEST This License Amendment Request (LAR) proposes to revise Ginna Station Technical Specifications Table 3.3.2-1 as follows (see Attachment B and C): |
| | : 1. Technical Specification Table 3.3.2-1, Function Sb. |
| | : i. The allowable value is changed from <68% to <94%. |
| | ii. The trip setpoint value is changed from <67% to <85%. |
| | B. BACKGROUND |
| | : 1. History The Steam Generator Water Level - High feedwater isolation setpoint is designed to prevent excessive moisture carryover to the main steam system, which would cause excessive wear on the main turbine. Steam Generators separate water in two stages, a Primary stage and a secondary stage. Primary separators are located in the steam drum of the generator below the secondary separators, and generally work on the centrifugal principle. The high water level setpoint is chosen such that water in the downcomer is not above the top of these primary separators which would flood them and degrade their performance. |
| | |
| | Ginna Station is planning to replace its steam generators during the 1996 Refueling Outage. The original steam generators are Westinghouse Model 44 steam generators. The primary separator flood point for these generators is at approximately 75% narrow range water level. Consequently, a setpoint sufficiently below this value to allow for instrument and process measurement uncertainty is chosen for the current setpoint value of 67% narrow range. |
| | Replacement steam generators are being manufactured by Babcock and Wilcox International. The flood point for the primary separators on these generators is above 100% narrow range level. Consequently, new setpoints sufficiently below 100% to account for process measurement uncertainty are chosen for an allowable value (94%), and instrument uncertainty for a setpoint value (85%). This expanded range allows the operator more time to restore level to nominal conditions using controlled means prior to initiation of feedwater isolation. |
| | Hardware Modifications Prior to implementing this Technical Specification change the steam generators must be replaced. No other hardware changes are required. |
| | C. JUSTIFICATION The design of the replacement steam generators is such that the primary steam separators are located at a higher elevation in the steam drum than in the existing steam generators. The bottom of the actual separator is approximately 14 inches above the upper narrow range level tap. Therefore, it is acceptable to operate with water levels above 100% narrow range level without degrading separator performance. Since water level above 100% cannot be monitored, 100% is chosen as the limit. |
| | Th UPSAli id ly h d I hi p i (S i 15..6,~i" d ener t r A m s hericRelief Valvean Fee w er n r l lveFail ire ) currentlyuse a value of 100% narrow range level. Therefore, the accident analysis is not affected by this proposed change. |
| | Minimizing the challenges to this setpoint is beneficial. Fast swings in feedwater valve position caused by actuation/clearing of this setpoint make it difficult to control the feedwater system, level in the other steam generator, and primary side temperature. By raising this setpoint the number of challenges are reduced. |
| | D. SAFETY EVALUATION The Steam Generator Water Level - High feedwater isolation function is designed to prevent excessive moisture carryover to the main steam system. The proposed setpoint change does not degrade the capability of the moisture separators and therefore this function is unchanged. |
| | |
| | The UFSAR accident analyses that model this function (UFSAR Section 15.1.6) use a value of 100% narrow range level. Therefore the accident analysis is not affected by this proposed change. |
| | Based on the above, the proposed amendment does not involve an unreviewed safety question and willnot adversely affect or endanger the health and safety of the general public. |
| | E. SIGNIFICANT HAZARDS CONSIDERATION EVALUATION The proposed changes to the Ginna Station Technical Specifications does 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 proposed setpoint change does not degrade the performance of any plant equipment Therefore, the probability of an accident is not increased. Since the revised trip setpoint and allowable value remain bounded by the accident analysis value of 100% steam generator narrow range level, the consequences of any accident are not adversely affected. |
| | 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 change does not involve a physical alteration to the plant (i.e., no new or different types of equipment will be installed) or changes in the methods governing normal plant operation, 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 revised setpoint and allowable value remain bounded by the accident analysis assumptions. The existing values are based on'design considerations and not accident analysis parameters. The replacement steam generators are not restricted by the same design considerations with respect to the ESFAS Steam Generator Water Level - High function. |
| | Therefore, this change does not involve a 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. |
| | |
| | F. ENVIRONMENTALCONSIDERATION RGB has evaluated the proposed changes and determined that: |
| | The changes do not involve a significant hazards consideration as documented in Section E above; |
| | : 2. The changes do not involve a change in the types or increase in the amounts of any effluents that may be released offsite since equipment performance is unchanged, and the accident analysis is unchanged. |
| | The changes do not involve any 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, nor are any operating or testing practices to be changed. |
| | 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.}} |
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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 AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
Rochester Gas and Electric Corporation ) Docket No. 50-244 (R.E. Ginna Nuclear Power Plant) )
APPLICATIONFOR AMENDMENT T PKRATIN Ll E E Pursuant to Section 50.90 of the regulations of the U.S. Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation ("RGEcE"), holder of Facility Operating License No. DPR-18, hereby requests that the Technical Specifications set forth in Appendix A to that License be amended. This request for change in Technical Specifications is to revise Table 3.3.2-1, Function 5b, "Feedwater Isolation, SG Water Level - High" to raise the allowable value and trip setpoint. This change reflects design improvements in the replacement steam generators being installed at Ginna Station during the 1996 Refueling Outage.
A description of the amendment request, necessary background information, justification of the requested change, safety evaluation and no significant hazards and environmental considerations are provided in Attachment A. A marked up copy of the proposed Ginna Station Technical Specifications which shows the requested change is set for in Attachment B. The proposed revised Technical Specifications are provided in Attachment C.
