ML15198A227

Attachment 4: Calculation TR-FSE-15-2-NP, Rev. 1, Palo Verde Nuclear Generating Station Unit 3 Evaluation of Potential Loose Part - Reactor Coolant Pump Instrument Nozzle Weld Fragment.

ML15198A227
Person / Time
Site:	Palo Verde
Issue date:	07/15/2015
From:	Slowik S T Westinghouse
To:	Office of Nuclear Reactor Regulation
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ML15198A232	List: ML15198A224 ML15198A225 ML15198A226 ML15198A227
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102-07077-TNW/DCE TR-FSE-15-2-NP, Rev 1
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{{#Wiki_filter:EnclosureNon-proprietary Documents for Relief Request 53Attachment 4Westinghouse Calculation TR-FSE-15-2-NP, Rev. 1, Palo VerdeNuclear Generating Station Unit 3 Evaluation of Potential LoosePart -Reactor Coolant Pump Instrument Nozzle Weld Fragment Westinghouse Non-Proprietary Class 3TR-FSE-15-2-NP, Rev. 1Palo Verde Nuclear Generating Station Unit 3Evaluation of Potential Loose Part -Reactor Coolant PumpInstrument Nozzle Weld FragmentThis document has been prepared and approved in accordance with Westinghouse Procedure WEC 6.1.Authors:Steven T. Slowik*Reviewers: Frank Ferraraccio*Manager: Tyler R. Upton** Electronically approved records are authenticated in the electronic document management system.© 2015 Westinghouse Electric Company LLC. All Rights Reserved.TR-FSE-15-2-NP, Rev. 1Page 1 of 19 Westinghouse Non-Proprietary Class 3SUMMARYDuring the 3R1 8 Palo Verde Nuclear Generating Station (PVNGS) Unit 3 refueling outage, leakage froma pressure instrument nozzle on the CE-KSB Type 101 Reactor Coolant Pump (RCP) 2A safe end wasidentified. The Arizona Public Service (APS) repair strategy includes performing a half-nozzle repair.This repair involves removing a portion of the existing nozzle, inserting a replacement nozzle design inthe same location, and then replacing the original pressure boundary partial penetration weld on theinside wetted surface with a weld located on the outside surface.Because the repair process involves removing the external portion of the existing RCP nozzle andleaving a small nozzle remnant inside the existing penetration, APS has asked Westinghouse to addressthe possibility that fragments of the existing partial penetration weld could come loose inside the reactorcoolant system (RCS) during the next cycle of operation (18 months is assumed). It was postulated thatthe crack (or cracks) which led to the leak were attributed to primary water stress corrosion cracking(PWSCC) and could propagate further until some portion(s) of the existing weld becomes a loose part.Westinghouse is aware of no prior industry experience where a half-nozzle repair has led to loose weldfragments.This evaluation concluded that the postulated loose part or parts will have no adverse impact on the RCSand connected systems, structures, and components (SSCs). The SSCs continue to be capable ofsatisfying their design functions.TR-FSE-1 5-2-NP, Rev, 1 Page 2 of 19TR-FSE-15-2-NP, Rev. 1Page 2 of 19 Westinghouse Non-Proprietary Class 31.0 IntroductionDuring the 3R18 PVNGS-3 refueling outage, APS identified signs of leakage (i.e., boric acid)stemming from a pressure instrument nozzle located on the suction nozzle safe end of the 2A CE-KSB Type 101 RCP. Refer to Figure 1.Figure 1Pressure Instrument Nozzle -Showing LeakageThe APS repair strategy is to perform a "half-nozzle" repair to the 1-inch instrument nozzle. Themodification will replace the instrument nozzle and leave in place a short segment of the originalnozzle and nozzle weld at the inner surface of the pump safe end (see Figure 2).Because the repair process involves leaving a small remnant of the nozzle inside the penetration,APS asked Westinghouse to address the possibility that some portion of the partial penetrationweld holding the RCP nozzle remnant in place could further crack and become a potential loosepart inside the RCS.Where identified by revision bars in the left margin, Revision 1 of this report makes editorialchanges recommended by APS to the Summary page and to Sections 2.0 and 7.0.2.0 Description of Loose PartAt the time this report was prepared, APS had not specifically identified the degradation mechanismI responsible for the leak. The topic was discussed with Westinghouse and it was postulated that thelikely mechanism is PWSCC of the susceptible Inconel 600 nozzle and weld materials. Non-TR-FSE-15-2-NP, Rev, 1Page 3 of 19 Westinghouse Non-Proprietary Class 3destructive examinations (NDE) were performed by APS to describe the flaw. The examinationsconsisted of:" injection of liquid penetrant at low pressure from the safe end outside diameter (OD) into theannulus between the bore and instrument nozzle;* visual inspection using a boroscope of the nozzle inner diameter (ID) and partial penetrationweld inside the safe end; and* ultrasonic testing (UT) across the nozzle remnant length, from the end of the pipe. (Thisinterrogation was not able to see the original partial penetration weld.)Figure 2Half-Nozzle Repair IllustrationPartial Penetration Weld (inside of RCP) could produce loose partNozzle RemnantReplacement PressureBoundary Weld (outside)Based on these inspections, APS identified no circumferential cracks in the nozzle (from UTinspection) and no external visually discernable degradation on the surface of the partialpenetration weld or the nozzle inside diameter. Thus, it was reasoned that one or more part-through-wall cracks likely exist in the nozzle and/or the weld. This is consistent with the orientationpreviously observed by APS for this type of degradation mechanism (i.e., PWSCC) in instrumentnozzles in the hot leg. This conclusion is important because both axial and circumferential flawswould be necessary to produce a loose part.The remnant Inconel 600 instrument nozzle (approximately 1.5 inches in length) is recessed insidethe safe end bore. It remains constrained by a relatively tight radial clearance between the nozzleTR-FSE-15-2-NP, Rev. 1Page 4 of 19 Westinghouse Non-Proprietary Class 3and the bore. This is further helped by the weld deposited in this annular gap during the weldingprocess. Therefore, even if the majority of the partial penetration weld was to break, it is notcredible to assume that the remnant nozzle could become a loose part and become ejected into theRCS flow during the next 18 month fuel cycle. Additional assurance is provided considering thatthe hypothetical cracks are likely longitudinal part-through-wall, and as such, the nozzle is able tomaintain its structural integrity. Also the partial penetration weld, even if it had several longitudinalradial cracks, would require at least two other planes oriented in the circumferential direction inorder to release a piece of any significant size. Since circumferentially-oriented cracks were notidentified by the UT, the likelihood for a weld fragment to be released is very low.Given this scenario, Westinghouse addressed the possibility that one or more fragments of theexisting partial penetration weld separates from the nozzle and weld butter and becomes a loosepart inside the RCS. For the purposes of this evaluation, the loose part has conservatively beendefined to be a relatively large weld fragment weighing approximately 0.1 pounds and having cross-sectional dimensions no greater than the partial penetration weld depth (approximately 0.9 inches)and a length equal to one-quarter of the circumference of the instrument nozzle (approximately 0.8inches). The weld filler material (i.e., down to the butter layer) is an Inconel alloy (Alloy 182) that iscompatible with the ASME SB-166 (UNS N06600) instrument nozzle material (References 8.9 and8.10).Other smaller sizes and shapes of the weld fragments are possible and, with this taken intoconsideration, various weld fragment sizes and shapes have been postulated in the individualevaluations contained in this report, as applicable.Additionally, it is noted that the postulated weld fragment would be native to the RCS and therefore,compatible with RCS chemistry.3.0 AssumptionsThe description of the loose part provided in Section 2.0 is based on an assumption that weldfragment(s) are generated. This is a conservative approach.All other principle assumptions made for various analyses/evaluations are identified in the individualsections that follow.4.0 Postulated Flow Path through the Reactor Coolant SystemThe following defines the postulated flow path of the weld fragments, and thus the portions andsubcomponents of the RCS that need to be assessed.The weld fragments will only enter the flow stream while the RCS is in operation. During normaloperation, flow through the RCS would carry the weld fragments through the suction of the 2A RCP.The weld fragments could impact components of the RCP and then be passed through the pumpdischarge into the cold leg. Flow in the cold leg would carry the weld fragments down the pipe.Three cold leg resistance temperature detector (RTD) thermowells are present in the flow path onTR-FSE-15-2-NP, Rev. 1Page 5 of 19 Westinghouse Non-Proprietary Class 3the vertical half of the pipe perimeter. The weld fragments would likely be carried past the RTDthermowells. However, it is possible that the weld fragments could impact one of the thermowells.At the end of the cold leg, the weld fragments would impact the core barrel, where flow and gravitywould carry the weld fragments down the downcomer. At the bottom of the downcomer, the weldfragments would likely impact the flowskirt and could become trapped in the gap between theflowskirt and the reactor vessel (RV), or travel through the gap between the flowskirt and the RV.This would depend on the size and orientation of the fragment when it hits the flowskirt.If the weld fragments pass through the gap between the flowskirt and the RV, or through one of theholes in the flowskirt, they would enter the reactor vessel lower plenum. In the lower plenum thereis a relatively lower flow stream velocity, and the loose weld fragments could settle at the bottom ofthe vessel. Alternatively, the turbulent flow in this area may push the weld fragments along thebottom of the reactor vessel or lift it to where they would impact the lower internals, the lower coresupport plate, or the bottom of the fuel assemblies (i.e., the lower end fitting). The flow could alsocarry the weld fragments towards the gaps around the core and the core bypass flow paths. Thestarting postulated size of the weld fragment would be too large to pass through the fuel or thebypass flow gaps. Only smaller weld fragments would be able to pass through the fuel assembliesor bypass gaps.Larger weld fragments would therefore remain in the lower reactor vessel plenum. It could bepostulated that the lower plenum turbulence may cause the weld fragments to fracture into smallerpieces. In this case, the weld fragments could only pass through the core bypass path or the fuelassembly debris capture grid once divided into small enough pieces.Other piping connected to the 2A cold leg includes the charging and safety injection lines. Both ofthese systems deliver to the RCS and therefore, flow would not carry the weld fragments out of theRCS through these lines. Larger weld fragments (i.e., those that cannot get past the fuel) could notbe carried to the pressurizer because the pressurizer main spray lines are located on the 1A and 1 Bcold legs.Similarly, weld fragments small enough to pass through the core could circulate around the RCS,through the hot leg and steam generators (SGs), to the 1A and 1 B loops and into the pressurizerspray system. Weld fragments could also travel to systems connected to the RCS, such as theemergency core cooling system (ECCS), through the shutdown cooling system (SDCS) suctionlines or chemical and volume control system (CVCS) through the letdown line. Only small weldfragments could reach the hot side of the RCS or connecting systems.In the short periods of operation as the plant transitions to off-normal conditions, such as duringstartup or shutdown, an even less likely scenario is that the weld fragments could become looseduring these off-normal conditions (i.e., when the RCS is operating with less than four pumps, suchas when the 2B RCP is operating while 2A is idle). Because this condition represents a veryinfrequent mode of operation, these various off-normal conditions are not specifically addressedherein.Based upon this predicted potential flow path, Sections 5.0 and 6.0 of this report specificallyaddress the consequences that the weld fragments could have on the RCPs, piping, vesselTR-FSE-15-2-NP, Rev. 1Page 6 of 19 Westinghouse Non-Proprietary Class 3structure and internals, fuel assemblies, control element assembly (CEA) operability, pressurizer,SGs, and connected systems.5.0 Affected Reactor Coolant System Components5.1 Reactor Coolant PumpsThis section discusses the evaluation of the effect of the weld fragments on the RCPs provided byReference 