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| {{#Wiki_filter:Attachment ARevisetheTechnical Specification pagesasfollows:RemoveInsertpage3.5-15page4.1-7page3.5-15page4.1-7"9710010029 06000~4487092+PDR~DGC~PDRgj,p | | {{#Wiki_filter:Attachment A Revise the Technical Specification pages as follows: Remove Insert page 3.5-15 page 4.1-7 page 3.5-15 page 4.1-7"9710010029 06000~44 87092+PDR~DGC~PDR gj, p |
| 'k TABLE3.5-4AccidentMonitorin Instrumentation TOTAIREQUIREDNO.OFCHANNELS(7)MINIMUMCHANNELSOPERABLE(7)1.Pressurizer WaterLevel(1)2.Auxiliary Feedwater FlowRate(2)(3)3.SteamGenerator WaterLevel-WideRange(3)2/steamgenerator 1/steamgenerator 1/steamgenerator 1/steamgenerator 4.ReactorCoolantSystemSubcooling MarginMonitor(4)5.Pressurizer PORVPositionindicator (5)6.PORVBlockValvePositionIndicator (1)7.Pressurizer SafetyValvePositionIndicator (5)2/Valve1/Valve2/Valve1/Valve0/Valve1/Valve8.Containment Pressure(8)9.Containment WaterLevel(NarrowRange,SumpA)1(6)1(6)10.Containment WaterIevel(WideRange,SumpB)ll.Core-Exit Thermocouples 12.ReactorVesselLevelIndication System4/corequadrant2/corequadrantNotes(1)Emergency powerforpressurizer equipment, NUREG-0737, itemII.G.l.(2)'3)Auxiliary feedwater systemflowindication, NUREG-0737, itemII.E.1.2. | | 'k TABLE 3.5-4 Accident Monitorin Instrumentation TOTAI REQUIRED NO.OF CHANNELS (7)MINIMUM CHANNELS OPERABLE (7)1.Pressurizer Water Level (1)2.Auxiliary Feedwater Flow Rate (2)(3)3.Steam Generator Water Level-Wide Range (3)2/steam generator 1/steam generator 1/steam generator 1/steam generator 4.Reactor Coolant System Subcooling Margin Monitor (4)5.Pressurizer PORV Position indicator (5)6.PORV Block Valve Position Indicator (1)7.Pressurizer Safety Valve Position Indicator (5)2/Valve 1/Valve 2/Valve 1/Valve 0/Valve 1/Valve 8.Containment Pressure (8)9.Containment Water Level (Narrow Range, Sump A)1(6)1(6)10.Containment Water Ievel (Wide Range, Sump B)ll.Core-Exit Thermocouples 12.Reactor Vessel Level Indication System 4/core quadrant 2/core quadrant Notes (1)Emergency power for pressurizer equipment, NUREG-0737, item II.G.l.(2)'3)Auxiliary feedwater system flow indication, NUREG-0737, item II.E.1.2.Only 2 out of the 3 indications (two steam generator auxiliary feedwater flow and one wide-range steam generator level)are required to be operable, NUREG-0737, item II.E.1.2.(4)Instrumentation for detection of inadequate core cooling, NUREG-0737, item II.'F.2.1. |
| Only2outofthe3indications (twosteamgenerator auxiliary feedwater flowandonewide-range steamgenerator level)arerequiredtobeoperable, NUREG-0737, itemII.E.1.2.
