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| {{#Wiki_filter:TECHNICALSPECIFICATIONMARKUPS9304090264930402pfPDRADOCK05000387PDR RIRLATINLP.-INLELPPERATNLIMITINNDITIONFROPERATION3.4.1~1.2Onereactorcoolantrecirculationloopshallbeinoperationwiththepumpspeeds80%oftheratedpumpspeedandthereactorataTHERMALPOWER/coreflowconditionoutsideofRegionsIandIIofFigure3.4.1.1.1-1,anda.thefollowingrevisedspecificationlimitsshallbefollowed:1.Specification2.1.2:theMCPRSafetyLimitshallbeincreasedto1.07.4.0V~E2.Table2.2.1-1:theAPRMFlow-BiasedScramTripSetpointsshallbeasfollows:'''=~,;-Trip',Setpoint.~;~"."";-.>-."'P~~~Pr-".'gj".;~~~'4b:.':'"lAIIowabhi:Value~-,":,~'",'.s0.58W+54%s0.58W+57%v00H~vCTj\3.Specification3.2.2:theAPRMSetpointsshallbeasfollows:""""j~'":"'":""')Trip,'Setpoht~"-""'~"""'i"."'F~':'~4''Z~~'-:"AIIowable'Yah'-';;<i+:.--'"i>>Ss(0.58W+54%)TSps(0.58W+45%)TSs(0.58W+57%)TS<s(0.58W+48%)T4.Specification3.2.3:TheMINIMUMCRITICALPOWERRATIO(MCPR)shallbegreaterthanorequaltothelargestofthefollowingvalues:Ia.theMCPRdeterminedfromFigure3.2.3-1plus0.01,andIb.theMCPRdeterminedfromFigure3.2.3-2,Figure3.2.3-3,orFigure3.2.3-4,asappropriate,plus0.01.~~~~~g.'gTable3.3.6-2:theRBM/APRMControlRodBlockSetpointsshallbeasfollows:a.RBM-Upscaleb.APRM-FlowBiasedTripSetpoint:.-,',s0.66W+36%TripSetpoint'..=".~-'0.58W+45%~v.",;.'AllowableValoe:.'".'-':.'0.66W+39%;.'-.';-'+;:AIIowibieVetue~,",',,"'s0.58W+48%*:<<<<''+.doperation.¹SUSQUEHANNA-UNIT13/44-1cAmendmentNo.118 | | {{#Wiki_filter:TECHNICAL SPECIFICATION MARKUPS 9304090264 930402 05000387 PDR ADOCK f p PDR |
| | |
| | R IR LATI NL P. - IN LEL P PERAT N LIMITIN NDITION F R OPERATION 3.4.1 1.2 One reactor coolant recirculation loop shall be in operation with the pump speed |
| | ~ |
| | s 80% of the rated pump speed and the reactor at a THERMALPOWER/core flow condition outside of Regions I and II of Figure 3.4.1.1.1-1, and |
| | : a. the following revised specification limits shall be followed: |
| | : 1. Specification 2.1.2: the MCPR Safety Limit shall be increased to 1.07. |
| | : 2. Table 2.2.1-1: the APRM Flow-Biased Scram Trip Setpoints shall be as follows: |
| | 4. |
| | 0 V |
| | ~E ''=~,;- Trip',Setpoint.~;~"."";-.>-."'P~~~Pr-" .'gj".;~~~'4b:.':'"lAIIowabhi:Value ~-,":,~'",'. |
| | s 0.58W + 54% s 0.58W + 57% |
| | : 3. Specification 3.2.2: the APRM Setpoints shall be as follows: |
| | v 0 |
| | """"j~'":"'":""')Trip,'Setpoht~"-""'~"""'i". "'F~': '~4'' Z~~'-:"AIIowable'Yah'-';;<i+:.--'"i>> |
| | 0 S s (0.58W+ 54%) T S s (0.58W + 57%) T H |
| | Sp s (0.58W + 45%) T S< s (0.58W + 48%) T |
| | ~ v |
| | : 4. Specification 3.2.3: The MINIMUMCRITICALPOWER RATIO (MCPR) shall be greater than or equal to the largest of the following values: |
| | I |
| | : a. the MCPR determined from Figure 3.2.3-1 plus 0.01, and I |
| | : b. the MCPR determined from Figure 3.2.3-2, Figure 3.2.3-3, or Figure 3.2.3-4, as appropriate, plus 0.01. |
| | ~ ~ ~ ~ |
| | CTj g.'g Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as |