8.1.The weld fragments, or smaller pieces of a larger weld fragment, are not expected to adverselyaffect RCP operation. All postulated sizes of weld fragments will likely remain in the flow stream,pass through the impeller, and discharge into the reactor vessel. As the flow propels the weldfragments through the suction pipe and into the impeller, the weld fragments are prevented fromentering the plenum above the impeller due to seal injection inducing a positive flow of injectionwater into the pump casing (via the [ ]a,c A-gap between the impeller and diffuser).Furthermore, the radial velocity and momentum of the weld fragments within the flow stream willpropel them toward the diffuser, as opposed to making an upward ninety-degree turn as they passby the A-gap.Due to the relatively small mass of the weld fragment(s), impact damage upon the impeller anddiffuser vanes would be negligible. As a weld fragment passes through the impeller, the flow carriesit past the vanes. A direct impact occurs only at the tip of the impeller cone and the leading edgesof the impeller and diffuser vanes. All other impacts are postulated to hit the impeller and diffuser ata shallow angle. At most, weld fragment impacts would result in a minor peen mark, if there is adirect impact area, and superficial scratches on all other areas. Any weld fragments would passdirectly into the diffuser due to the high exit velocity at the impeller. Once through the diffuser, theweld fragments may cause superficial scratches or minor impact marks on the pump casingcladding before exiting through the cold leg.Therefore, it is concluded that the weld fragments, or smaller pieces of a larger weld fragment,passing through the RCP would not adversely impact the operation of the RCP.5.2 RCS Cold Leg PipingThis section discusses the evaluation of the effect of the weld fragments on the RCS cold legpiping, including the tributary nozzles and RTD thermowells, provided by Reference 8.2. Thisevaluation is limited to the cold leg piping between the 2A RCP and the reactor vessel, andtherefore, only the 2A safety injection nozzle, the charging inlet nozzle, and the RTD thermowellsare evaluated.The cold leg piping may be affected by the weld fragments since the weight of the weld fragmentsand the fluid velocities are great enough to cause the weld fragments to nick or gouge the cladsurfaces of the piping. It is highly unlikely that the weld fragments will produce a gouge thatextends down to the base metal.The charging inlet and safety injection tributary nozzles/lines are located in the upper half of thecold leg piping and flow into the RCS. Therefore, the weld fragments do not pose a problemTR-FSE-15-2-NP, Rev_1Page 7 of 19 Westinghouse Non-Proprietary Class 3because they cannot enter the nozzles due to the high velocity of the flow during operatingconditions. During low or no-flow conditions, the weld fragments will settle to the bottom of thepiping. Settled weld fragments would eventually make their way to the RV when higher flow ratesare reached. Additionally, the charging and safety injection lines are either discharging or stagnant,eliminating the possibility of the weld fragments entering and traveling through the two respectivesystems.Effects due to projectile impact on the thermowell have been previously evaluated by Westinghouse(References 8.7 and 8.8). Based on a comparison to prior evaluations, it is concluded that animpact from the limiting weld fragment of the size and mass described in Section 2.0 will not causeplastic instability in the thermowell. Hence, the pressure boundary will be maintained after such animpact. However, there remains a possibility that a thermowell could be bent or dented. If animpact occurs, monitoring data and/or alarms may indicate that a RTD has been renderedinoperable. If it is confirmed that a safety-related RTD has become inoperable, then continuedplant operation is subject to technical specification requirements. If a RTD does become inoperableafter startup with no associated pressure boundary breech occurring at the thermowell, it isconceivably possible that the thermowell could have sustained some damage from an impact.Performance of a visual inspection of the thermowells at the next outage would be advisable.5.3 Reactor Vessel StructureThis section evaluates the potential consequences of the weld fragments on the structural integrityof the surveillance capsule holder, flowskirt, in-core instrumentation (ICI) nozzles, and RV structurein general, as provided in Reference 8.2.Surveillance Capsule HolderThe weld fragments may be carried by the reactor coolant flow from the cold leg into thedowncomer, and impact a reactor vessel surveillance capsule holder (RVSCH) support bracket.The RVSCH support system consists of pairs of brackets welded to either side of the RVSCH andthe RV wall at several elevations.The effect of such an impact was addressed previously for a [ ]ac bolt (Reference 8.3).Since the approximately 0.1 pound weight of the limiting weld fragment is less than the weight ofthe bolt, the conclusions of the previous evaluation are also applicable to the weld fragment beingevaluated herein. The worst case scenario previously considered was that a loose bolt could strikea RVSCH and damage an intermediate bracket system so as to render one of the two bracketsections incapable of supporting the holder. The bracket section on the other side of the holderwould remain intact and maintain support for the holder at that elevation. Because the damagedbracket system will continue to provide support from the remaining section, there should be noissues with the removal of the capsule from the holder at a later date.FlowskirtThe weld fragments would be carried by the coolant flow and, in a worst case scenario, impact theflowskirt cylinder at one of its supports. The impact forces would generate stresses in the flowskirtcylinder and its support. The effect of such an impact was previously addressed for a [ ]axbolt. Since the approximately 0.1 pound weight of the weld fragment is less than the weight of thebolt, the conclusions of the previously evaluation can also be applied to the loose weld fragments.SE-15-2-NP, Rev. 1Page 8 of 19 Westinghouse Non-Proprietary Class 3The previous stress evaluation for the [ ]a,c bolt shows that the stress due to the impactexceeds the yield strength. In the worst case scenario, one of the nine supports is damaged andincapable of supporting the flowskirt but the other eight supports remain intact. Additionally, thecurrent primary stresses and fatigue usage factors on the supports during operating conditions arenegligibly small. There could be a localized plastic deformation on one of the nine supports or theflow baffle; however, the flowskirt assembly will remain intact.ICI NozzlesThe ICI nozzles are welded to the RV bottom head. It is assumed that the weld fragments areeither in the downcomer between the RV and core support barrel (CSB) or at the bottom of the RV.In either scenario, the weld fragments would be lifted, swept by the coolant flow, and impact one ormore ICI nozzles. The impact forces generate stresses in the ICI nozzles and weld that, whenadded to stresses due to other design and operating load conditions, may result in stressesexceeding ASME Code stress criteria. The effect of such an impact was previously addressed for aI ]axc bolt. Since the approximately 0.1 pound weight of the postulated weld fragment isless than the weight of the bolt, the conclusions of the previous evaluation can also be applied tothe weld fragments as a loose part.The cited ICI nozzle/weld stress evaluation including the weld fragment impact forces considerednormal operating conditions of the RCS. In addition to a weld fragment impact force, the stressespreviously evaluated include, as applicable, pressure, flow loads, thermal loads, pump inducedmechanical excitation of the reactor vessel, operating basis earthquake (OBE), and safe shutdownearthquake (SSE). These loads were retained along with the impact loads, but they are negligiblecompared to the weld fragment impact load and therefore, do not impact the conclusions of theanalysis.The evaluated case yields the maximum loads and stresses on the ICI nozzle. The ASME Codestress criteria are not satisfied at the ICI nozzle weld. The stresses are evaluated on an elasticbasis. However, the ASME Code, Appendix F provides stress criteria for elastic analyses thatapproach the material ultimate strength (Su) and allows for some plastic deformation. Since thesecriteria are also exceeded, there is a reasonable expectation that application of elastic/plasticanalyses would also demonstrate localized failure or possibly marginal acceptance. ExceedingASME Code limits at the ICI weld may result in crack initiation and/or leakage.Since the limiting size weld fragment weighs [ ]a,c less than the bolt previously analyzed, thestresses due to impact will be significantly less and will likely meet ASME Code, Appendix Fallowable values.The previous velocities considered are sufficient to lift the weld fragments and sweep them awayfrom the ICI nozzle, thereby preventing the weld fragments from being wedged at the ICI nozzle.Therefore only one impact of the ICI nozzle would occur and the impact would not contribute to thefatigue usage.RV StructureThe RV may be affected by weld fragments since the weight of the weld fragments and' the fluidvelocities are great enough to cause these loose parts to nick or gouge the clad surfaces of the RV.It is highly unlikely that the weld fragments will produce a gouge that extends down to the basemetal.TR-FSE-15-2-NP, Rev. 1Page 9 of 19 Westinghouse Non-Proprietary Class 3The potential damage caused by the weld fragments would have minimal and acceptable effects onthe interior cladding of the RV, the flowskirt, RVSCHs, and ICI nozzle. Postulated damage wouldnot preclude continued plant operation for one cycle.5.4 Reactor Vessel InternalsThis section discusses the evaluation of the consequences of the weld fragments, either being in orpassing through the reactor vessel internals (RVI), as provided by Reference 8.4. The weldfragments, being relatively small, could be carried by the flow into various portions of the RVI.Evaluation of Weld Fragments Impacting the Core Support BarrelSince the RCP suction nozzle is located in a RCS cold leg, the weld fragments would be carried bythe RCS flow and impact the wall of the core support barrel when they exit the cold leg. The CSB isa large robust structure fabricated from 3-inch plate at the elevation of the cold leg where the weldfragments would impact. Therefore, the largest weld fragment, which is assumed to weighapproximately 0.1 pounds, is judged to impart minimal damage to the CSB. This judgment isfurther supported by industry experience with safety injection thermal sleeves, which aresignificantly heavier, having impacted the core barrel at other Combustion Engineering (CE)designed plants after coming loose.After impacting the CSB, the weld fragments would be carried by the flow down the downcomerbetween the core barrel and the reactor vessel. Any impact with the core barrel during the traverseof the weld fragments in the downcomer would be less severe than the initial impact at the inletnozzle location.Evaluation of Small Weld FragmentsThe possibility of small weld fragments being carried throughout the RCS and affecting the RVI isevaluated in the following sub-sections.Core Support Barrel Alignment Keys and KeywaysThe reactor internals alignment keys are part of the CSB assembly and provide the alignmentsystem for the reactor internals, the RV, and the reactor vessel closure head. The alignmentsystem consists of precise gaps between the alignment keys and their respective mating keys slots(i.e., keyways) in the interface components. There are four alignment keys at ninety degreesequally spaced azimuthally that are shrunk-fit into the CSB flange and retained in position by tworadial dowel pins at each key location. The keyways are subjected to a small amount of inletleakage flow into the RV head region that would have a tendency to keep those areas flushed ofsmall particles if they were transported to that location. It is highly unlikely that the weld fragmentscould reach the alignment keys, which are located in the RV closure head region of the vessel, andif they did, and were not flushed away, the weld fragments still would not affect the alignment keyfunction.Hold Down RingThe hold down ring is compressed between the top surface of the CSB flange and the underside ofthe upper guide structure flange. The function of the hold down ring is to prevent movement of thereactor internals during plant operation. In order to perform that function, the hold down ring iscompressed, causing the ring to rotate. This exerts a preload on the interface surfaces of the UGSand the CSB. Since the interface surfaces of the hold down ring are in compression, there is