| | (5)Direct indication of relief and safety valve position, NUREG-0737, item II.D.3.Two channels include a primary detector and RTD as the backup detector.(6)Operation may continue with less than the minimum channels operable provided that the requirements of Technical Specification 3.1.5.1 are met.(7)See Specification 3.5.2 for required action.(8)Containment pressure monitor, NUREG-0737, item II.F.1.4.3s5)5 Proposed II Channel Descri tion TABLE 4.1-1'CONTINUED) |
| (4)Instrumentation fordetection ofinadequate corecooling,NUREG-0737, itemII.'F.2.1. | | Check Calibrate Test Remarks 25.Containment Pressure 26.Steam Generator Pressure S 27.Turbine First Stage Pressure S M Narrow range containment pressure (-3.0,+3 psig)excluded 28.Emergency Plan Radiation Instruments 29.j 30.I Environmental Monitors Loss of Voltage/Degraded Voltage 480 Volt Safeguards Bus NA NA NA 31.Trip of Main Feedwater Pumps NA 32.Steam Flow AVG NA R 34.Chlorine Detector, Control NA Room Air Intake 35.0 36.Ammonia Detector, Control Room Air Intake NA Radiation Detectors, Control NA Room Air Intake 37.Reactor Vessel Level Indication System NA Attachment B The Reactor Vessel Z,evel Indication (RVZ,IS)was installed during the Spring 1986 refueling outage.A description of the RVLIS and plans for implementing revised Emergency Operating Procedures have previously been provided to the NRC in letters dated December 22, 1986, March 18, 1987 and September 18, 1987.The RVLIS is being incorporated into the Ginna Technical Specifications to satisfy a NUREG-0737 requirement transmitted by a D.G.Eisenhut letter dated November 1, 1983.This letter provided"Model Technical Specifications" to be incorporated for the RVLIS.The proposed RVZ IS technical specifications are identical'to the model specifications except they have been modified to fit the Ginna format.The detailed changes are listed on Table 1.In accordance with 10CFR 50.91, this change to the Technical Specifications has been evaluated against, three criteria to determine if the operation of the facility in accordance with the proposed amendement would: l.Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.Create the possibility of a new or different kind of accident previously evaluated; or 3.Involve a significant reduction in margin of safety.The proposed changes do not,involve a significant'hange-in the probability of an accident previously evaluated because RVLIS is an instrument system involving small connections (3/8 inch)to the reactor coolant system.The RVLIS provides no automatic actuation on control functions and therefore will not.impact the probability of previously analyzed accidents. |
| (5)Directindication ofreliefandsafetyvalveposition, NUREG-0737, itemII.D.3.TwochannelsincludeaprimarydetectorandRTDasthebackupdetector. | | Incorporation of the RVLIS into Technical Specifications may decrease the consequences of certain accidents by implementing instrumentation designed to detect'an'd aid in the response to inadequate core cooling.The proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated because the changes involve only specifying operability and surveillance requirements of the RVLIS.The proposed changes do not involve a significant reduction in margin of safety because specifying operability and surveill-ance requirements, in fact, increase safety margins by providing additional information useful to plant operators in responding to transient events and accidents. |
| (6)Operation maycontinuewithlessthantheminimumchannelsoperableprovidedthattherequirements ofTechnical Specification 3.1.5.1aremet.(7)SeeSpecification 3.5.2forrequiredaction.(8)Containment pressuremonitor,NUREG-0737, itemII.F.1.4. | | 1 e~II Therefore, Rochester Gas and Electric submits that the issues associated with this amendment. |
| 3s5)5Proposed II ChannelDescritionTABLE4.1-1'CONTINUED) | | request are outside the criteria of 10CFR50.91 and a no significant hazards finding is warranted. |