| | ~ |
| | follows: |
| | \ |
| | ~ v. |
| | Trip Setpoint:. -, ', ",;. 'Allowable Valoe:.'".'-':.' |
| | : a. RBM- Upscale s 0.66W + 36% 0.66W + 39% |
| | Trip Setpoint '..=". ~ -' ;.'-.';-'+;:AIIowibie Vetue~,",',,"' |
| | *: << b. APRM- Flow Biased operation.¹ 0.58W + 45% |
| | ' '+. |
| | s 0.58W + 48% |
| | d SUSQUEHANNA - UNIT 1 3/4 4-1c Amendment No. 118 |
| | |
| | RESPONSE TO NRC QUESTIONS REV. 1 RESPONSE TO NRC QUESTIONS REACTOR SYSTH6 BRANCH QUESTION 3 If single loop operation (SLO) yields a higher peak cladding temperature (PCT) than two loop operation, why is the upper bound peak cladding temperature (UBPCT) based on two loop operation applicable for SLO? Does the limiting single failure and break size remain the same for SLO as for two loop operation? Discuss the applicability of SAFER/GESTR for SLO in view of the fact SLO results in a higher PCT. |
| | Operation with one recirculation loop out of service is allowed, but it is not considered a normal mode of operation. SLO is a special operational condition when only one of the two recirculation loops is operable. In this operating condition, the reactor power will be limited to less than 804 of rated by the maximum achievable core flow, which is typically less than 604 of rated core flow. A postulated LOCA occurring in the active recirculation loop during SLO would cause a more rapid coastdown,of the recirculation flow than would occur in two loop operation, where one active loop would remain intact. This rapid coastdown causes an earlier boiling transition time and deeper penetration of boiling transition into the bundle, which tends to increase the calculated PCT. However, the PCT effects of the early boiling transition are substantially offset by the mitigating effect of the lower power level achievable at the start of such an event. The SAFER/GESTR-LOCA analysis results for Susquehanna (NEDC-32071P) for SLO and two loop operation are well below 2200'F. |
| | The ECCS performance for Susquehanna under SLO was evaluated using SAFER/GESTR-LOCA. Calculations for the DBA were performed using both nominal and Appendix K inputs. The SLO SAFER/GESTR-LOCA analysis for the DBA assumes that there is essentially no period of recirculation pump coastdown. Thus, dryout is assumed to occur simultaneously at all axial locations of the hot bundle shortly after initiation of the event. Dryout is assumed to occur in one second for the nominal case and O.l second for the Appendix K case. These assumptions are very conservative and provide bounding results for the DBA under SLO. |
| | The two-loop Appendix K break spectrum documented in NEDC-32071P is representative of SLO because the two-loop spectrum was analyzed assuming a one second dryout time for all axial locations of the hot bundle. As shown by the two-loop break spectrum, the DBA is the limiting case for SLO. In addition, SLO will affect the DBA results more than the smaller breaks. With breaks smaller than the DBA, there is a longer period of nucleate and/or film boiling prior to fuel uncovery to remove the fuel stored energy. |
