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| {{#Wiki_filter:Attachment IIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnical Specifications IncludedPages:3.3-27B3.3-95*B3.3-96*Thesebasespagesarebeingprovidedforinformation onlytoshowthechangesRG&Eintendstomakefollowing NRCapprovaloftheI.AR.ThebasesareunderRGREcontrolforallchangesinaccordance withSpecification 5.5.13.'P6i03fOi22 9hi029PDRADOCK05000244PDR~l ESFASInstrumentation 3.3.2Table3.3.2-1(page3of3)Engineered SafetyFeatureActuation SystemInstrINIcntation FUNCTIONAPPLICABLE HOOESOROTHERSPECIFIED COHOITIONSREQUIREDCHANNELSSURVEILLANCE ALLOWABLE COHOITIONS REQUIREKENTS VALUETRIPSETPOIHT5.FeedIIater Isolation a.Automatic Actuation LogicandActuation Relays1,2(c)3(c)2trainsE,GSR3.3.2.7NAb.SGMaterLevel-High1,2(c),3( | | {{#Wiki_filter:Attachment II Marked Up Copy of R.E.Ginna Nuclear Power Plant Technical Specifications Included Pages: 3.3-27 B 3.3-95*B 3.3-96*These bases pages are being provided for information only to show the changes RG&E intends to make following NRC approval of the I.AR.The bases are under RGRE control for all changes in accordance with Specification 5.5.13.'P6i03fOi22 9hi029 PDR ADOCK 05000244 PDR~l ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)Engineered Safety Feature Actuation System InstrINIcntation FUNCTION APPLICABLE HOOES OR OTHER SPECIFIED COHO I T IONS REQUIRED CHANNELS SURVEILLANCE ALLOWABLE COHOITIONS REQUIREKENTS VALUE TRIP SETPOIHT 5.FeedIIater Isolation a.Automatic Actuation Logic and Actuation Relays 1,2(c)3(c)2 trains E,G SR 3.3.2.7 NA b.SG Mater Level-High 1,2(c),3()3 per SG F,G SR 3.3.2.1 s 94X SR 3.3.2.2 SR 3.3.2.5 s 85X c.Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. |
| )3perSGF,GSR3.3.2.1s94XSR3.3.2.2SR3.3.2.5s85Xc.SafetyInjection RefertoFunction1(SafetyInjection) forallinitiation functions andrequirements. | | 6.Auxiliary FeedIIatcr (AF'W)a.Hanual Initiation AFW Standby AFM 1,2,3 1,2,3 1 per pump 1 pcr pump SR 3.3.2.4 SR 3.3.2.4 HA NA NA b.Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains E,G SR 3.3.2.7 c.SG Mater Level-Lou Lou 1,2,3 F 3 per SG~G SR 3.3.2~1 2 16X SR 3.3.2.2 SR 3.3.2.5 z 17X d.Safety Injection (Hotor driven pImps only)Refer to Function 1 (Safety Injection) for all initiation functions and requirements. |
| 6.Auxiliary FeedIIatcr (AF'W)a.HanualInitiation AFWStandbyAFM1,2,31,2,31perpump1pcrpumpSR3.3.2.4SR3.3.2.4HANANAb.Automatic Actuation LogicandActuation Relays1,2,32trainsE,GSR3.3.2.7c.SGMaterLevel-LouLou1,2,3F3perSG~GSR3.3.2~1216XSR3.3.2.2SR3.3.2.5z17Xd.SafetyInjection (HotordrivenpImpsonly)RefertoFunction1(SafetyInjection) forallinitiation functions andrequirements. | | e.Undervoltagc-Bus 11A and 11B (Turbine driven punp only)1,2,3 2 pcI'us D,G SR 3.3.2.3 SR 3.3.2.5~2450 V~2579 V uith s 3.6 with s 3.6 sec time sec time delay delay f.Trip of Both Hain FeedIIater PImps (Hotor driven pumps only)1,2 2 pcl HFM pump B,C SR 3.3.2.4 HA (c)Except IIhen all Hain FecdIIatcr Regulating and associated bypass valves are closed and dc-activated or isolated by a closed manual valve.R.E.Ginna Nuclear Power Plant 3.3-27 Amendment No.Q, 63 ESFAS Instrumentation B 3.3.2 BASES ACTIONS (continued) |
| e.Undervoltagc | | D.l Condition 0 applies to the following ESFAS Functions: |