noTR-FSE-15-2-NP, Rev. IPage 10 of 19 Westinghouse Non-Proprietary Class 3possibility that weld fragments can enter the interface during RCS operation. Therefore, the weldfragments could not affect the hold down ring function.Core Barrel Flange to Reactor Vessel Seating Surface AnnulusIt is highly unlikely that weld fragments will move into this annular space during service since thereis only a small amount of inlet coolant leakage flow to transport the fragments through the CSBalignment keys and into this region of the RV head.Annular Space between the Core Shroud and Core Support Barrel Inside DiameterIt is possible that the weld fragments could enter the annular space between the core shroud andCSB inside diameter. There is a small amount of flow in this annular space to cool the backside ofthe core shroud and inside diameter of the CSB in this region. However, the weld fragments wouldtend to settle out in a low flow area and would not have an adverse effect on any of the largecomponents in this region.SnubbersThere are six snubbers spaced sixty degrees apart between the lower end of the CSB and the RV.These components have a tongue and groove arrangement with a small gap on each side. Weldfragments, if transported to these gaps, would be immediately flushed out, due to the high velocityflow. Therefore, the weld fragments would have no effect on the function of the snubbers.The Upper Guide Structure (UGS) Support Barrel Assembly and CEA Shroud AssemblyThere are no close fits in this region that would be impaired by the presence of weld fragments.Weld fragments, if deposited on the upper surface of the support plate of the UGS support barrelassembly, would most likely remain in position due to the low velocity flows in that region.However, if transported by the reactor coolant flow, the weld fragments would not impair thefunctions of the UGS support barrel assembly and CEA shroud assembly.Other RVI Components1. The interface between the guide post of the fuel assembly upper end fitting and the UGStubes in the UGS support barrel assembly is a precise interface, for both the standardfuel design and Next Generation Fuel (NGF). The coolant flow exiting from the fuelassembly guide tubes will tend to flush this annular space of the weld fragments, buteven if it did not, there will be no loss of function at the fuel-to-UGS tube interface.2. At the periphery of the fuel alignment plate there are four keyways spaced ninetydegrees apart that form a precise interface gap with the shims on the guide lugs. Weldfragments small enough to fit into these gaps would most likely be flushed out by thecoolant flow, but even if they remained, they would cause no loss of function to thisinterface.5.5 FuelThis section summarizes the evaluation of the potential impact of the weld fragments on fuelperformance (Reference 8.5).TR-FSE-1 5-2-NP, Rev. 1 Page 11 of 19TR-FSE-15-2-NP, Rev. IPagel 1 of 19 Westinghouse Non-Proprietary Class 3Since the weld fragment mitigation features are essentially the same for the CE16STDGUARDIANTM1 grid design and the CE16NGF GUARDIAN grid design, the evaluation is applicableto PVNGS Unit 3 cores containing either fuel product.The weld fragments as described in Section 2.0 have been evaluated. Additionally, it has beenpostulated that some cladding material above or adjacent to the weld may also break off with theweld fragment. The composition, size, and shape of the weld fragment is not precisely known, so amixture of Inconel 600 and stainless steel has been assumed specifically for the evaluation of thefuel. Given that the weld fragments evaluated below are assumed to be a mixture of Inconel alloysand stainless steel, there will be no metallurgical concerns with the presence of these materialswithin the reactor core region.Passage of parts through the ICI guide pathThe funnel on the fuel assembly lower end fitting (LEF) in non-ICI locations represents a very smallpercentage of the flow, so it is unlikely that the weld fragments would enter the funnel. If the weldfragments enter the funnel and are larger than the through-hole diameter, they would be caught andwould fall out at the end of cycle or become wedged. If an unidentified wedged piece of weldfragment was in an assembly that is moved to an ICI location, the ICI could not be inserted prior tooperation.A weld fragment smaller than the minimum entrance diameter and larger than the exit hole]axC would be retained in the guide tube during operation and may fall out at the end ofthe cycle or remain in the instrument tube. In this unlikely case, the weld fragment could interferewith the insertion of an ICI in a subsequent cycle. A weld fragment smaller than the exit hole wouldenter the flow stream above the fuel assemblies.At ICI locations, there is a very small gap between the LEF funnel and ICI nozzle]a,c so only very small weld fragments could enter this gap. A second location where theweld fragments could enter an ICI location is at the interface of the instrument nozzles. However,the tight radial clearance within the instrument nozzles would likely capture any weld fragment thatmay enter at that location. Therefore, there are no operational consequences of weld fragmentsentering the ICI flow paths. There is some risk of the ICI binding during withdrawal, but this risk isvery small given that a weld fragment of a very specific size would have to be wedged between theICI and wall.Passage to and through the Lower End Fitting and GUARDIAN gridThe LEF is comprised of [ ]a,c flow holes each with a diameter of [ ]a-c. The LEF mayor may not prevent weld fragments from passing. However, the largest circular size that can passthrough the CE16STD fuel GUARDIAN grid is considerably smaller at [ The largestcircular size that could pass through the CE16NGF fuel GUARDIAN grid is [Although weld fragments with dimensions greater than [ ]aC would likely be held againstthe GUARDIAN grid and/or LEF for both CE16STD and CE16NGF fuel designs, and would evenlydistribute at one axial plane, it is conservatively assumed that all of the weld fragments are caught1 GUARDIAN and ZIRLO are trademarks or registered trademarks of Westinghouse Electric Company LLC, its Affiliates and/or itsSubsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved.Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.TR-FSE-15-2-NP, Rev. 1Page 12 of 19 Westinghouse Non-Proprietary Class 3in the LEF/GUARDIAN grid of one assembly (out of 241) for the purposes of evaluating flowstarvation upstream of the beginning of the heated length to negatively impact departure fromnucleate boiling (DNB). Based upon DNB test results for a four foot heated length, a []ax at the inlet had no measurable impact on DNB performance at nominal conditions.Hence, the weld fragment size is bounded by these results.For the weld fragment to impact fuel performance due to fretting wear, a small piece of weldfragment must pass through the GUARDIAN grid or around the LEF. For weld fragments to causefretting wear, they need to be long enough so that the one end is trapped in a grid feature and theother end is free to vibrate due to coolant flow with a hammering or rubbing action on the cladding.Such a weld fragment that was able to pass through this region of the fuel assembly would likely notbe of a configuration conducive to cause fragment fretting. However, the material of the weldfragment is harder than the ZIRLO 1 cladding, so there exists some risk that a small number offragment fretting failures could occur.The operating history of the GUARDIAN grid has been excellent. Only one confirmed fretting-related leaker is known to have occurred (Waterford-3 Cycle 19) out of over 7200 16x16assemblies. If the weld fragment is small and light enough to get through or around the LEF andGUARDIAN grid, it would either be carried through the grids and end fittings and exit the fuelassembly, or be captured in the grids above the GUARDIAN grid. It is unlikely that weld fragmentscaught in the mid grids above the GUARDIAN grid would be sufficiently long enough to causefretting failure, but there is always some risk. Although a small risk, weld fragments in the RCS canresult in a leaking rod. Therefore, continuous monitoring of the coolant activity to check for thepresence of any new grid-to-rod fretting (GTRF) leakers is recommended.Bypass FlowThe flow area corresponding to the [ ]ac holes in the lower support structure cylinderbypass flow region may result in large enough flow velocities to lift the weld fragments and transportthem through the shroud cooling water passages. The much smaller velocities further downstreamand the tight turns and small annular gaps would inhibit weld fragment passage beyond this region.Within the core support barrel and core shroud annulus, the flow area will result in very low flowvelocities; hence, the weld fragments would be expected to settle to the bottom of the bypassregion. Therefore, it is concluded that there is low probability that the postulated weld fragmentswill pass from the lower reactor vessel environs through the core barrel/core shroud annulus andinto the outlet regions of the reactor vessel.5.6 CEA OperabilityThis section discusses the evaluation of the effect of the weld fragments on CEA operabilityprovided by Reference 8.5.The only viable path for small weld fragments to make it through the GUARDIAN grid and enter theCEA guide path is if they are in the immediate vicinity of the bleed hole and the cooling hole in anouter guide tube. Although extremely unlikely, any weld fragments that might enter the CEA guidepath would likely either drop to a benign location at the bottom of the guide tube or be swept up theguide tube and into the CEA shroud. Weld fragments would not be expected to impede theoperation of the CEA by being wedged between the CEA and the guide tube based on the smallsize required to enter the CEA guide path. In the very unlikely event that a loose weld fragment didTR-FSE-15-2-NP, Rev. 1Page 13 of 19 Westinghouse Non-Proprietary Class 3impede the motion of the CEA, it is most likely to occur when the CEA finger is within the reducedclearance region of the guide tube dashpot. In this event, maneuvering of the CEA is expected toclear the obstruction, based on prior instances of obstructions in the dashpot regions.6.0 Remaining SSCs in the RCS and Connected and Auxiliary SystemsThe following subsections address the portions and major components of the RCS that will beaffected by weld fragments that are sufficiently small to pass through the fuel and core bypass, andhave access to downstream systems connected to the RCS (i.e., not otherwise addressed inSection 5.0).Other systems connected to the 2A cold leg includes the charging and safety injection lines. Bothof these systems deliver to the RCS and therefore, flow would not carry the initial weld fragmentsout of the RCS through these lines. As the weld fragments pass through the 2A RCP, the cold leg,and into the RV lower plenum, the fragments could break into much smaller pieces, which willultimately pass into and remain in circulation within the RCS until they are drawn into the designfiltration system of the CVCS or settle elsewhere in an auxiliary system. The following descriptionsreview the possibility of such effects on the individual auxiliary systems.6.1 Remaining RCS ComponentsUpper RVIAll RVI (both upper and lower) are evaluated in Section 5.4.RCS Hot LegsThe impact of weld fragments small enough to pass through the fuel on the RCS hot legs isbounded by the evaluation for the cold leg, documented in Section 5.2, as well as by the reviewdocumented in Reference 8.6.PressurizerDuring normal operation, the pressurizer receives a continuous bypass spray flow from the cold legand a corresponding continuous flow from the pressurizer to the hot leg. The smaller weldfragments would most likely remain in the main RCS flow path if they pass through the core. It ispossible that if the pressurizer main spray is cycled and weld fragments are in the appropriate coldleg, that they could be drawn into the pressurizer spray line. The larger postulated weld fragmentscould not be carried to the pressurizer because the pressurizer main spray lines are located on the1A and 1 B cold legs. Only the weld fragments small enough to pass through the fuel assembliescould possibly reach the pressurizer.There will be no consequence on the main spray piping and valves, or on main spray performance.The main spray valves are 3-inch full-port globe valves and, as such, have no likelihood of blockagedue to the small weld fragments. The warm-up/bypass valves are 33/4-inch globe valves understoodto be throttled to a fairly open position. Even in the throttled position, the small weld fragmentshave a low likelihood of blockage in the valve.TR-FSE-1 5-2-NP, Rev. 1 Page 14 of 19TR-FSE-15-2-NP, Rev. 1Page 14 of 19 Westinghouse Non-Proprietary Class 3Pressurizer Spray NozzleThe pressurizer spray nozzle outlet is a hollow core design