| | An LHGR reduction (multiplier) of 0.70 will be imposed when the plant is in SLO. As shown in Table 5-6 of NEDC-32701P, the SLO results are less limiting (i.e., lower PCTs) than the results for the two loop DBA LOCA. |
| | Thus, the licensing PCT is based appropriately on two loop operation rather than SLO. |
|
| |
|
| RESPONSETONRCQUESTIONS RESPONSETONRCQUESTIONSREACTORSYSTH6BRANCHREV.1QUESTION3Ifsingleloopoperation(SLO)yieldsahigherpeakcladdingtemperature(PCT)thantwoloopoperation,whyistheupperboundpeakcladdingtemperature(UBPCT)basedontwoloopoperationapplicableforSLO?DoesthelimitingsinglefailureandbreaksizeremainthesameforSLOasfortwoloopoperation?DiscusstheapplicabilityofSAFER/GESTRforSLOinviewofthefactSLOresultsinahigherPCT.Operationwithonerecirculationloopoutofserviceisallowed,butitisnotconsideredanormalmodeofoperation.SLOisaspecialoperationalconditionwhenonlyoneofthetworecirculationloopsisoperable.Inthisoperatingcondition,thereactorpowerwillbelimitedtolessthan804ofratedbythemaximumachievablecoreflow,whichistypicallylessthan604ofratedcoreflow.ApostulatedLOCAoccurringintheactiverecirculationloopduringSLOwouldcauseamorerapidcoastdown,oftherecirculationflowthanwouldoccurintwoloopoperation,whereoneactiveloopwouldremainintact.Thisrapidcoastdowncausesanearlierboilingtransitiontimeanddeeperpenetrationofboilingtransitionintothebundle,whichtendstoincreasethecalculatedPCT.However,thePCTeffectsoftheearlyboilingtransitionaresubstantiallyoffsetbythemitigatingeffectofthelowerpowerlevelachievableatthestartofsuchanevent.TheSAFER/GESTR-LOCAanalysisresultsforSusquehanna(NEDC-32071P)forSLOandtwoloopoperationarewellbelow2200'F.TheECCSperformanceforSusquehannaunderSLOwasevaluatedusingSAFER/GESTR-LOCA.CalculationsfortheDBAwereperformedusingbothnominalandAppendixKinputs.TheSLOSAFER/GESTR-LOCAanalysisfortheDBAassumesthatthereisessentiallynoperiodofrecirculationpumpcoastdown.Thus,dryoutisassumedtooccursimultaneouslyatallaxiallocationsofthehotbundleshortlyafterinitiationoftheevent.DryoutisassumedtooccurinonesecondforthenominalcaseandO.lsecondfortheAppendixKcase.TheseassumptionsareveryconservativeandprovideboundingresultsfortheDBAunderSLO.Thetwo-loopAppendixKbreakspectrumdocumentedinNEDC-32071PisrepresentativeofSLObecausethetwo-loopspectrumwasanalyzedassumingaoneseconddryouttimeforallaxiallocationsofthehotbundle.Asshownbythetwo-loopbreakspectrum,theDBAisthelimitingcaseforSLO.Inaddition,SLOwillaffecttheDBAresultsmorethanthesmallerbreaks.WithbreakssmallerthantheDBA,thereisalongerperiodofnucleateand/orfilmboilingpriortofueluncoverytoremovethefuelstoredenergy.AnLHGRreduction(multiplier)of0.70willbeimposedwhentheplantisinSLO.AsshowninTable5-6ofNEDC-32701P,theSLOresultsarelesslimiting(i.e.,lowerPCTs)thantheresultsforthetwoloopDBALOCA.Thus,thelicensingPCTisbasedappropriatelyontwoloopoperationratherthanSLO.