| -Bus11Aand11B(Turbinedrivenpunponly)1,2,32pcI'usD,GSR3.3.2.3SR3.3.2.5~2450V~2579Vuiths3.6withs3.6sectimesectimedelaydelayf.TripofBothHainFeedIIater PImps(Hotordrivenpumpsonly)1,22pclHFMpumpB,CSR3.3.2.4HA(c)ExceptIIhenallHainFecdIIatcr Regulating andassociated bypassvalvesareclosedanddc-activated orisolatedbyaclosedmanualvalve.R.E.GinnaNuclearPowerPlant3.3-27Amendment No.Q,63 ESFASInstrumentation B3.3.2BASESACTIONS(continued) | | ~Manual Initiation of SI;~Hanual Initiation of Steam Line Isolation; n~AFW-Undervoltage |
| D.lCondition 0appliestothefollowing ESFASFunctions: | | -Bus 11A and llB.If a channel is inoperable, 48 hours is allowed to restore it to OPERABLE status.The specified Completion Time of 48 hours is reasonable considering that there are two automatic actuation trains and another manual initiation channel OPERABLE for each manual initiation, Fun'ction additional AFW actuation channels available besides the Undervoltage |
| ~ManualInitiation ofSI;~HanualInitiation ofSteamLineIsolation; n~AFW-Undervoltage | | -Bus 11A and 118 AFW Initiation unctions, and the low probability of an event occurring during this interval.E.1 Condition E applies to the automatic actuation logic and actuation relays for the following ESFAS Functions: |
| -Bus11AandllB.Ifachannelisinoperable, 48hoursisallowedtorestoreittoOPERABLEstatus.Thespecified Completion Timeof48hoursisreasonable considering thattherearetwoautomatic actuation trainsandanothermanualinitiation channelOPERABLEforeachmanualinitiation, Fun'ction additional AFWactuation channelsavailable besidestheUndervoltage | | ~Steam Line Isolation; |
| -Bus11Aand118AFWInitiation | | ~Feedwater Isolation; and~AFW.Condition E addresses the train orientation of the protection system and the master and slave relays.If one train is inoperable, a Completion Time of 6 hours is allowed to restore the train to OPERABLE status.This Completion Time is reasonable considering that there is another train OPERABLE, and the low probability of an event occurring during this time interval.The Completion Time of 6 hours is consistent with Reference 7.(continued) |
| : unctions, andthelowprobability ofaneventoccurring duringthisinterval.
| | R.E.Ginna Nuclear Power Plant B 3.3-95 Revision 0 ESFAS Instrumentation B 3.3.2 BASES ACTIONS (continued) |
| E.1Condition Eappliestotheautomatic actuation logicandactuation relaysforthefollowing ESFASFunctions: | | F.1 Condition F applies to the following Functions: |
| ~SteamLineIsolation; | | ~Steam Line Isolation-Containment Pressure-High High;~Steam Line Isolation-High Steam Flow Coincident With Safety Injection and Coincident With T.,-Low;~Steam Line Isolation-High-High Steam Flow Coincident With Safety Injection; n~Feedwater Isolation-SG Water Level-High, Condition F applies to Functions that typically operate on two-out-of-three logic.Therefore, failure of one channel places the Function in a two-out-of-two configuration. |
| ~Feedwater Isolation; and~AFW.Condition Eaddresses thetrainorientation oftheprotection systemandthemasterandslaverelays.Ifonetrainisinoperable, aCompletion Timeof6hoursisallowedtorestorethetraintoOPERABLEstatus.ThisCompletion Timeisreasonable considering thatthereisanothertrainOPERABLE, andthelowprobability ofaneventoccurring duringthistimeinterval. | | One channel must be tripped to place the Function in a one-out-of-two configuration that satisfies redundancy requirements. |
| TheCompletion Timeof6hoursisconsistent withReference 7.(continued)
| | If one channel is inoperable, a Completion Time of 6 hours is allowed to restore the channel to OPERABLE status or to place it in the tripped condition. |