| CheckCalibrate TestRemarks25.Containment Pressure26.SteamGenerator PressureS27.TurbineFirstStagePressureSMNarrowrangecontainment pressure(-3.0,+3psig)excluded28.Emergency PlanRadiation Instruments 29.j30.IEnvironmental MonitorsLossofVoltage/Degraded Voltage480VoltSafeguards BusNANANA31.TripofMainFeedwater PumpsNA32.SteamFlowAVGNAR34.ChlorineDetector, ControlNARoomAirIntake35.036.AmmoniaDetector, ControlRoomAirIntakeNARadiation Detectors, ControlNARoomAirIntake37.ReactorVesselLevelIndication SystemNA Attachment BTheReactorVesselZ,evelIndication (RVZ,IS)wasinstalled duringtheSpring1986refueling outage.Adescription oftheRVLISandplansforimplementing revisedEmergency Operating Procedures havepreviously beenprovidedtotheNRCinlettersdatedDecember22,1986,March18,1987andSeptember 18,1987.TheRVLISisbeingincorporated intotheGinnaTechnical Specifications tosatisfyaNUREG-0737 requirement transmitted byaD.G.EisenhutletterdatedNovember1,1983.Thisletterprovided"ModelTechnical Specifications" tobeincorporated fortheRVLIS.TheproposedRVZIStechnical specifications areidentical
| |
| 'tothemodelspecifications excepttheyhavebeenmodifiedtofittheGinnaformat.ThedetailedchangesarelistedonTable1.Inaccordance with10CFR50.91,thischangetotheTechnical Specifications hasbeenevaluated against,threecriteriatodetermine iftheoperation ofthefacilityinaccordance withtheproposedamendement would:l.Involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or2.Createthepossibility ofanewordifferent kindofaccidentpreviously evaluated; or3.Involveasignificant reduction inmarginofsafety.Theproposedchangesdonot,involve asignificant'hange | |
| -intheprobability ofanaccidentpreviously evaluated becauseRVLISisaninstrument systeminvolving smallconnections (3/8inch)tothereactorcoolantsystem.TheRVLISprovidesnoautomatic actuation oncontrolfunctions andtherefore willnot.impacttheprobability ofpreviously analyzedaccidents. | |
| Incorporation oftheRVLISintoTechnical Specifications maydecreasetheconsequences ofcertainaccidents byimplementing instrumentation designedtodetect'an'daidintheresponsetoinadequate corecooling.Theproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanypreviously evaluated becausethechangesinvolveonlyspecifying operability andsurveillance requirements oftheRVLIS.Theproposedchangesdonotinvolveasignificant reduction inmarginofsafetybecausespecifying operability andsurveill-ancerequirements, infact,increasesafetymarginsbyproviding additional information usefultoplantoperators inresponding totransient eventsandaccidents. | |
| 1e~II Therefore, Rochester GasandElectricsubmitsthattheissuesassociated withthisamendment.
| |
| requestareoutsidethecriteriaof10CFR50.91 andanosignificant hazardsfindingiswarranted.
| |
| ~~ | | ~~ |
| Table1DetailedTechnical Specification ChangesLocationpp3.5-15pp4.1-7DescritionofChaneaddeditem12addeditem37ReasonforChaneNUREG-0737 requirement NUREG-0737 requirement}}
| | Table 1 Detailed Technical Specification Changes Location pp 3.5-15 pp 4.1-7 Descri tion of Chan e added item 12 added item 37 Reason for Chan e NUREG-0737 requirement NUREG-0737 requirement}} |
Proposed Tech Specs Incorporating Requirements for Reactor Vessel Level Indication Sys| ML17261A624 |
| Person / Time |
|---|
| Site: |
Ginna  |
|---|
| Issue date: |
09/24/1987 |
|---|
| From: |
ROCHESTER GAS & ELECTRIC CORP. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML17261A621 |
List: |
|---|
| References |
|---|
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-2.E.1.2, TASK-2.F.1, TASK-2.F.2, TASK-2.G.1, TASK-TM NUDOCS 8710010029 |
| Download: ML17261A624 (10) |
|
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[Table view] |
Text
Attachment A Revise the Technical Specification pages as follows: Remove Insert page 3.5-15 page 4.1-7 page 3.5-15 page 4.1-7"9710010029 06000~44 87092+PDR~DGC~PDR gj, p
'k TABLE 3.5-4 Accident Monitorin Instrumentation TOTAI REQUIRED NO.OF CHANNELS (7)MINIMUM CHANNELS OPERABLE (7)1.Pressurizer Water Level (1)2.Auxiliary Feedwater Flow Rate (2)(3)3.Steam Generator Water Level-Wide Range (3)2/steam generator 1/steam generator 1/steam generator 1/steam generator 4.Reactor Coolant System Subcooling Margin Monitor (4)5.Pressurizer PORV Position indicator (5)6.PORV Block Valve Position Indicator (1)7.Pressurizer Safety Valve Position Indicator (5)2/Valve 1/Valve 2/Valve 1/Valve 0/Valve 1/Valve 8.Containment Pressure (8)9.Containment Water Level (Narrow Range, Sump A)1(6)1(6)10.Containment Water Ievel (Wide Range, Sump B)ll.Core-Exit Thermocouples 12.Reactor Vessel Level Indication System 4/core quadrant 2/core quadrant Notes (1)Emergency power for pressurizer equipment, NUREG-0737, item II.G.l.(2)'3)Auxiliary feedwater system flow indication, NUREG-0737, item II.E.1.2.Only 2 out of the 3 indications (two steam generator auxiliary feedwater flow and one wide-range steam generator level)are required to be operable, NUREG-0737, item II.E.1.2.(4)Instrumentation for detection of inadequate core cooling, NUREG-0737, item II.'F.2.1.