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| ~' | | ~' |
| OErrataandAddendaSheetApplicableto:PublicationNo.TitleUnits1and2SAFERGESTR-LOCALoss-Of-ColantAccidentAnalsisIssueDateGf'NvdeerfnerJry/15CurlerA@eveSanJm.CA85125EBANo.Datec199Note:Correctallcopiesoftheapplicablepublicationasspecifiedbelow.References(SecdaaPapePareyaptCkeJlmtrecdaer(Conec0iesaifAdkera)Pages5-6and5-7Replacewithnewpages5-6and5-7Page5-l3ReplacewithnewPage5-13(changebracketsinrighthandmarginindicateareaswherereporthasbeenchanged)
| | O Errata and Addenda Sheet Gf'Nvdeer fnerJry |
| /> | | /15 Curler A@eve San Jm. CA 85125 Applicable to: |
| }} | | Publication No. EBA No. |
| | Title Date c 199 Units 1 and 2 SAFER GESTR-LOCA Loss-Of- Note: Correct all copies of the Co lant Accident Anal sis applicable publication as Issue Date specified below. |
| | References lmtrecdaer (Secdaa Pape (Conec0ies aifAdkera) |
| | Pareyapt CkeJ Pages 5-6 and 5-7 Replace with new pages 5-6 and 5-7 Page 5-l3 Replace with new Page 5-13 (change brackets in right hand margin indicate areas where report has been changed) |
| | |
| | />}} |
|
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18040B2891999-03-12012 March 1999 Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2 ML18040B2881999-01-12012 January 1999 Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A6711998-07-0808 July 1998 Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included ML17159A3261998-05-12012 May 1998 Proposed Tech Specs Re Removal of Fire Protection Program ML18026A4711997-02-11011 February 1997 Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315 ML20129D7851996-09-23023 September 1996 Proposed Tech Specs Re MSIVs Leakage Testing ML20116K3491996-08-0909 August 1996 Proposed Tech Specs Re Battery Load Profiles ML17158B5581996-03-20020 March 1996 Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level ML20115A8171996-02-29029 February 1996 Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59 ML20115A8211996-02-29029 February 1996 Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers ML17158B1071996-02-12012 February 1996 Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program. ML17164A5801995-02-10010 February 1995 Proposed Tech Specs for Aot/Sti Extensions ML17164A4351994-11-21021 November 1994 Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS ML17158A5441994-10-28028 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML20058F8281993-11-24024 November 1993 Proposed Tech Specs Re Power Uprate W/Increased Flow ML17157C2741993-04-0202 April 1993 Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation ML20082P1871991-09-0404 September 1991 Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria ML17157A3371990-09-24024 September 1990 Proposed Tech Specs in Support of Facility Cycle 5 Reload ML17157A2441990-07-0202 July 1990 Proposed Tech Specs to Support Cycle 6 Reload ML19325D7491989-10-19019 October 1989 Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months ML17156B1101989-04-14014 April 1989 Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R ML17156A7291988-08-10010 August 1988 Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc ML18040A8741988-04-0606 April 1988 Proposed Tech Specs Re Radiation Monitoring Instrumentation ML17146B0891987-12-23023 December 1987 Proposed Tech Specs Index & Sections 3/4.2.1,3/4.2.2, 3/4.2.3,3/4.2.4,3/4.3.6,3/4.4.1,B 2.1,B 3/4.2.1,B 3/4.2.2, B 3/4.2.3 & B 3/4.4.1,to Support Cycle 3 Reload ML18040A8421987-06-10010 June 1987 Proposed Tech Specs,Increasing Load Profile for Batteries 1D612 & 1D622 ML18040A8341987-04-16016 April 1987 Proposed Tech Spec 4.1.3.1.4(a) Changing Requirements for Surveillance of Scram Discharge Vol Vent & Drain Valves ML18040A8261987-02-0909 February 1987 Proposed Tech Specs,Allowing Alternate Method of post-accident Drywell Gaseous Sampling & Providing Relief for Unnecessarily Restrictive Action Statement on Drywell Oxygen Analyzer ML20215C1291986-12-0909 December 1986 Proposed Tech Spec Tables 3.6.3-1 & 3.8.4.2-1,supporting Mods to Improve Containment Isolation Function & Testability of Feedwater Sys ML17146A4811986-08-0505 August 1986 Proposed Administrative Changes to Tech Specs ML20206J9471986-06-23023 June 1986 Proposed Tech Specs Changing Main Steam Line