attached to the 3-inch nominal RCSspray piping. The flow path through the nozzle is large enough that the weld fragments would flowthrough the nozzle and into the pressurizer.Pressurizer HeatersThe pressurizer heaters consist of cylindrical heating elements inserted in the bottom of thepressurizer and are supported by two support plates inside the lower region of the pressurizer.Should any weld fragments make it into the pressurizer, they would settle to the lower region of thepressurizer, settling onto the support plates or lower head. These weld fragments would eitherremain in place with no consequence or be swept back into circulation through the pressurizersurge line during a normal surge/swell. There is a small gap between the pressurizer heaters andthe two horizontal support plates. As previously described, since the likelihood of weld fragmentsentering the pressurizer is very low, it is considered further unlikely that weld fragments would settledirectly within this gap. The downflow out of the pressurizer, which would occur during a sprayevent, would tend to draw any weld fragments around the top support plate, making it considerablyless likely that any weld fragments would land on the lower support plate. Thus, it is consideredhighly unlikely that any weld fragment would obstruct the gap and thus, have an appreciable effecton thermal growth or heat transfer efficiency of the heaters.Pressurizer Surge LineThe pressurizer surge line connects to roughly the midpoint of hot leg 1. The surge line diameter issufficient that the smaller weld fragments would not affect flow along the surge line. The surge linematerial is -stainless steel, which is the same material as the RCS piping cladding. Therefore, therewould be no consequence to the surge line piping due to the presence of the weld fragments in thecoolant. Weld fragments entering through the spray line may settle in the lower head and not leavethe pressurizer.Steam GeneratorsDuring normal operation, the weld fragments could only reach the SG if they were small enough topass through the fuel assemblies.Reference 8.7 evaluated loose bolts, nuts, and washers of significantly more size and mass (up toI ] a,c) than any weld fragment that could pass through the fuel assemblies, and concludedthey would not adversely impact the function of the SGs operationally or as part of the RCSpressure boundary. Therefore, the potential weld fragments in the system would not adverselyimpact the SGs from performing their design function.6.2 Connected and Auxiliary Systems-The following subsections address the systems connected to the RCS. The conclusions of thissection are based upon the prior evaluation of similar debris evaluated in Reference 8.7.Safety Iniection, Containment Spray, and Shutdown Cooling SystemsThe safety injection system (SIS) and containment spray system (CSS), including the ECCS pumpsand safety injection tanks (SITs), inject borated water into the RCS in the event of a loss of coolantaccident (LOCA). This provides cooling to limit core damage and fission product release, andTR-FSE-15-2-NP, Rev. 1Page 15 of 19 Westinghouse Non-Proprietary Class 3ensures adequate shutdown margin. The SIS also provides continuous long-term, post-accidentcooling of the core by recirculation of borated water that collects in the containment sump.The shutdown cooling system (SDCS) is used in conjunction with the main steam and main orauxiliary feedwater systems to reduce the temperature of the RCS in post-shutdown periods fromnormal operating temperature to the refueling temperature.The piping connected to the 2A cold leg includes one SIS injection nozzle. The SIS delivers flow tothe RCS at this location and therefore, flow would not carry the weld fragments out of the RCSthrough these lines.The shutdown cooling suction lines are connected to the hot legs of the RCS and this is the onlycredible flow path for the weld fragment to enter the SIS, CSS, or SDCS. Only weld fragmentssmall enough to pass through the fuel assemblies could reach the shutdown cooling suction line onthe hot leg. Weld fragments of this size would not adversely impact the ability of the SIS, CSS, orSDCS to fulfill their design functions.Chemical and Volume Control SystemThe CVCS controls the purity, volume, and boric acid content of the reactor coolant. The coolantpurity level in the RCS is controlled by continuous purification of a bypass stream of reactor coolant.Water removed from the RCS is cooled in the regenerative heat exchanger. From there, thecoolant flows to the letdown heat exchanger and then through a filter and demineralizer wherecorrosion and fission products are removed. The filtered coolant is then sprayed into the volumecontrol tank and returned by the charging pumps to the regenerative heat exchanger where it isheated prior to return to the RCS.The letdown system components are not explicitly evaluated, as the purification system is fulfillingits design function. This is due, in part, to the fact that removal of system debris is within the designbasis of the letdown system components. The larger weld fragments cannot pass the fuelassemblies GUARDIAN grid; therefore, the larger weld fragments will not be introduced into theletdown system, which connects to the RCS in the suction leg connected to the bottom of the coldside of the steam generator outlet.In the event that the weld fragments break apart to the point of being able to pass through the fuel itis most likely that the weld fragments will be small enough and the flow sufficient that the weldfragments would flow past the letdown nozzle and not be introduced into the letdown system. In theevent that they are introduced into the letdown system, the weld fragments would pass through theletdown system to the system filters where they would be retained.Regarding the charging function of the CVCS, the charging pumps only draw inventory from thevolume control tank (VCT) and the refueling water storage tank (RWST). The weld fragments willnot enter either of these suction sources.Seal injection water supplied to the RCPs is drawn from the VCT by the charging pumps.Consequently, per the explanation in the prior paragraph, the weld fragments cannot migrate intothe RCP seal packages by seal injection.TR-FSE-1 5-2-NP, Rev. 1 Page 16 of 19TR-FSE-15-2-NP, Rev. 1Page 16 of 19 Westinghouse Non-Proprietary Class 3It is unlikely the weld fragments will enter the CVCS. However, if they do, they would be retained inthe system filter and not adversely impact the ability of the CVCS to fulfill its design functions.Spent Fuel PoolThe spent fuel pool (SFP) is isolated from the refueling cavity and the RCS during normal operation.If the weld fragments came loose during normal operation, they would travel through the RCS andcould reach the fuel. It is possible that weld fragments could become caught in the fuel assemblyGUARDIAN grid.During the following refueling cycle, the weld fragments 'could transfer with the fuel assemblies tothe SFP. If the weld fragments entered the SFP during refueling operations (i.e., if they were to fallfrom the GUARDIAN Grid), they would settle to the floor of the pool and remain there. The weldfragments on the SFP floor would not migrate into the spent pool cooling system due to therelatively high location of the cooling system suction inlet above the pool bottom surface.Based on this evaluation, the potential presence of the weld fragments in the RCS does notadversely impact the capability of the pool cooling system to fulfill its design function.7.0 ConclusionsDuring the 3R18 Palo Verde Nuclear Generating Station (PVNGS) Unit 3 refueling outage, ArizonaPublic Service (APS) identified signs of leakage (i.e., boric acid) coming from a 1-inch pressureinstrument nozzle on the 2A loop reactor coolant pump (RCP). The APS repair strategy includedperforming a half-nozzle repair, which would involve removing a portion of the existing nozzle,inserting a replacement nozzle design into the same location, and then replacing the originalpressure boundary partial penetration weld (on the inside wetted surface) with a weld located on theoutside surface of the pump safe end.Because the repair process involves leaving a small remnant of the nozzle inside the existingpenetration, APS asked Westinghouse to address the possibility that fragments of the existingpartial penetration weld could come loose inside the RCS during the next cycle of operation (18months is assumed). Westinghouse and APS postulated, based on non-destructive examinations(NDE) performed to describe the flaws, that the crack(s) on the nozzle and or weld are part throughwall in the axial direction with no evidence of circumferential cracks. This is consistent with theorientation previously observed by APS for this type of degradation mechanism (PWSCC) ininstrument nozzles in the hot leg.The remnant Inconel Alloy 600 instrument nozzle (approximately 1.5 inches in length) is recessedinside the safe end bore. It remains constrained by a relatively tight radial clearance between thebore and the nozzle. This is further helped by the weld deposited in this annular gap during thewelding process. Therefore, even if the majority of the partial penetration weld was to break, it is notcredible to assume that the remnant nozzle could become a loose part and become ejected into theRCS flow during the next 18 month fuel cycle. Additional assurance is provided considering thatthe hypothetical cracks are likely longitudinal part through wall, and as such the nozzle is able tomaintain its structural integrity. Also, even if the partial penetration weld had several longitudinalTR-FSE-15-2-NP, Rev. 1Page 17 of 19 Westinghouse Non-Proprietary Class 3radial cracks, it would require at least two other crack planes oriented in the circumferentialdirection in order to release a piece of any significant size. Since circumferentially-oriented crackswere not identified by the ultrasonic testing (UT), the likelihood for a fragment of the weld to bereleased is very low.The pressure instrument nozzle partial penetration weld is an Inconel alloy compatible with theInconel Alloy 600 nozzle. Based on the above, a conservatively sized fragment of weld wasassumed to weigh approximately 0.1 pounds and have dimensions no greater than the partialpenetration weld thickness at its cross-section, and a length of one-quarter of the circumferencearound the instrument nozzle.Westinghouse evaluated the structural and functional impacts of the loose weld fragment(s) onaffected SSCs. Engineering judgments were applied and prior PVNGS loose parts evaluationresults were taken into consideration. The evaluation considered that although the aforementionedfragment represents one possible form of the loose part, it is possible that smaller fragments ofdifferent sizes, shapes, and weights could be released, or created. Additional smaller fragmentsare possible, for example, if a weld fragment were to make contact with a high-velocity RCPI impeller blade, or perhaps make high-speed contact with the reactor vessel core barrel.The evaluation concluded that the postulated loose parts will have no adverse impact on the RCSand connected SSCs after one cycle of plant operation. The evaluation addressed potentialimpacts to various SSCs where the loose parts might travel. This included the RCPs, the maincoolant piping, the reactor vessel and its internals, the fuel, the pressurizer, steam generators, aswell as other systems attached to the RCS, including the spent fuel pool. It was determined that allimpacted SSCs would continue to be capable of satisfying their design functions.8.0 References8.1 LTR-KUAE-15-016, "Loose Parts Evaluation -Suction Nozzle Pressure Tap ReactorCoolant Pump, Palo Verde Unit 3, S/N 1111-2A," April 14, 2015.8.2 LTR-MRCDA-15-35, Rev. 0, "Transmittal of MRCDA-l Input for the Analysis of Loose RCPSuction Nozzle Weld Fragments at PVNGS Unit 3 Considering One Cycle of ContinuedOperation," April 14, 2015.8.3 LTR-MRCDA-10-79, "Structural Evaluation of the Palo Verde Unit 1 Reactor VesselSurveillance Holders due to a Loose Bolt Impact," May 10, 2010.8.4 LTR-RIDA-15-73, "Palo Verde Nuclear Generating Station Unit 3 Evaluation of PossibleReactor Coolant Pump Suction Nozzle Weld Fragment Loose Parts on the Reactor VesselInternals," April 14, 2015.8.5 CE-15-207, "PVNGS RCP Suction Nozzle Remnant Loose Part Evaluation for the Fuel andCore Components," April 14, 2015.8.6 LTR-RC-14-55, Rev. 0, "Palo Verde Nuclear Generating Station Unit 3 Review of BoundingEvaluations for Loose Weld Material," December 2014.TR-FSE-15-2-NP, Rev. 1 Page 18 of 19TR-FSE-15-2-NP, Rev. 1Page 18 of 19 Westinghouse Non-Proprietary Class 38.7 DAR-SEE-II-10-3, Rev. 0, "Palo Verde Nuclear Generating Station Unit 1 Evaluation ofMissing Bolt Shanks, Nuts and Washers," May 2010.8.8 DAR-SEE-II-08-12, Rev. 0, "Disposition of Postulated Foreign Material in Palo VerdeNuclear Generating Station Units 1, 2, 3 Nuclear Steam Supply System Originating fromReactor Coolant Pump Wedge Assemblies," December 2008.8.9 LTR-KUAE-15-017, "Documentation of References applicable to Palo Verde Unit 3 PressureTap Weld Details," April 16, 2015.8.10 STD-009-0009, Rev. 2, "Coolant Pumps Weld Joint Identification and FabricationRequirements."TR-FSE-1 5-2-NP, Rev. 1 Page 19 of 19TR-FSE-15-2-NP, Rev. 1Page 19 of 19 EnclosureNon-proprietary Documents for Relief Request 53Attachment 5Westinghouse Letter, LTR-ME-1 5-30-NP, Rev. 2, ASME CodeSection Xl Reconciliation for Arizona Public Service (APS), PaloVerde Nuclear Generating Station (PVNGS) Unit 3 ReplacementInstrument Nozzle Westinghouse Non-Proprietary Class 3S WestinghouseTo: Sarah E. LaxDate: July 7, 2015cc: Byounghoan ChoiEric M. WeiselFrom: Ana BauerTel: 860-731-6529Your ref:Our ref: LTR-ME-15-30-NP, Rev. 2Total Pages: 10