| R.E.GinnaNuclearPowerPlantB3.3-95Revision0 ESFASInstrumentation B3.3.2BASESACTIONS(continued) | | Placing the channel in the tripped condition conservatively compensates for the inoperability, restores capability to accommodate a single failure, and allows operation to continue.The Required Actions are modified by a Note that allows the inoperable channel to be bypassed for up to 4 hours for surveillance testing of other channels.This 4 hours applies to each of the remaining OPERABLE channels.The Completion Time of 6 hours allowed to restore the channel to OPERABLE status or to place the inoperable channel in the tripped condition, and the 4 hour s allowed for testing, are justified in Reference 7.(continued) |
| F.1Condition Fappliestothefollowing Functions: | | R.E.Ginna Nuclear Power Plant 8 3.3-96 Revision 0 h |
| ~SteamLineIsolation | | Attachment III Proposed Technical Specifications Included Pages: 3.3-27 0 ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE ALLOMABLE TRIP COND IT IOHS REQUIREMENTS VALUE SETPOINT 5.Feedwater Isolation a.Automatic Actuation Logic and Actuation Relays 1,2 3 2 trains E,G SR 3.3.2.7 HA NA b.SG Mater Level-High 1i2(c)3(c)3 per SG FiG SR 3 3 2 1 i 947, SR 3.3'.2 SR 3.3.2.5 s 85K c.Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. |
| -Containment Pressure-HighHigh;~SteamLineIsolation | | 6.Auxiliary Feedwater (AFM)a.Manual Initiation AFM Standby AFM 1,2,3 1,2,3 1 per pwp 1 pcl'R 3.3.2.4 SR 3.3.2.4 NA HA b.Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains E,G SR 3.3.2.7 NA c.SG Mater Level-Low Low 1,2,3 3 per SG F,G'R 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 a 16'17X d.Safety Injection (Motor driven pumps only)Refer to Function 1 (Safety Injection) for all initiation functions and requirements. |
| -HighSteamFlowCoincident WithSafetyInjection andCoincident WithT.,-Low;~SteamLineIsolation | | e.Under vol tage-Bus 11A and 11B (Turbine driven pump only)1,2,3 2 per bus D,G SR 3.3.2.3?2450 V a 2579 V with s 3.6 with s 3.6 sec time sec time delay delay f.Trip of Both Main Feedwater Pumps (Motor driven pumps only)1,2 2 per MFM punp B,C SR 3.3.2.4 HA NA (c)Except when all Main Feedwater Regulating and associated bypass valves are closed and de-activated or isolated by a closed manual valve.R.E.Ginna Nuclear Power Plant 3.3-27 Amendment No.g, Q Attachment IV NUREG-1431 Included pages: 3.3-24 3.3-37 O ESFAS Instrumentation 3.3.2 ACTIONS continued CONDITION REQUIRED ACTION COMPLETION TIME C.One train inoperable. |
| -High-HighSteamFlowCoincident WithSafetyInjection; n~Feedwater Isolation | | C.l----NOTE-----One train may be bypassed for up to[4]hours for surveillance testing provided the other train is OPERABLE.OR Restore train to OPERABLE status.6 hours C.2.1 Be in MODE 3.AND C.2.2 Be in MODE 5.12 hours 42 hours D.One channel inoperable. |
| -SGWaterLevel-High,Condition FappliestoFunctions thattypically operateontwo-out-of-three logic.Therefore, failureofonechannelplacestheFunctioninatwo-out-of-two configuration. | | S~a.t+<~~%, C4+ui~cL~prov 0.1----NOTE-----The inoperable channel may be bypassed for up to[4]hours for.surveillance testing of other channels.OR Place channel in trip.6 hours+<M&cl Qt+g~$~@+a~G.h~k G.W D.2.1 Be in MODE 3.AND 0.2.2 Be in MODE 4.12 hours 18 hour (continued) |
| OnechannelmustbetrippedtoplacetheFunctioninaone-out-of-two configuration thatsatisfies redundancy requirements.