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'DR ADQCK 05000244 PDR
The evaluation set forth in Attachment A demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility. The proposed change also does not involve a significant hazards consideration.
WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No. DPR-18 be amended in the form attached hereto as Attachment C.
Rochester Gas and Electric Corporation Robert C. Mecredy Vice President Nuclear Production Subscribed and sworn to before me on this 9th day of February, 1996.
g~ M Notary Public JOANNE S. GORMAN Notary Public in the State of New York Orleans County Commission Expires Nov. 19
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ATTACHMENTA R.E. GINNANUCLEAR POWER PLANT LICENSE AMENDMENTREQUEST TECHNICAL SPECIFICATIONS TABLE 3.3.2-1 This attachment provides a description of the amendment request and necessary justification for the proposed changes. The attachment is divided into six sections as follows. Section A identifies all changes to the current Ginna Station Technical Specifications while Section B provides the background and history associated with the changes being requested. Section C provides detailed justification for the proposed changes. A safety evaluation, significant hazards consideration evaluation and environmental consideration of the requested changes are provided in Sections D, E, and F, respectively.
A. DESCRIPTION OF AlVKNDMENTREQUEST This License Amendment Request (LAR) proposes to revise Ginna Station Technical Specifications Table 3.3.2-1 as follows (see Attachment B and C):
- 1. Technical Specification Table 3.3.2-1, Function Sb.
- i. The allowable value is changed from <68% to <94%.
ii. The trip setpoint value is changed from <67% to <85%.
B. BACKGROUND
- 1. History The Steam Generator Water Level - High feedwater isolation setpoint is designed to prevent excessive moisture carryover to the main steam system, which would cause excessive wear on the main turbine. Steam Generators separate water in two stages, a Primary stage and a secondary stage. Primary separators are located in the steam drum of the generator below the secondary separators, and generally work on the centrifugal principle. The high water level setpoint is chosen such that water in the downcomer is not above the top of these primary separators which would flood them and degrade their performance.
Ginna Station is planning to replace its steam generators during the 1996 Refueling Outage. The original steam generators are Westinghouse Model 44 steam generators. The primary separator flood point for these generators is at approximately 75% narrow range water level. Consequently, a setpoint sufficiently below this value to allow for instrument and process measurement uncertainty is chosen for the current setpoint value of 67% narrow range.
Replacement steam generators are being manufactured by Babcock and Wilcox International. The flood point for the primary separators on these generators is above 100% narrow range level. Consequently, new setpoints sufficiently below 100% to account for process measurement uncertainty are chosen for an allowable value (94%), and instrument uncertainty for a setpoint value (85%). This expanded range allows the operator more time to restore level to nominal conditions using controlled means prior to initiation of feedwater isolation.
Hardware Modifications Prior to implementing this Technical Specification change the steam generators must be replaced. No other hardware changes are required.
C. JUSTIFICATION The design of the replacement steam generators is such that the primary steam separators are located at a higher elevation in the steam drum than in the existing steam generators. The bottom of the actual separator is approximately 14 inches above the upper narrow range level tap. Therefore, it is acceptable to operate with water levels above 100% narrow range level without degrading separator performance. Since water level above 100% cannot be monitored, 100% is chosen as the limit.
Th UPSAli id ly h d I hi p i (S i 15..6,~i" d ener t r A m s hericRelief Valvean Fee w er n r l lveFail ire ) currentlyuse a value of 100% narrow range level. Therefore, the accident analysis is not affected by this proposed change.
Minimizing the challenges to this setpoint is beneficial. Fast swings in feedwater valve position caused by actuation/clearing of this setpoint make it difficult to control the feedwater system, level in the other steam generator, and primary side temperature. By raising this setpoint the number of challenges are reduced.
D. SAFETY EVALUATION The Steam Generator Water Level - High feedwater isolation function is designed to prevent excessive moisture carryover to the main steam system. The proposed setpoint change does not degrade the capability of the moisture separators and therefore this function is unchanged.
The UFSAR accident analyses that model this function (UFSAR Section 15.1.6) use a value of 100% narrow range level. Therefore the accident analysis is not affected by this proposed change.
Based on the above, the proposed amendment does not involve an unreviewed safety question and willnot adversely affect or endanger the health and safety of the general public.
E. SIGNIFICANT HAZARDS CONSIDERATION EVALUATION The proposed changes to the Ginna Station Technical Specifications does 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 proposed setpoint change does not degrade the performance of any plant equipment Therefore, the probability of an accident is not increased. Since the revised trip setpoint and allowable value remain bounded by the accident analysis value of 100% steam generator narrow range level, the consequences of any accident are not adversely affected.
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 change does not involve a physical alteration to the plant (i.e., no new or different types of equipment will be installed) or changes in the methods governing normal plant operation, 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 revised setpoint and allowable value remain bounded by the accident analysis assumptions. The existing values are based on'design considerations and not accident analysis parameters. The replacement steam generators are not restricted by the same design considerations with respect to the ESFAS Steam Generator Water Level - High function.
Therefore, this change does not involve a 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.
F. ENVIRONMENTALCONSIDERATION RGB has evaluated the proposed changes and determined that:
The changes do not involve a significant hazards consideration as documented in Section E above;
- 2. The changes do not involve a change in the types or increase in the amounts of any effluents that may be released offsite since equipment performance is unchanged, and the accident analysis is unchanged.
The changes do not involve any 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, nor are any operating or testing practices to be changed.
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.