Radiation High Setpoint from Three Times Background to Seven Times Background ML17146A4161986-06-19019 June 1986 Proposed Tech Specs Re Cycle 2 Reload.Nshc Encl ML17146A3111986-03-27027 March 1986 Proposed Tech Spec Changes Providing Editorial Correction to Previously Approved Change for Unit 1 & Supporting Mods Which Enhance Capability of Drywell Cooling Sys for Unit 2 ML20141C9281986-03-27027 March 1986 Proposed Tech Specs Re Recirculation Sys W/One & Two Loop Operation,Supporting Operation W/One Recirculation Loop Out of Svc ML17146A2681986-02-10010 February 1986 Proposed Tech Specs,Reflecting Incorporation of Fifth Diesel Generator Into Plant Design ML20137G5781985-11-26026 November 1985 Proposed Tech Specs,Deleting Requirement for Operability of Refueling Floor Wall & High Exhaust Ducts & Railroad Access Exhaust Duct Radiation Monitoring Sys for Conditions 1,2 & 3 ML17156A1261985-04-11011 April 1985 Proposed Tech Spec Changes Re Single Loop Operation Requirement ML18040A7701985-02-11011 February 1985 Proposed Tech Specs Re Util Review Committee Membership ML17139C7431984-12-0606 December 1984 Proposed Tech Specs Separating Unit 1 from Unit 2 Battery Loads to Avoid Forced Shutdown of Unit 2 During Unit 1 Refueling Outage ML18040A7421984-09-24024 September 1984 Proposed Tech Specs,Revising Table 3.3.7.1-1, Radiation Monitoring Instrumentation. ML18040A7411984-09-0707 September 1984 Proposed Tech Specs Re Primary Containment Isolation Valves & Containment Sys Limiting Condition for Operation & Bases ML20078M6531983-10-20020 October 1983 Proposed Changes to Tech Spec Table 4.8.1.1.2-2 Re Settings for Emergency Svc Water Pump Timers ML17139B3301983-02-0303 February 1983 Proposed Tech Specs 2.2.1.1,3.2.2,4.2.2 & 3.3.6-2 Re Reactor Protection Sys Instrumentation,Average Power Range Monitor & Control Rod Block Instrumentation Setpoints ML17139B3311983-02-0303 February 1983 Proposed Tech Specs 3.4.3 & 4.4.3 Re RCS Leakage Detection Sys ML18031A4031982-10-19019 October 1982 Proposed Changes to Tech Spec Table 3.8.4.1-1 to Include More Conservative Type 2 Molded Case Circuit Breakers & to Add Previously Omitted Type 3 Molded Case Circuit Breakers 1999-03-12
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18040B2891999-03-12012 March 1999 Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2 ML18040B2881999-01-12012 January 1999 Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits ML17164A6711998-07-0808 July 1998 Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included ML17159A3261998-05-12012 May 1998 Proposed Tech Specs Re Removal of Fire Protection Program ML20199C8741997-10-22022 October 1997 Rev 0 to NASI-00-507, Corrective Action Process Effectiveness Assessment ML18026A4711997-02-11011 February 1997 Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315 ML17158C0321997-01-0808 January 1997 Rev 4, Solid Radwaste Pcp. ML20129D7851996-09-23023 September 1996 Proposed Tech Specs Re MSIVs Leakage Testing ML20116K3491996-08-0909 August 1996 Proposed Tech Specs Re Battery Load Profiles ML17158B5581996-03-20020 March 1996 Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level ML20115A8211996-02-29029 February 1996 Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers ML20115A8171996-02-29029 February 1996 Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59 ML17158B1071996-02-12012 February 1996 Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program. ML17158A6821995-04-26026 April 1995 Rev 3 to Nuclear Dept Procedure ON-100-009, Control Room Evacuation. ML17158A6841995-04-13013 April 1995 Rev 3 to Nuclear Dept Procedure ON-200-009, Control Room Evacuation. ML20081L9151995-03-14014 March 1995 Rev 1 to NS-ST-002, Security Training & Crucial Security Task Certification ML17164A5801995-02-10010 February 1995 Proposed Tech Specs for Aot/Sti Extensions ML17164A5891995-01-20020 January 1995 Rev 2 to PP&L SSES Odcm. ML17164A4351994-11-21021 November 1994 Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS ML17158A5441994-10-28028 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML20058F8281993-11-24024 November 1993 Proposed Tech Specs Re Power Uprate W/Increased Flow ML17157C3881993-05-31031 May 1993 Rev 8 to ISI-T-100.0, ISI Program Plan for Pump & Valve Operational