Subject:

ASME Code Section XI Reconciliation for Arizona Public Service (APS), Palo Verde NuclearGenerating Station (PVNGS) Unit 3 Replacement Instrument NozzleAttachment 1:ASME Code Section XI Reconciliation Arizona Public Service (APS), Palo Verde NuclearGenerating Station (PVNGS) Unit 3 Replacement Instrument NozzleAttachment 1 of this letter contains the ASME Code Section XI Reconciliation for the ReplacementInstrument Nozzle to be supplied to Arizona Public Service (APS), Palo Verde Nuclear GeneratingStation (PVNGS) Unit 3. This ASME Code Section XI Reconciliation is to be used in conjunction withCN-MRCDA-15-13.If you have any questions or desire further information, please contact the undersigned.Author Name (s)Ana V. BauerSignature / DateScopeElectronically Approved*Non-Proprietary Class 3Verifier Name (s)Aaron C. BergeronSignature / DateScopeElectronically Approved*Non-Proprietary Class 3Manager NameRichard P. O'NeillSignature / DateScopeElectronically Approved*Non-Proprietary Class 3*Electronically approved records are authenticated in the electronic document management system.© 2015 Westinghouse Electric Company LLCAll Rights Reserved Westinghouse Non-Proprietary Class 3Page 2 of 10Our ref: LTR-ME-15-30-NP, Rev. 2July 7, 2015Attachment 1: ASME Code Section XI Reconciliation Arizona Public Service (APS), Palo VerdeNuclear Generating Station (PVNGS) Unit 3 Replacement Instrument Nozzle1.0 Introduction1.1 PurposeThe purpose of this ASME Code Section XI reconciliation is to demonstrate fulfillment of the requirementsfor the use of a later edition of the ASME Boiler and Pressure Vessel Code for the Replacement InstrumentNozzle to be supplied and installed at Arizona Public Service, Palo Verde Nuclear Generating Station(PVNGS) Unit 3. The Replacement Instrument Nozzle is part of the Reactor Coolant Pump (RCP) and is tobe supplied in accordance with the contract requirements in [9] and the code years specified in the designspecification [5].The ASME Code Section XI program at PVNGS Unit 3 is governed by the 2001 Edition up to and includingthe 2003 Addenda of Section XI [4]. Section XI of the ASME Code requires reconciliation of changes to theoriginal design basis when ASME Code replacement items (such as materials, parts, and components) aredesigned and fabricated to a later edition or addendum of the Construction Code.This document is intended to reconcile the ASME Code Section III, 1995 up to and including 1997 Addenda[2] used in the analysis/qualification and the 1998 Edition up to and including the 2000 Addenda [3] used inthe procurement of material, fabrication, and examination of the Palo Verde Nuclear Generating Station(PVNGS) Unit 3 Replacement Instrument Nozzle to the Original Construction Code. The OriginalConstruction Code for Palo Verde Nuclear Generating Station (PVNGS) Unit 3 is the ASME Code SectionIII, 1974 Edition, no Addenda [1].1.2 Limits of ApplicabilityThis document is applicable to Palo Verde Nuclear Generating Station (PVNGS) Unit 3.2.0 Summary of Results and Conclusion2.1 ResultsThe Arizona Public Service, Palo Verde Nuclear Generating Station (PVNGS) Unit 3, Reactor Coolant Pump(RCP) Replacement Instrument Nozzle is analyzed to the requirements of the ASME Code Section III, 1995up to an including the 1997 Addenda [2], and procured and fabricated to the requirements of the ASMECode Section III, 1998 Edition up to and including the 2000 Addenda [3], and the design specification [5]and reconciled herein to the Original Construction Code, 1974, no Addenda [1].The design configuration changes, loadings, and different materials in the Palo Verde Nuclear GeneratingStation (PVNGS) Unit 3 Replacement Instrument Nozzle are identified in Section 4.0. The impact of theseOwner's Requirements are evaluated in the ASME Section III Code design report and supporting analyses.There are no pressure-temperature ratings associated with the design of the Replacement Instrument nozzlesand the interfacing equipment. Westinghouse Non-Proprietary Class 3Page 3 of 10Our ref: LTR-ME-15-30-NP, Rev. 2July 7, 20152.2 ConclusionThe Replacement Instrument Nozzle meets the ASME Section XI Code Applicability and Reconciliationrequirements since:(1) Materials are compatible with the installation and system requirements.(2) The requirements affecting design, fabrication, installation, and examination of the item to be used forreplacement are reconciled with the Owner's Specification through the design drawings, designspecification, and design report.(3) Mechanical interfaces, fits, and tolerances that create the pressure boundary are compatible with thesystem and component requirements through the design report and supporting analysis.3.0 Assumptions and Open Items3.1 AssumptionsThis reconciliation report contains no assumptions.3.2 Open ItemsThis reconciliation report contains no open items.4.0 Section XI -2001 through 2003 Addenda -Summary of RequirementsIn accordance with the APS contract [9] and Westinghouse Reactor Coolant Pumps Design Specification [5]:" The Original Construction Code is the ASME Boiler and Pressure Vessel Code, Section III, 1974 Editionno Addenda [1]* The ASME Code, Section I11, 1995 Edition up to and including 1997 Addenda [2] is used for the designanalysis/qualification of the Replacement Instrument Nozzle" The ASME Code, Section III, 1998 Edition up to and including 2000 Addenda [3] is used forprocurement, fabrication, and examination of the Replacement Instrument Nozzle* The ASME Code Section XI program is governed by the 2001 Edition up to and including the 2003Addenda [4]This project involves both repair and replacement activities in accordance with ASME Code Section XI [4]per Article IWA-4220, "Code Applicability," as it is defined as a Code Class 1 item. Article IWA-4221(a)of Section XI states that:An item to be used for repair/replacement activities shall meet the Owner's Requirements. Owner'sRequirements may be revised, provided they are reconciled in accordance with IWA-4222.Reconciliation documentation shall be prepared. Westinghouse Non-Proprietary Class 3Page 4 of 10Our ref: LTR-ME-15-30-NP, Rev. 2July 7, 2015Additionally, Article IWA-4221 (c) states:As an alternative to (b) above, the item may meet all or portions of the requirements of differentEditions and Addenda of the Construction Code, or Section III when the Construction Code was notSection III, provided the requirements of IWA-4222 through IWA-4226, as applicable, are met.Construction Code Cases may also be used. Reconciliations required by this Article shall bedocumented.4.1 IWA-4222 Reconciliation of Code and Owner's Requirements(a) (1) States that: "Only tecbnical requirements that could affect materials, design, fabrication, orexamination, and affect the pressure boundary, or core support or component support function, needto be reconciled. "4.1.1 Owner's Design RequirementsThere is no change to the design requirements since the instrument nozzles are considered a replacement andas such the design requirements in the design specification [5] remain unchanged. Therefore, there are nochanges in the design parameters (e.g., design pressure, normal operating pressure, design temperature, noload temperature, normal operating inlet water temperature, and normal operating outlet water temperature).4.2 IWA-4223 Reconciliation of Components(a) States that. "Reconciliation of later Editions or Addenda of the Construction Codes or alternativeCodes as permitted by IWA-4221 is not required. The Owner shall evaluate any changes in weight,configuration, or pressure-temperature rating in accordance with IWA-431i. "This article does not apply to this replacement. The Replacement Instrument Nozzle is reconciled underparagraph IWA-4225.4.3 IWA-4224 Reconciliation of MaterialIWA-4224.1 Identical Material Procured to a Later Edition or Addenda of the Construction Code, SectionIII, or Material SpecificationIWA-4224.2 Identical Material Procured to an Earlier Construction Code Edition or Addenda or MaterialSpecificationIWA-4224.3 Use of a Different MaterialIWA-4224.4 Substitution of Material Specifications Westinghouse Non-Proprietary Class 3Page 5 of 10Our ref: LTR-ME-15-30-NP, Rev. 2July 7, 20154.3.1 Instrument Nozzle MaterialsThe Replacement Instrument Nozzle is fabricated from SB-166 Alloy UNS N06690 material certified to the1998 Edition including the 2000 Addenda of the Code. Alloy N06690 is an improved Nickel alloy material,which has an improved resistance to Primary Water Stress Corrosion Cracking as compared to Alloy N06600which is the original material for the Instrument Nozzle. This is considered a different material since AlloyN06690 material did not exist as an alternative in the Original Construction Code, which only included AlloyN06600.Welding material used to weld the Replacement Instrument Nozzle to the RCP case and nozzle remnant isERNiCrF-7A (Alloy 52M UNS N06054) weld filler metal [10]. Like for the SB-166 Alloy UNS N06690material, this material did not exist as an alternative in the Original Construction Code.4.3.2 Materials RequirementsBased on the material specifications described above, only the requirements of IWA 4224.3 apply to theReplacement Instrument Nozzle.IWA-4224.3 -Use of a Different Material, states that:(a) Use of materials of a specification, grade, type, class, or alloy, and heat-treated condition, otherthan that originally specified, shall be evaluated for suitability for the specified design and operatingconditions in accordance with IWA-4311.(b) Material examination and testing requirements shall be reconciled to the Construction Coderequirements of the item.4.3.3 Materials EvaluationAlloy N06690 is an improved Nickel alloy material, which has an improved resistance to Primary WaterStress Corrosion Cracking as compared to Alloy N06600. As previously indicated, SB-166 Alloy UNSN06690 material did not exist as an alternative in the Original Construction Code. Therefore, no directcomparison can be made between the Original Construction Code and the Procurement Code for thismaterial. In terms of the Original Construction Code Alloy N06600 is used. Table 1 shows a comparison ofallowable stresses and material properties between the Construction and Procurement and as well as theAnalysis Codes (1995 up to an including the 1997 Addenda) which is used as the basis for theanalysis/qualification (CN-MRCDA-15-13). Westinghouse Non-Proprietary Class 3Page 6 of 10Our ref: LTR-ME-15-30-NP, Rev. 2July 7, 2015Table 1: Comparison of Allowables and Material PropertiesMaterial SB-166, N06600 [1] SB-166, N06690 SB-166, N06690 [3]Code Year 1974-No Addenda 1995-A'97 1998-A'00Property/AllowableSm (ksi) at 700'F 23.3 23.3 23.3Sm (ksi) at 650'F 23.3 23.3 23.3E (ksi) at 70'F 31,700 30,300 30,300cc (in/in/°F) at 70'F 7.13 x 10.6 7.7 x 10.6 7.7 x 10.6Table 1 shows that the allowable stress values for the Replacement Instrument Nozzle materials are the sameas the allowable stress values of the Original Construction Code for the existing material. The values of the1995 ASME Code Edition are added to reconcile the use of this code edition for the analysis/qualification aspart of CN-MRCDA-15-13. Table 1 also indicates slight differences between the Construction and the laterCodes in the material property a and E values. The differences may result from the chemical compositionchanges associated with the change in material and over time span of the Code editions. Differences mayalso result from the change in product form from the original to the replacement material. The differences inmaterial properties are not significant and do not affect the performance of the material or design.The Replacement Instrument Nozzle materials are acceptable for use because the later Code Editions havebeen accepted by the nuclear industry (including the Nuclear Regulatory Commission). The materials aresimilar in composition to those in the Original Construction Code, are examined and tested to similarrequirements, and are shown to be compatible with the installation and system requirements for the specifieddesign and operating conditions per the analysis/qualification. Therefore, it is concluded that, with respect tomaterial, the later Code Editions are reconciled to the Construction Code and the Owner's Specification.4.3.4 Material Examination and Testing RequirementsPer the requirements IWA-4224.3 (b): "Material examination and testing requirements shall be reconciledto the Construction Code requirements of the item. "In this case, this means the replacement item. The examination and testing requirements of the later editionof the Code are, in general, more stringent than those of the Construction Code; therefore, they envelop theConstruction Code. In particular, the later Code is more prescriptive in requirements for qualification ofnondestructive examination personnel. For the replacement project, other changes in the examinationrequirements are editorial in nature. Therefore, it is concluded that, with respect to examination and testingrequirements, the use of the later Code is reconciled to the requirements of the Construction Code for allreplacement materials.4.4 IWA-4225 Reconciliation of Parts, Appurtenances, and Piping Subassemblies(a) Parts, appurtenances, and piping subassemblies may be fabricated to later Editions and Addenda ofthe Construction Code and later different Construction Codes, as permitted by IWA-4222(b), Westinghouse Non-Proprietary Class 3Page 10 of 10Our ref: LTR-ME-15-30-NP, Rev. 2July 7, 20155.0 References1. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," 1974 Edition,no Addenda.2. ASME Boiler and Pressure Vessel Code, Section III, "Rules for Construction of Nuclear Power PlantComponents," 1995 Edition Up to and Including 1997 Addenda.3. ASME Boiler and Pressure Vessel Code, Section III, "Rules for Construction of Nuclear Power PlantComponents," 1998 Edition Up to and Including 2000 Addenda.4. ASME Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear PowerPlant Components," 2001 Edition Up to and Including 2003 Addenda.5. Westinghouse Design Specification 14273-PE-480, Rev. 06, "Project Specification for Reactor CoolantPumps for Arizona Nuclear Power Project Units 1, 2 and 3," dated November 11, 2003.6. Westinghouse Drawing, C-14473-220-002, Rev. 0, "Replacement Pressure Tap Nozzle."7. Westinghouse Drawing, E-14473-220-001, Rev. 0, "Pump Casing -A, Pressure Tap NozzleModification Assembly."8. Westinghouse Drawing, E-8111-101-2002, Rev. 00, "Pump Casing -A."9. Arizona Public Service Order No. 500592766, dated 4/10/2015.10. PCI Weld Procedure Supplement 143-F43 MN-GTA/SMA, Rev. 0, dated 01/08/97.11. ASME Code Case N-474-2, "Design Stress Intensities and Yield Strength Values For UNS N06690 witha Minimum Specified Yield Strength of 35 ksi, Class 1 Components Section III, Division 1", ApprovalDate December 9, 1993. EnclosureNon-proprietary Documents for Relief Request 53Attachment 6Westinghouse Calculation CN-NPE-06-03-NP, Rev. 1, Plant X-Structural Evaluations of the RCP Pressure Tap Nozzles Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision Shop Order Number Charge Number PageCN-NPE-06-XXXX-03-NP 1 NA 2400588 INTG IProject Releasable (Y/N) Open Items (Y/N) Files Attached (Y/N) Total No. PagesPlant X RCP Project Y N Y 219Title: Plant X -Structural Evaluations of the RCP Pressure Tap NozzlesAuthor(s) Name(s)K. H. HaslingerSignature / DateN/AFor PagesAllVerifier(s) Name(s)R. F. RaymondSignature / DateN/AFor PagesAllManager NameJ. W. LeavittSignature / DateN/APreparerSarah E. LaxReviewerEarnest S. ShenJeffery R. StackSignature / DateElectronically Approved*Signature / DateElectronically Approved*Electronically Approved*For PagesNon-Proprietary Class 3For PagesNon-Proprietary Class 3Non-Proprietary Class 3Owning ManagerJames P. Burke for Carl J.GimbroneSignature / DateElectronically Approved*For PagesNon-Proprietary Class 3*Electronically approved records are authenticated in the electronic document management system.@2015 Westinghouse Electric Company LLCAll Rights Reserved(OWestinghouseWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 2Record of RevisionsRev Date Revision Description0 08/27/2009 Original Issue1 3/16/2010 References 2, 11 and 13 were updated to Revisions 4, 2 and 1, respectively. AffectedPages: Cover, 2, 10, 97 and 98.1 See EDMS This -NP version adds proprietary brackets and the proprietary information has beenredacted.4 I.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 3Table Of Contents1 .0 In tro d u c tio n ............................................................................................................................... 1 01.1 Background/ Purpose .................................................................................................. 101.2 Limits of Applicability .................................................................................................... 101.3 SER Constraints ........................................................................................................... 101.4 Documentation Overview ............................................................................................. 102.0 Summary of Results and Conclusions ................................................................................. 152.1 Primary Stress Result Sum mary ................................................................................. 152.2 Fatigue Analysis Result Summary .............................................................................. 162.2.1 Assuming Negligible External SSE Loads ....................................................... 162.2.2 Considering External SSE Loads ..................................................................... 163.0 Assumptions and Open Items ............................................................................................... 183.1 Discussion of Major Assumptions ................................................................................. 183 .2 O p e n Ite m s ....................................................................................................................... 1 84.0 Acceptance Criteria ................................................................................................................... 194.1.1 Design Conditions ............................................................................................ 194.1.2 Normal and Upset Conditions .......................................................................... 204.1.3 Emergency Conditions (not Specified for this Project) .................................... 214.1.4 Faulted Conditions ........................................................................................... 214.1.5 Test Conditions .................................................................................................. 215.0 Computer Codes Used In Calculation ................................................................................... 226 .0 C a lc u la tio n s ............................................................................................................................... 2 36.1 Method Discussion ........................................................................................................ 236.1.1 Calculation of Stresses in Nozzle ..................................................................... 236.1.2 Calculation of Stresses in the Nozzle Safe End ................................................ 276 .2 In p u t ................................................................................................................................. 2 76.2.1 Geometry Information ...................................................................................... 276.2.2 Material Property Information .......................................................................... 316.2.3 Specified Loads for Plant X RCPs ................................................................... 346.3 Evaluation, Analysis, Detailed Calculations and Results ............................................. 406.3.1 Plant X Pressure Tap Nozzle ANSYS Model .................................................. 406.3.2 Plant X RCP Pressure Tap Nozzle Stress Analysis Results ........................... 53Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 47 .0 R e fe re n c e s ................................................................................................................................ 9 7A ppendix A : C om puter R un Logs ............................................................................................... 98A ppendix B : S upporting D ocum entation ........................................................................................ 107a,c~2Checklist A: Proprietary Class Statem ent Checklist ....................................................................... 215Checklist B: Calculation Note Methodology Checklist .................................................................... 216Checklist C: Verification M ethodology Checklist ............................................................................. 217Additional Verifier's Com m ents ........................................................................................................ 218Custom er Review Com ments and Reconciliations .......................................................................... 219Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 5List of FiguresFigure 1-1 Plant X Reactor Coolant Pump Sectional View ..................................................... 12Figure 1-2 Detail of RCP Pressure Tap Nozzle Located in Discharge Nozzle Safe End ...... 13Figure 1-3 Detail of RCP Pressure Tap Nozzle Weld Pad Size for [ ]a,cC la d d in g ..................................................................................................................... 1 3Figure 1-4 Plant X RCP Discharge Side Pressure Tap Nozzle .............................................. 14Figure 1-5 Plant X RCP Suction Side Pressure Tap Nozzle .................................................. 14Figure 6-1 Main Dimensions of Plant X RCP Discharge Side Pressure Tap Nozzle ............. 28Figure 6-2 Main Dimensions of Plant X RCP Suction Side Pressure Tap Nozzle .................. 28Figure 6-3 Dimensions of Countersink Weld Preparation into Base Metal and SSC la d d in g ..................................................................................................................... 2 9Figure 6-4 Dimensions of [ ]ac Buttering (Yellow), [ Weld(Green) following Installation of Pressure Tap Nozzle (12 mm MinimumW e ld Le ngth) ......................................................................................................... ..2 9Figure 6-5 Pressure Tap Nozzle Showing Region of Interference Fit with Safe EndB o re ............................................................................................................................ 3 0Figure 6-6 IRWST RRS for RCP Components & Appurtenances (H & V-Dir.),]a,c ........................................................................................................................ ....3 7Figure 6-7 SSE RRS for RCP Components & Appurtenances (H & V-Dir.),] ac ............................................................................................................................... 3 7Figure 6-8 Faulted Condition Response Spectra, Global X, Y and Z Axes, HorizontalEnvelope and RSS Spectra, [].,. c ..................................................... 38Figure 6-9 Plant X 3-D RCP Pressure Tap Nozzle ANSYS Model ......................................... 42Figure 6-10 RCP Pressure Tap Nozzle ANSYS Model Close-up View .................................... 42Figure 6-11 RCP Pressure Tap Nozzle, ANSYS Model Details at Nozzle to Weld PadR e g io n ........................................................................................................................ 4 3Figure 6-12 RCP Pressure Tap Nozzle, Cladding and Shell Materials at Nozzle to PadW e ld R e g io n ......................................................................................................... ..4 3Figure 6-13 RCP Pressure Tap Nozzle, Nozzle Shank/Tip Modeling Details ........................... 44Figure 6-14 ANSYS Pressure Tap Nozzle Model Areas at Nozzle to Pad Weld Region ..-....... 44Figure 6-15 Plant X ANSYS Pressure Tap Nozzle Model Boundary Conditions ..................... 45Figure 6-16 Close-up View of Boundary Conditions at RCP Pressure Tap Nozzle to PadW e ld R eg io n ......................................................................................................... ..4 6Figure 6-17 ANSYS RCP Pressure Tap Nozzle Model Cuts, Through Nozzle [ and Along Weld Seam [ ]ac ....................................................... 48Figure 6-18 Nozzle Tip Analysis Path Locations, Plant X RCP Pressure Tap Nozzle ............. 49Figure 6-19 Plant X RCP Pressure Tap Nozzle Safe End Cut Locations PipeAxi andP ip e _ R a d ................................................................................................................... 