| | WOG STS 3.3-24 Rev 1, 04/07/95 |
| Ifonechannelisinoperable, aCompletion Timeof6hoursisallowedtorestorethechanneltoOPERABLEstatusortoplaceitinthetrippedcondition.
| | ~-s~ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 8)Engineered Safety Feature Actuation System Instruncntation RNCT I ON APPLICABLE KCOES OR OTHER SPECIFIED CONDITIONS REOUI RED CHANNELS SURVEILLANCE ALLOMABLE CONDI'TIOHS REQUIREKENTS VALUE TRIP SETPOIHT<'> |
| Placingthechannelinthetrippedcondition conservatively compensates fortheinoperability, restorescapability toaccommodate asinglefailure,andallowsoperation tocontinue.
| | 5.Turbine Trip and Feedwater Isolation a.Automatic Actuation Logic and Actuation Relays 1 2(j)[3)(j)2 trains H[G]SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA b.SG Mater Level-High Nigh (P-14)1,2<j>,[3)<j)[3]per SG 1[D)'R 3.3.2.1<[84.2]X SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10[82.4)X'.Safety Injection Refer to Fmction 1 (Safety Injection) for all initiation functions and requirements. |
| TheRequiredActionsaremodifiedbyaNotethatallowstheinoperable channeltobebypassedforupto4hoursforsurveillance testingofotherchannels.
| | 6.Auxiliary Feedwater a.Automatic Actuation Logic and Actuation Relays (Solid State Protection System)1,2,3 2 trains SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 b.Automatic Actuation Logic and Actuation Relays (Balance of Plant ESFAS)1,2,3 2 trains SR 3.3.2-3 NA Z~cled (i<v me~ACkdA C,'.~c.SG Mater Level-Low Low 1,2,3[3]per SG SR 3.3-2.1>[30.4)X I Q2.2]X SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.1D (continued)(a)Reviewer's Note: Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit.(j)Except when all KFIVs, KFRVs,[and associated bypass valves)are closed and[de-activated] |
| This4hoursappliestoeachoftheremaining OPERABLEchannels.
| | [or isolated by a closed manual valve].WOG STS 3~3 37 Rev 1, 04/07/95 0 E T J}} |
| TheCompletion Timeof6hoursallowedtorestorethechanneltoOPERABLEstatusortoplacetheinoperable channelinthetrippedcondition, andthe4hoursallowedfortesting,arejustified inReference 7.(continued)
| |
| R.E.GinnaNuclearPowerPlant83.3-96Revision0 h | |
| Attachment IIIProposedTechnical Specifications IncludedPages:3.3-27 0ESFASInstrumentation 3.3.2Table3.3.2-1(page3of3)Engineered SafetyFeatureActuation SystemInstrumentation FUNCTIONAPPLICABLE MODESOROTHERSPECIFIED CONDITIONS REQUIREDCHANNELSSURVEILLANCE ALLOMABLE TRIPCONDITIOHSREQUIREMENTS VALUESETPOINT5.Feedwater Isolation a.Automatic Actuation LogicandActuation Relays1,232trainsE,GSR3.3.2.7HANAb.SGMaterLevel-High1i2(c)3(c)3perSGFiGSR3321i947,SR3.3'.2SR3.3.2.5s85Kc.SafetyInjection RefertoFunction1(SafetyInjection) forallinitiation functions andrequirements. | |
| 6.Auxiliary Feedwater (AFM)a.ManualInitiation AFMStandbyAFM1,2,31,2,31perpwp1pcl'R3.3.2.4SR3.3.2.4NAHAb.Automatic Actuation LogicandActuation Relays1,2,32trainsE,GSR3.3.2.7NAc.SGMaterLevel-LowLow1,2,33perSGF,G'R3.3.2.1SR3.3.2.2SR3.3.2.5a16'17Xd.SafetyInjection (Motordrivenpumpsonly)RefertoFunction1(SafetyInjection) forallinitiation functions andrequirements. | |
| e.Undervoltage-Bus11Aand11B(Turbinedrivenpumponly)1,2,32perbusD,GSR3.3.2.3?2450Va2579Vwiths3.6withs3.6sectimesectimedelaydelayf.TripofBothMainFeedwater Pumps(Motordrivenpumpsonly)1,22perMFMpunpB,CSR3.3.2.4HANA(c)ExceptwhenallMainFeedwater Regulating andassociated bypassvalvesareclosedandde-activated orisolatedbyaclosedmanualvalve.R.E.GinnaNuclearPowerPlant3.3-27Amendment No.g,Q Attachment IVNUREG-1431 Includedpages:3.3-243.3-37 OESFASInstrumentation 3.3.2ACTIONScontinued CONDITION REQUIREDACTIONCOMPLETION TIMEC.Onetraininoperable. | |
| C.l----NOTE-----Onetrainmaybebypassedforupto[4]hoursforsurveillance testingprovidedtheothertrainisOPERABLE. | |
| ORRestoretraintoOPERABLEstatus.6hoursC.2.1BeinMODE3.ANDC.2.2BeinMODE5.12hours42hoursD.Onechannelinoperable.