Testing. ML17157C3901993-05-31031 May 1993 Rev 5 to ISI-T-200.0, ISI Program Plan for Pump & Valve Operational Testing. ML18017A2671993-04-20020 April 1993 Exercise Manual. ML17157C2741993-04-0202 April 1993 Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation ML18017A2631992-05-0606 May 1992 Emergency Exercise Std for Conduct in Performance of 920219 NRC Graded Exercise ML20113G9881992-02-19019 February 1992 Package Providing Basis for Conduct of Simulated Radiological Accident at Plant ML17157B0081991-12-31031 December 1991 Rev 7 to ISI-T-100.0, Sses,Unit 1,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04 ML17157B0101991-12-31031 December 1991 Rev 4 to ISI-T-200.0, Sses,Unit 2,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04 ML18017A2591991-10-16016 October 1991 Exercise Manual, Approved by Util as Std for Conduct in Performance of 911016 NRC Graded Exercise ML20082P1871991-09-0404 September 1991 Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria ML17157A3381990-09-30030 September 1990 Cycle 5 Reload Summary Rept. ML17157A3371990-09-24024 September 1990 Proposed Tech Specs in Support of Facility Cycle 5 Reload ML17157A2441990-07-0202 July 1990 Proposed Tech Specs to Support Cycle 6 Reload ML17157A0891990-03-19019 March 1990 Rev 0 to Procedure MT-024-024, Diesel Engine Analysis & Load Balancing. ML17157A0871990-03-19019 March 1990 Rev 0 to Procedure TP-024-087, Data Collection for E Diesel Generator Combustion Intake Air Temp Test. ML20127B4271990-01-19019 January 1990 Rev 8 to Procedure MT-GE-008, 480 Volt & Under Circuit Breaker High Current Testing ML19325D7491989-10-19019 October 1989 Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months ML20082C4101989-08-16016 August 1989 Spec Change Notice 7 to Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML17156B1101989-04-14014 April 1989 Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R ML17156B0671989-03-31031 March 1989 Rev 3 to ISI-T-200.0, Pump & Valve Inservice Insp Testing Program. ML17156B0651989-03-31031 March 1989 Rev 6 to ISI-T-100.0, Pump & Valve Inservice Insp Testing Program. ML20082C4071989-03-23023 March 1989 Spec Change Notice 6 to Rev 4 to F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML17156B1391989-02-22022 February 1989 Rev 12 to EO-100-009, Plant Shutdown from Outside Control Room. ML20082B2771989-01-0404 January 1989 Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML20082C3731988-11-0707 November 1988 Spec Change Notice 5 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML20082C3711988-11-0101 November 1988 Spec Change Notice 4 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML20082C3641988-10-14014 October 1988 Spec Change Notice 3 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers ML17156A7291988-08-10010 August 1988 Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc ML20082B2911988-07-11011 July 1988 Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers 1999-03-12
[Table view] |
Text
TECHNICAL SPECIFICATION MARKUPS 9304090264 930402 05000387 PDR ADOCK f p PDR
R IR LATI NL P. - IN LEL P PERAT N LIMITIN NDITION F R OPERATION 3.4.1 1.2 One reactor coolant recirculation loop shall be in operation with the pump speed
~
s 80% of the rated pump speed and the reactor at a THERMALPOWER/core flow condition outside of Regions I and II of Figure 3.4.1.1.1-1, and
- a. the following revised specification limits shall be followed:
- 1. Specification 2.1.2: the MCPR Safety Limit shall be increased to 1.07.
- 2. Table 2.2.1-1: the APRM Flow-Biased Scram Trip Setpoints shall be as follows:
4.
0 V
~E =~,;- Trip',Setpoint.~;~"."";-.>-."'P~~~Pr-" .'gj".;~~~'4b:.':'"lAIIowabhi:Value ~-,":,~'",'.
s 0.58W + 54% s 0.58W + 57%
- 3. Specification 3.2.2: the APRM Setpoints shall be as follows:
v 0
""""j~'":"'":""')Trip,'Setpoht~"-""'~"""'i". "'F~': '~4 Z~~'-:"AIIowable'Yah'-';;<i+:.--'"i>>
0 S s (0.58W+ 54%) T S s (0.58W + 57%) T H
Sp s (0.58W + 45%) T S< s (0.58W + 48%) T
~ v
- 4. Specification 3.2.3: The MINIMUMCRITICALPOWER RATIO (MCPR) shall be greater than or equal to the largest of the following values:
I
- a. the MCPR determined from Figure 3.2.3-1 plus 0.01, and I
- b. the MCPR determined from Figure 3.2.3-2, Figure 3.2.3-3, or Figure 3.2.3-4, as appropriate, plus 0.01.