5 0Figure 6-20 Plant X RCP Pressure Tap Nozzle, Applied Internal Pressure (Red) andBlow-off (Blue and Yellow) Load Vectors .............................................................. 51Figure 6-21 Plant X RCP Pressure Tap Nozzle, Close-up View of Applied Pressures ............ 51Figure 6-22 Overall Stress Intensity Profile due to Design Pressure and TemperatureC o n d itio n s .................................................................................................................. 6 7Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 6Figure 6-23Figure 6-24Figure 6-25Figure 6-26Figure 6-27Figure 6-28Figure 6-29Figure 6-30Figure 6-31Stress Intensity Profile due to Design Pressure and Temperature Conditions ..... 68Linearized Stress Graph at Safe End Location [121 ................. 69Linearized Stress Graph at Safe End Location [.............. 69Temperature Profiles During Plant Heatup, [ ],. ..........................76Temperature Profiles During Plant Heatup, [ ]c.................................... 77RCP Pressure Tap Nozzle Stress Intensity Profile, Heatup at [ ]a.c OF andI Ia'c P s i ............................................................................................................... 7 8RCP Pressure Tap Nozzle Stress Intensity Profile, Heatup at [ ]a'c OF and]ac P s i ................................................................................................................ 7 8General Stress Intensities during Heatup Transient, [ ]..........79General Stress Intensities during Heatup Transient, [ ,........................ 80Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 7List of TablesTable 2-1 Results of Primary Stress Evaluation for Plant X Pressure Tap Nozzles(Excluding Effects from External Loads) ................................................................ 15Table 2-2 Fatigue Usage Factor Summary for Plant X RCS Pressure Tap Nozzle ............. 16Table 2-3 Summary of Fatigue Usage Factor Not Considering and ConsideringContributions from External Nozzle Loads ............................................................ 17Table 5-1 Summary of Computer Codes Used in Calculation ................................................ 22Table 6-1 RCP Casing and Nozzle Safe End Shell Material Properties ............................... 31Table 6-2 RCP Pressure Tap Nozzle, Weld and Weld Pad Material Properties .................... 32Table 6-3 RCP Pressure Housing Cladding Material Properties ............................................ 32Table 6-4 RCP Pressure Tap Nozzle Material Property Summary for 650 OF ........................ 33Table 6-5 ASME Code Fatigue Strength Properties for [ ]a-c Nozzle andW eld P ad M aterials ............................................................................................. ..33Table 6-6: External Nozzle Load Criteria for RCP Pressure Taps [12] .................................. 35Table 6-7 Definition of Normal, Upset, Emergency, Faulted and Test TransientC o n d itio n s .................................................................................................................. 3 9Table 6-8 Association between Cuts, Keypoints and Nodes at Inside Weld .......................... 47Table 6-9 Association between Cuts, Keypoints and Nodes at Nozzle Shank/Tip ................ 49Table 6-10: Load Cases for Primary Stress Analysis ................................................................. 53Table 6-11: Results of Primary Stress Evaluation for RCP Pressure Tap Nozzles,Pressure and Temperature Effects ....................................................................... 56Table 6-12 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I 'Design Pressure and Temperature Conditions ..................................................... 57Table 6-13 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I 'Design Pressure and Temperature Conditions ..................................................... 58Table 6-14 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I ,Design Pressure and Temperature Conditions ..................................................... 59Table 6-15 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ ]B'CDesign Pressure and Temperature Conditions ..................................................... 60Table 6-16 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I ,Design Condition without Temperature Effects ..................................................... 61Table 6-17 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I ,U pset C ondition .................................................................................................... ..62Table 6-18 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I ,T est C ond ition ...................................................................................................... ..6 3Table 6-19 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [ I ,Faulted C ondition ................................................................................................. ..64Table 6-20 Zero-Period-Acceleration Levels for Faulted Events and Resulting NozzleLoads and Stresses .............................................................................................. .66Table 6-21 Properties for RCP Pressure Tap Nozzles ............................................................ 66Table 6-22 Linearized Stress Results, Free-Field RCP Inlet/Outlet Nozzle Safe End[]a,, Design Pressure and Temperature ......................................... 70Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NPP 1 8Table 6-23 Linearized Stress Results, Free-Field RCP Inlet/Outlet Nozzle Safe EndI ]ac,, Design Pressure and Temperature ......................................... 71Table 6-24 Description of Transient Events with Event ID Numbers ...................................... 82Table 6-25 Plant X RCP Pressure Tap Nozzle Fatigue Usage Factor for [ ]a,cCombinations of Heatup and Cooldown Pressure (High and Low)C o n d itio n s .................................................................................................................. 8 3Table 6-26 Plant X RCP Pressure Tap Nozzle Maximum Fatigue Usage FactorSummary with all Fatigue Strength Reduction Factors equal to [ ]a,c ................... 83Table 6-27 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside NodeI ]a c, Through Nozzle [ ]a-c, LP Heatup & HP Cooldown ............... 84Table 6-28 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle OutsideNode [ ]a, c Through Nozzle [ ]a,', LP Heatup & HPC o o ld o w n ................................................................................................................... 8 4Table 6-29 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside NodeI la,]a Through Nozzle [ ],c, LP Heatup & HP Cooldown ............. 85Table 6-30 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle OutsideNode [ Through Nozzle [ ] c, LP Heatup & HPC o o ld o w n ................................................................................................................... 8 5Table 6-31 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside NodeI Iac]a, Through Nozzle [ ]a,, LP Heatup & HP Cooldown ............... 86Table 6-32 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle OutsideNode [ ]a,c, Through Nozzle [ ]a,c, LP Heatup & HPC o o ld o w n ................................................................................................................... 8 6Table 6-33 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside NodeI Ia.],c, Through Nozzle [ I ac, LP Heatup & LP Cooldown ........... 87Table 6-34 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle OutsideNode [ ]a,c, Through Nozzle [ ] ,c LP Heatup & LPC o o ld o w n ................................................................................................................... 8 7Table 6-35: Summary of Primary Membrane plus Bending Stress Ranges for all FatigueR u n s ........................................................................................................................... 8 8Table 6-36 Summary of Fatigue Usage Factor Not Considering and ConsideringContributions from External Nozzle Loads ............................................................ 90Table 6-37 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Inside Node [ ]ac, Through Nozzle [I .................. 91Table 6-38 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Outside Node [ ]a,c, Through Nozzle [ ]a"' ................ 91Table 6-39 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Inside Node [ ]5C, Through Nozzle [ I ............... 92Table 6-40 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Outside Node [ ]ac, Through Nozzle [ ]a, .............. 92Table 6-41 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Inside Node [ ]ac, Through Nozzle [ ]a c, LPH eatup & H P C ooldow n ........................................................................................ ..93Table 6-42 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 9Nozzle Loads, Outside Node [ ]ac, Through Nozzle [ ]a, ............ 93Table 6-43 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Inside Node [ ]ac, Through Nozzle [I a,c ............ 94Table 6-44 Fatigue Usage Factors Considering "Realistic" and "Worst Case" ExternalNozzle Loads, Outside Node [ ]a-c, Through Nozzle [ ] '° ............... 94Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 101.0 Introduction1.1 BACKGROUND /PURPOSEThe Plant X Reactor Coolant Pump (RCP) is shown in Figure 1-1. The components evaluatedin this Calculation Note are the Pressure Tap Nozzles located at the Nozzle Safe Ends of theRCP Suction and Discharge Nozzle Safe Ends (Figures 1-2 through 1-5).The analyses performed include the determination of the primary stress intensities and thefatigue capabilities of the RCP Pressure Tap Nozzles that are located at both the RCP SuctionNozzle Safe End and RCP Discharge Nozzle Safe End. Transient Thermal Analyses wereperformed to determine the stresses due to the operational temperature fluctuations and tocompute the associated fatigue usage factor for the specified life time of the RCPs (60 years).This evaluation was performed in accordance with ASME Code Section III (Reference 4) usingthe ANSYS computer program (Reference 5) and the RCP Design Specification (Reference 2).The ANSYS code was used to develop a 3-dimensional representation of a section of the RCPSuction/Discharge Nozzle Safe End that includes the Pressure Tap Nozzle. This model wasused to determine the nozzle shank, the nozzle/weld interface, and the "free field" shell stressesdue to internal RCP pressure. This model was also used to perform all the required stress (dueto pressure) and thermal transient analyses according to the ASME Code.Revision 1 updates Reference 2 to Revision 4, Reference 11 to Revision 2, Reference 12 toRevision 3, and Reference 13 to Revision 1. There was no impact on the previouslydocumented results. Also, none of the computer runs changed. However, for convenience, thecomputer runs are also attached to this document revision.This calculation note was prepared according to Westinghouse Procedure NSNP-3.2.6.1.2 LIMITS OF APPLICABILITYThe results contained in this Calculation Note are applicable to the Plant X Reactor CoolantPumps.1.3 SER CONSTRAINTSThere are no Safety Evaluation Report (SER) Constraints that apply to this Calculation Note.1.4 DOCUMENTATION OVERVIEWThis calculation note is one of a larger number of documents that comprise the evaluations ofthe Plant X RCP pressure boundary and support components. The document numbers andtitles are:Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 11a,cKJWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 12a,cFigure 1-1 Plant X Reactor Coolant Pump Sectional ViewWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 13a,cFigure 1-2 Detail of RCP Pressure Tap Nozzle Located in Discharge Nozzle Safe Endra,c-/Figure 1-3 Detail of RCP Pressure Tap Nozzle Weld Pad Size for []aJc CladdingWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 14ac,KFigure 1-4 Plant X RCP Discharge Side Pressure Tap Nozzlea,cFigure 1-5 Plant X RCP Suction Side Pressure Tap NozzleWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 152.0 Summary of Results and Conclusions2.1 PRIMARY STRESS RESULT SUMMARYAll primary stress intensities are satisfactory and meet the appropriate allowables fromReference 4. The following summarizes these results for each load category. SpecificallyTable 2-1 summarizes the Primary Membrane Stress and the Primary Membrane plus BendingStress results obtained from ANSYS computer runs. These runs for four (4) nozzle locationsdid not consider the effects from external loads, only those from internal pressure. Table 2-2provides the combined (internal pressure, external loads, SSE, BLPB and IRWST inertias loads)Primary Membrane Stress and the Primary Membrane plus Bending Stress results that weredetermined using the ASME Code hand equations. The location of these stresses is at theregion where the Pressure Tap Nozzle shanks exit