| |
| S~a.t+<~~%,C4+ui~cL~prov0.1----NOTE-----Theinoperable channelmaybebypassedforupto[4]hoursfor.surveillance testingofotherchannels. | |
| ORPlacechannelintrip.6hours+<M&clQt+g~$~@+a~G.h~kG.WD.2.1BeinMODE3.AND0.2.2BeinMODE4.12hours18hour(continued)
| |
| WOGSTS3.3-24Rev1,04/07/95
| |
| ~-s~ESFASInstrumentation 3.3.2Table3.3.2-1(page6of8)Engineered SafetyFeatureActuation SystemInstruncntation RNCTIONAPPLICABLE KCOESOROTHERSPECIFIED CONDITIONS REOUIREDCHANNELSSURVEILLANCE ALLOMABLE CONDI'TIOHS REQUIREKENTS VALUETRIPSETPOIHT<'> | |
| 5.TurbineTripandFeedwater Isolation a.Automatic Actuation LogicandActuation Relays12(j)[3)(j)2trainsH[G]SR3.3.2.2SR3.3.2.4SR3.3.2.6NAb.SGMaterLevel-HighNigh(P-14)1,2<j>,[3)<j)[3]perSG1[D)'R3.3.2.1<[84.2]XSR3.3.2.5SR3.3.2.9SR3.3.2.10[82.4)X'.SafetyInjection RefertoFmction1(SafetyInjection) forallinitiation functions andrequirements. | |
| 6.Auxiliary Feedwater a.Automatic Actuation LogicandActuation Relays(SolidStateProtection System)1,2,32trainsSR3.3.2.2SR3.3.2.4SR3.3.2.6b.Automatic Actuation LogicandActuation Relays(BalanceofPlantESFAS)1,2,32trainsSR3.3.2-3NAZ~cled(i<vme~ACkdAC,'.~c.SGMaterLevel-LowLow1,2,3[3]perSGSR3.3-2.1>[30.4)XIQ2.2]XSR3.3.2.5SR3.3.2.9SR3.3.2.1D(continued) | |
| (a)Reviewer's Note:Unitspecificimplementations maycontainonlyAllowable Valuedepending onSetpointStudymethodology usedbytheunit.(j)ExceptwhenallKFIVs,KFRVs,[andassociated bypassvalves)areclosedand[de-activated] | |
| [orisolatedbyaclosedmanualvalve].WOGSTS3~337Rev1,04/07/95 0ETJ}} | |
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ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML17265A4661998-11-24024 November 1998 Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising 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 Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements 1999-06-28
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Attachment II Marked Up Copy of R.E.Ginna Nuclear Power Plant Technical Specifications Included Pages: 3.3-27 B 3.3-95*B 3.3-96*These bases pages are being provided for information only to show the changes RG&E intends to make following NRC approval of the I.AR.The bases are under RGRE control for all changes in accordance with Specification 5.5.13.'P6i03fOi22 9hi029 PDR ADOCK 05000244 PDR~l ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)Engineered Safety Feature Actuation System InstrINIcntation FUNCTION APPLICABLE HOOES OR OTHER SPECIFIED COHO I T IONS REQUIRED CHANNELS SURVEILLANCE ALLOWABLE COHOITIONS REQUIREKENTS VALUE TRIP SETPOIHT 5.FeedIIater Isolation a.Automatic Actuation Logic and Actuation Relays 1,2(c)3(c)2 trains E,G SR 3.3.2.7 NA b.SG Mater Level-High 1,2(c),3()3 per SG F,G SR 3.3.2.1 s 94X SR 3.3.2.2 SR 3.3.2.5 s 85X c.Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