(5)Direct indication of relief and safety valve position, NUREG-0737, item II.D.3.Two channels include a primary detector and RTD as the backup detector.(6)Operation may continue with less than the minimum channels operable provided that the requirements of Technical Specification 3.1.5.1 are met.(7)See Specification 3.5.2 for required action.(8)Containment pressure monitor, NUREG-0737, item II.F.1.4.3s5)5 Proposed II Channel Descri tion TABLE 4.1-1'CONTINUED)
Check Calibrate Test Remarks 25.Containment Pressure 26.Steam Generator Pressure S 27.Turbine First Stage Pressure S M Narrow range containment pressure (-3.0,+3 psig)excluded 28.Emergency Plan Radiation Instruments 29.j 30.I Environmental Monitors Loss of Voltage/Degraded Voltage 480 Volt Safeguards Bus NA NA NA 31.Trip of Main Feedwater Pumps NA 32.Steam Flow AVG NA R 34.Chlorine Detector, Control NA Room Air Intake 35.0 36.Ammonia Detector, Control Room Air Intake NA Radiation Detectors, Control NA Room Air Intake 37.Reactor Vessel Level Indication System NA Attachment B The Reactor Vessel Z,evel Indication (RVZ,IS)was installed during the Spring 1986 refueling outage.A description of the RVLIS and plans for implementing revised Emergency Operating Procedures have previously been provided to the NRC in letters dated December 22, 1986, March 18, 1987 and September 18, 1987.The RVLIS is being incorporated into the Ginna Technical Specifications to satisfy a NUREG-0737 requirement transmitted by a D.G.Eisenhut letter dated November 1, 1983.This letter provided"Model Technical Specifications" to be incorporated for the RVLIS.The proposed RVZ IS technical specifications are identical'to the model specifications except they have been modified to fit the Ginna format.The detailed changes are listed on Table 1.In accordance with 10CFR 50.91, this change to the Technical Specifications has been evaluated against, three criteria to determine if the operation of the facility in accordance with the proposed amendement would: l.Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2.Create the possibility of a new or different kind of accident previously evaluated; or 3.Involve a significant reduction in margin of safety.The proposed changes do not,involve a significant'hange-in the probability of an accident previously evaluated because RVLIS is an instrument system involving small connections (3/8 inch)to the reactor coolant system.The RVLIS provides no automatic actuation on control functions and therefore will not.impact the probability of previously analyzed accidents.
Incorporation of the RVLIS into Technical Specifications may decrease the consequences of certain accidents by implementing instrumentation designed to detect'an'd aid in the response to inadequate core cooling.The proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated because the changes involve only specifying operability and surveillance requirements of the RVLIS.The proposed changes do not involve a significant reduction in margin of safety because specifying operability and surveill-ance requirements, in fact, increase safety margins by providing additional information useful to plant operators in responding to transient events and accidents.
1 e~II Therefore, Rochester Gas and Electric submits that the issues associated with this amendment.
request are outside the criteria of 10CFR50.91 and a no significant hazards finding is warranted.
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Table 1 Detailed Technical Specification Changes Location pp 3.5-15 pp 4.1-7 Descri tion of Chan e added item 12 added item 37 Reason for Chan e NUREG-0737 requirement NUREG-0737 requirement