~ ~ ~ ~
CTj g.'g Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as
~
follows:
\
~ v.
Trip Setpoint:. -, ', ",;. 'Allowable Valoe:.'".'-':.'
- a. RBM- Upscale s 0.66W + 36% 0.66W + 39%
Trip Setpoint '..=". ~ -' ;.'-.';-'+;:AIIowibie Vetue~,",',,"'
- << b. APRM- Flow Biased operation.¹ 0.58W + 45%
' '+.
s 0.58W + 48%
d SUSQUEHANNA - UNIT 1 3/4 4-1c Amendment No. 118
RESPONSE TO NRC QUESTIONS REV. 1 RESPONSE TO NRC QUESTIONS REACTOR SYSTH6 BRANCH QUESTION 3 If single loop operation (SLO) yields a higher peak cladding temperature (PCT) than two loop operation, why is the upper bound peak cladding temperature (UBPCT) based on two loop operation applicable for SLO? Does the limiting single failure and break size remain the same for SLO as for two loop operation? Discuss the applicability of SAFER/GESTR for SLO in view of the fact SLO results in a higher PCT.
Operation with one recirculation loop out of service is allowed, but it is not considered a normal mode of operation. SLO is a special operational condition when only one of the two recirculation loops is operable. In this operating condition, the reactor power will be limited to less than 804 of rated by the maximum achievable core flow, which is typically less than 604 of rated core flow. A postulated LOCA occurring in the active recirculation loop during SLO would cause a more rapid coastdown,of the recirculation flow than would occur in two loop operation, where one active loop would remain intact. This rapid coastdown causes an earlier boiling transition time and deeper penetration of boiling transition into the bundle, which tends to increase the calculated PCT. However, the PCT effects of the early boiling transition are substantially offset by the mitigating effect of the lower power level achievable at the start of such an event. The SAFER/GESTR-LOCA analysis results for Susquehanna (NEDC-32071P) for SLO and two loop operation are well below 2200'F.
The ECCS performance for Susquehanna under SLO was evaluated using SAFER/GESTR-LOCA. Calculations for the DBA were performed using both nominal and Appendix K inputs. The SLO SAFER/GESTR-LOCA analysis for the DBA assumes that there is essentially no period of recirculation pump coastdown. Thus, dryout is assumed to occur simultaneously at all axial locations of the hot bundle shortly after initiation of the event. Dryout is assumed to occur in one second for the nominal case and O.l second for the Appendix K case. These assumptions are very conservative and provide bounding results for the DBA under SLO.
The two-loop Appendix K break spectrum documented in NEDC-32071P is representative of SLO because the two-loop spectrum was analyzed assuming a one second dryout time for all axial locations of the hot bundle. As shown by the two-loop break spectrum, the DBA is the limiting case for SLO. In addition, SLO will affect the DBA results more than the smaller breaks. With breaks smaller than the DBA, there is a longer period of nucleate and/or film boiling prior to fuel uncovery to remove the fuel stored energy.
An LHGR reduction (multiplier) of 0.70 will be imposed when the plant is in SLO. As shown in Table 5-6 of NEDC-32701P, the SLO results are less limiting (i.e., lower PCTs) than the results for the two loop DBA LOCA.
Thus, the licensing PCT is based appropriately on two loop operation rather than SLO.
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O Errata and Addenda Sheet Gf'Nvdeer fnerJry
/15 Curler A@eve San Jm. CA 85125 Applicable to:
Publication No. EBA No.
Title Date c 199 Units 1 and 2 SAFER GESTR-LOCA Loss-Of- Note: Correct all copies of the Co lant Accident Anal sis applicable publication as Issue Date specified below.
References lmtrecdaer (Secdaa Pape (Conec0ies aifAdkera)
Pareyapt CkeJ Pages 5-6 and 5-7 Replace with new pages 5-6 and 5-7 Page 5-l3 Replace with new Page 5-13 (change brackets in right hand margin indicate areas where report has been changed)
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