6.Auxiliary FeedIIatcr (AF'W)a.Hanual Initiation AFW Standby AFM 1,2,3 1,2,3 1 per pump 1 pcr pump SR 3.3.2.4 SR 3.3.2.4 HA NA NA b.Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains E,G SR 3.3.2.7 c.SG Mater Level-Lou Lou 1,2,3 F 3 per SG~G SR 3.3.2~1 2 16X SR 3.3.2.2 SR 3.3.2.5 z 17X d.Safety Injection (Hotor driven pImps only)Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
e.Undervoltagc-Bus 11A and 11B (Turbine driven punp only)1,2,3 2 pcI'us D,G SR 3.3.2.3 SR 3.3.2.5~2450 V~2579 V uith s 3.6 with s 3.6 sec time sec time delay delay f.Trip of Both Hain FeedIIater PImps (Hotor driven pumps only)1,2 2 pcl HFM pump B,C SR 3.3.2.4 HA (c)Except IIhen all Hain FecdIIatcr Regulating and associated bypass valves are closed and dc-activated or isolated by a closed manual valve.R.E.Ginna Nuclear Power Plant 3.3-27 Amendment No.Q, 63 ESFAS Instrumentation B 3.3.2 BASES ACTIONS (continued)
D.l Condition 0 applies to the following ESFAS Functions:
~Manual Initiation of SI;~Hanual Initiation of Steam Line Isolation; n~AFW-Undervoltage
-Bus 11A and llB.If a channel is inoperable, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allowed to restore it to OPERABLE status.The specified Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is reasonable considering that there are two automatic actuation trains and another manual initiation channel OPERABLE for each manual initiation, Fun'ction additional AFW actuation channels available besides the Undervoltage
-Bus 11A and 118 AFW Initiation unctions, and the low probability of an event occurring during this interval.E.1 Condition E applies to the automatic actuation logic and actuation relays for the following ESFAS Functions:
~Steam Line Isolation;
~Feedwater Isolation; and~AFW.Condition E addresses the train orientation of the protection system and the master and slave relays.If one train is inoperable, a Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed to restore the train to OPERABLE status.This Completion Time is reasonable considering that there is another train OPERABLE, and the low probability of an event occurring during this time interval.The Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is consistent with Reference 7.(continued)
R.E.Ginna Nuclear Power Plant B 3.3-95 Revision 0 ESFAS Instrumentation B 3.3.2 BASES ACTIONS (continued)
F.1 Condition F applies to the following Functions:
~Steam Line Isolation-Containment Pressure-High High;~Steam Line Isolation-High Steam Flow Coincident With Safety Injection and Coincident With T.,-Low;~Steam Line Isolation-High-High Steam Flow Coincident With Safety Injection; n~Feedwater Isolation-SG Water Level-High, Condition F applies to Functions that typically operate on two-out-of-three logic.Therefore, failure of one channel places the Function in a two-out-of-two configuration.
One channel must be tripped to place the Function in a one-out-of-two configuration that satisfies redundancy requirements.
If one channel is inoperable, a Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is allowed to restore the channel to OPERABLE status or to place it in the tripped condition.
Placing the channel in the tripped condition conservatively compensates for the inoperability, restores capability to accommodate a single failure, and allows operation to continue.The Required Actions are modified by a Note that allows the inoperable channel to be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.This 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> applies to each of the remaining OPERABLE channels.The Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowed to restore the channel to OPERABLE status or to place the inoperable channel in the tripped condition, and the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> s allowed for testing, are justified in Reference 7.(continued)
R.E.Ginna Nuclear Power Plant 8 3.3-96 Revision 0 h
Attachment III Proposed Technical Specifications Included Pages: 3.3-27 0 ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 3)Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE ALLOMABLE TRIP COND IT IOHS REQUIREMENTS VALUE SETPOINT 5.Feedwater Isolation a.Automatic Actuation Logic and Actuation Relays 1,2 3 2 trains E,G SR 3.3.2.7 HA NA b.SG Mater Level-High 1i2(c)3(c)3 per SG FiG SR 3 3 2 1 i 947, SR 3.3'.2 SR 3.3.2.5 s 85K c.Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
6.Auxiliary Feedwater (AFM)a.Manual Initiation AFM Standby AFM 1,2,3 1,2,3 1 per pwp 1 pcl'R 3.3.2.4 SR 3.3.2.4 NA HA b.Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains E,G SR 3.3.2.7 NA c.SG Mater Level-Low Low 1,2,3 3 per SG F,G'R 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 a 16'17X d.Safety Injection (Motor driven pumps only)Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
e.Under vol tage-Bus 11A and 11B (Turbine driven pump only)1,2,3 2 per bus D,G SR 3.3.2.3?2450 V a 2579 V with s 3.6 with s 3.6 sec time sec time delay delay f.Trip of Both Main Feedwater Pumps (Motor driven pumps only)1,2 2 per MFM punp B,C SR 3.3.2.4 HA NA (c)Except when all Main Feedwater Regulating and associated bypass valves are closed and de-activated or isolated by a closed manual valve.R.E.Ginna Nuclear Power Plant 3.3-27 Amendment No.g, Q Attachment IV NUREG-1431 Included pages: 3.3-24 3.3-37 O ESFAS Instrumentation 3.3.2 ACTIONS continued CONDITION REQUIRED ACTION COMPLETION TIME C.One train inoperable.
C.l----NOTE-----One train may be bypassed for up to[4]hours for surveillance testing provided the other train is OPERABLE.OR Restore train to OPERABLE status.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.2.1 Be in MODE 3.AND C.2.2 Be in MODE 5.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 42 hours D.One channel inoperable.
S~a.t+<~~%, C4+ui~cL~prov 0.1----NOTE-----The inoperable channel may be bypassed for up to[4]hours for.surveillance testing of other channels.OR Place channel in trip.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s+<M&cl Qt+g~$~@+a~G.h~k G.W D.2.1 Be in MODE 3.AND 0.2.2 Be in MODE 4.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 18 hour (continued)
WOG STS 3.3-24 Rev 1, 04/07/95
~-s~ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 8)Engineered Safety Feature Actuation System Instruncntation RNCT I ON APPLICABLE KCOES OR OTHER SPECIFIED CONDITIONS REOUI RED CHANNELS SURVEILLANCE ALLOMABLE CONDI'TIOHS REQUIREKENTS VALUE TRIP SETPOIHT<'>
5.Turbine Trip and Feedwater Isolation a.Automatic Actuation Logic and Actuation Relays 1 2(j)[3)(j)2 trains H[G]SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA b.SG Mater Level-High Nigh (P-14)1,2<j>,[3)<j)[3]per SG 1[D)'R 3.3.2.1<[84.2]X SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.10[82.4)X'.Safety Injection Refer to Fmction 1 (Safety Injection) for all initiation functions and requirements.
6.Auxiliary Feedwater a.Automatic Actuation Logic and Actuation Relays (Solid State Protection System)1,2,3 2 trains SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 b.Automatic Actuation Logic and Actuation Relays (Balance of Plant ESFAS)1,2,3 2 trains SR 3.3.2-3 NA Z~cled (i<v me~ACkdA C,'.~c.SG Mater Level-Low Low 1,2,3[3]per SG SR 3.3-2.1>[30.4)X I Q2.2]X SR 3.3.2.5 SR 3.3.2.9 SR 3.3.2.1D (continued)(a)Reviewer's Note: Unit specific implementations may contain only Allowable Value depending on Setpoint Study methodology used by the unit.(j)Except when all KFIVs, KFRVs,[and associated bypass valves)are closed and[de-activated]
[or isolated by a closed manual valve].WOG STS 3~3 37 Rev 1, 04/07/95 0 E T J