the narrow annulus (interference fit) with thewall of the RCP discharge/suction nozzle safe ends.Table 2-1 Results of Primary Stress Evaluation for Plant X Pressure Tap Nozzles(Excluding Effects from External Loads)RCP Pressure Tap Nozzles (Pressure and Temperature Effects)faWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 16[be negligible.]a-c. The effects of any Faulted condition, inertia induced loads were shown to2.2 FATIGUE ANALYSIS RESULT SUMMARY2.2.1 Assuming Negligible External SSE LoadsThe fatigue capability of the Suction/Discharge Nozzle Safe End Pressure Tap Nozzles isdemonstrated by meeting the requirements of NB-3222.4 (e), "Procedure for Analysis for CyclicLoading." Specifically, the nozzle was evaluated at two (2) critical "Nozzle" (through-wall) cutsand at two (2) critical "Weld" (along weld seam) cuts. There are no "uphill" or "downhill" effectsat this location since the nozzle penetrates the shell in a perpendicular fashion. The resultingFatigue Usage Factors were determined to be well within the limit of one (1). They aresummarized in Table 2-3.Table 2-2 Fatigue Usage Factor Summary for Plant X RCS Pressure Tap Nozzle~a, cThe NB-3228.5(a) requirement for Primary plus Secondary Membrane plus Bending StressIntensities, excluding thermal bending stresses, to be less than or equal to 3Sm was met in allinstances. The narrowest margin for "through-nozzle" occurs at [ ]a,cwith a Primary Membrane plus Bending Stress Range of [ ]a.c [psi] versus a 3Sm limit of69,900 [psi]. For the "along-weld" cuts, the narrowest margin is [ Iac [psi] versus a 3Smlimit of 69,900 [psi] and occurs at [ Consequently, all requirementsfor stress and fatigue of the Plant X Pressure Tap Nozzles are fully satisfied.2.2.2 Considering External SSE LoadsExternal load limits specified in Reference 12 are used to assess their impact, if applicable, onfatigue. Table 2-3 lists the results and provides a comparison with the Table 2-2 values. Themaximum usage factors are found for the [ ]a,c Disregarding the effectsWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 17from external SSE loads, as may be permitted by NB-3337.3 [4], the maximum usage factor isS ]a,c. Using a "realistic" limit for external SSE loads it increases to [ ]a,c.Assuming "worst" case SSE loads, the usage factor increases to [ ]ac, still well within theallowable of 1.0.Table 2-3 Summary of Fatigue Usage Factor Not Considering and Considering Contributions fromExternal Nozzle LoadsacoWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 183.0 Assumptions and Open Items3.1 DISCUSSION OF MAJOR ASSUMPTIONSThere are no Major Assumptions associated with this Calculation Note.3.2 OPEN ITEMSThere are no Open Items associated with this Calculation Note.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 194.0 Acceptance CriteriaThe acceptance criteria for this Calculation Note are the Analysis Requirements for the Plant XReactor Coolant Pump in accordance with ASME Code Section III of Reference 4, as specifiedin Reference 2.The allowables for Design, Faulted, Normal, Upset, Emergency and Test conditions are asfollows:4.1.1 Design Conditions1. The primary stress intensity (produced by stresses which retain a Pm classification) acrossthe minimum thickness of a section resulting from design pressure and normal operatingplus operational basis earthquake loads shall not exceed Sm at design temperature (NB-3221.1 and NB-3227.5 of Reference 4).2. The average local primary membrane stress intensity (PL) across the thickness of a sectionfrom design pressure and normal operating plus operational basis earthquake loads shallnot exceed 1.5"Sm at design temperature (NB-3221.2 and NB-3227.5 of Reference 4).3. The maximum general or local primary membrane plus primary bending stress intensity (Pm+ Pb or PL + Pb) across the thickness of a section resulting from design pressure plusoperational basis earthquake loads shall not exceed a5Sm at design temperature, where ais defined according to NB-3221.3 of Reference 4 as the lesser of plastic shape factor and1.5.For a thick annular cross section, Reference 7 (Table 1, Case 15) gives the followingformula for the plastic shape factor:16 .ro r, -r,)3.ýr 0r4 -for ro = 12.6 mm and r, = 2.4,5or 6.35 mm,a is 1.69, 1.63 and 1.58, respectively. Use a = 1. 5.4. The triaxial stress, defined as the algebraic sum of the three primary principal stresses,shall not exceed 4 times the tabulated value of Sm (NB-3227.4(a) of Reference 4).Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 204.1.2 Normal and Upset Conditions5. If the pressure for an upset condition exceeds the design pressure, the primary stressintensity shall be limited to the following values from NB-3223(a) of Reference 4.(a) Pm < Sm' 1.1"mSi(b) PL + Pb < "S,' a "1.1"Sm(C) PL < 1.5"Sm' = 1.65"Sm6. A fatigue evaluation for normal operating, upset, and applicable test conditions shall beperformed to demonstrate that the critical components can withstand the specified number ofoperating cycles without failure. Per NB-3222.4 (e), the cumulative usage factor (U) is limitedto:U <. 1.0where m is the number of stress ranges considered, ni is the number of cycles extended forrange i, and N1 is the number of cycles indicated in the fatigue curves.In the evaluation of fatigue, sometimes a Simplified Elastic-Plastic Analysis is required asspecified in Section NB-3228.5. This type of analysis is performed when the limit onmaximum range on the primary-plus-secondary stress intensity is exceeded, and therequirements (a) through (f) of NB-3228.5 are met. In particular, requirement (b) of NB-3228.5recommends a factor (Ke) to be applied to the alternating stress range before entering thefatigue curves. This factor is determined from the following expressions:K, = 1.0 => S,<_3S[ (1= 1r +1) (Ke= -3S,, -< S,, < 3mS.,1K, =- = S, > 3mS,nm and n are material constants specified by the ASME Code of Reference.Requirement (a) of NB-3228.5 stipulates that the range of primary plus secondary membraneplus bending stress intensities, excluding thermal bending stresses, shall be < 3Sr.7. The triaxial stress, defined as the algebraic sum of the three primary principal stresses,shall not exceed 4 times the tabulated value of Sm (NB-3227.4(a) of Reference 4).Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 214.1.3 Emergency Conditions (not Specified for this Project)8. For emergency conditions the primary stress limits of NB-3221 shall be satisfied using an Smvalue equal to the greater of 1.2.Sm or Sy (NB-3224). For ferritic material, the Pm elasticanalysis limits for pressure alone shall be equal to the greater of 1.1 Sm or 0.9.Sy.9. The triaxial stress, defined as the algebraic sum of the three primary principal stresses,shall not exceed 4 times the tabulated value of Sm (NB-3227.4(a) of Reference 4).4.1.4 Faulted Conditions10. The primary membrane stress intensity (Pm) for the minimum thickness of a sectionresulting from faulted condition loads (Level D Service Limits) shall not exceed the lesser of2.4Srm or 0.7.S, for austenitic material or 0.7-Su for ferritic material at design temperature(NB-3225 and Appendix F, F-1331).11. The local primary stress intensity (P,) across the thickness of a section resulting from faultedcondition loads shall not exceed the lesser of 1.5. (2.4"Sm) or 1.5.(0.7.S,) for austeniticmaterial or 1.5.(0.7.Su) for ferritic material at design temperature (NB-3225 and Appendix F,F-1331).12. The primary stress intensity (PL+Pb) across the thickness of a section resulting from faultedcondition loads shall not exceed a value equal to, or the lesser of 1.5.(2.4.Sm) or 1.5.(0.7-Su)for austenitic material or 1.5.(0.7.Su) for ferritic material at design temperature (NB-3225 andAppendix F, F-1331).4.1.5 Test Conditions13. Hydrostatic test condition -NB-3226 of Reference 4(a) Pm:_ 0.90.Sy(b) Pm + Pb < 1.35.Sy when Pm < 0.67.Sy(c) Pm + Pb < (2.15.Sy -1.2"Pm) when 0.67-Sy < Pm < 0.90"Sy (Sy at test temperature)Where,Sy = Yield StrengthS, = Ultimate Tensile StrengthSm = Design Stress Intensity14. The triaxial stress, defined as the algebraic sum of the three primary principal stresses,shall not exceed 4 times the tabulated value of Sm (NB-3227.4(a) of Reference 4).Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 225.0 Computer Codes Used In CalculationTable 5-1 Summary of Computer Codes Used in CalculationCode Code Code Configuration Basis (or reference) that supports use of codeNo. Name Ver. Control Reference in current calculation1 ANSYS 11.0 Reference 5 The ANSYS finite element computer code is apublic domain code intended for and usedextensively for static and dynamic finite elementanalyses. The code is used herein for structuraland transient thermal analyses of an RCP nozzleand for computation of ASME code stresses and forevaluating the Fatigue aspect of the design.ANSYS, ANSYS Workbench, AUTODYN, CFX, FLUENT and any and all ANSYS, Inc. brand, product,service and feature names, logos and slogans are registered trademarks or trademarks of ANSYS, Inc. orits subsidiaries in the United States or other countries. All other brand, product, service and featurenames or trademarks are the property of their respective owners.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 236.0 Calculations6.1 METHOD DISCUSSION6.1.1 Calculation of Stresses in Nozzle6.1.1.1 Primary Stress EvaluationPrimary stresses result from pressure and piping reactions applied to the Nozzle forDesign, Upset, Emergency, Faulted and Test Conditions. The classification of theprimary stresses in the nozzle is governed by the limit of reinforcement normal to thevessel wall which is determined in the nozzle sizing calculation. Paragraph NB-3227.5of Reference 4 defines the classification of the stresses inside (ILOR) and outside(OLOR) the limit of reinforcement.OLOR Primary StressesOutside the limit of reinforcement, a Pm classification is applicable to stress intensitiesresulting from general membrane stresses and the average stress across the nozzle dueto externally applied pipe axial, shear and torsional loads (excluding thermal pipe loads).A Pm + Pb classification is applicable to the stress intensities that result from adding Pmstresses to the stresses due to external pipe bending moments (excluding thermal pipeloads). The following classical stress equations apply:OLOR Pm Stress EquationsP + R2NCA =2 ~J2 -AR,-R0PR1t1oR =- P2A _V +VA JOLOR Pm + Pb Stress EquationsCA.+IV t + ("LRA A-o-R A ICH-P9.t1=_p°R 2+V _TTHA =+ _+_-A JWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 24Where:P = Internal Pressure, [ksi]R= Inside Radius of Nozzle (does not include cladding), [in]R= Outside Radius of Nozzle, [in]t = Nozzle Minimum Wall Thickness, [in]N = Axial Load, [kips]V = Shear Load, [kips]M = Bending Moment, [in-kips]T = Torsional Load, [in-kips]Rm = Mean Radius of Nozzle, [in]A = Cross Sectional Area, [in2]J = Torsional Constant, [in4]= Moment of Inertia, [in4]L = Distance between the safe end/pipe interface and the cross section beingevaluated, [in]CA = Axial Stress, [psi or ksi]GN = Hoop Stress, [psi or ksi]OR = Radial Stress, [psi or ksi]THA = Shear Stress, [psi or ksi]ILOR Primary StressesInside the limit of reinforcement, a Pm classification is applicable to stress intensitiesresulting from pressure induced general membrane stresses and stresses due to pipeloads including thermally induced pipe loads (discontinuity stresses are not included).Stress results may be obtained from the ANSYS analyses (it is noted here that theANSYS results include any effects due to geometry discontinuities). The followingclassical stress equations apply:ILOR PM Stress EquationsPR + N+ MR + (V- L)Rm-A IPR.t1o-R = -P+ V + TR.A JILOR PL StressesThe local primary membrane stress intensities for ILOR include the discontinuity effects.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 25The pressure and piping load PL stresses are calculated using the ANSYS finite elementprogram. The linearized membrane plus bending stresses across the nozzle wallthickness for the cuts considered may be obtained from the computer output or bedetermined using simple hand calculations. The computer models may also be used toobtain linearized membrane stresses rather than applying the classical stress equations.6.1.1.2 Computation of Principal Stresses and Maximum Stress IntensitiesThe following describes the method used for determination of the Maximum StressIntensity Values. The Method is based on the Practical Approach to Solve Stress CubicEquations of Reference 15. This method provides results that are consistent with thoseproduced by the ANSYS computer code of Reference 5.from ANSYS Runs:*cr, = Sx = Stress in Global X -DirectionUy = SY = Stress in Global Y -Directiono-z = SZ = Stress in Global Z -Directionrt = Sx, = Shear Stress in Global X -Y PlanerZ -= SYZ= Shear Stress in Global Y- Z Plane, = Sz Shear Stress in Global X- Z PlaneSolution for Determination of the Roots of the Stress Cubic Equation3 -1,72 + -13 = 0WhereI1 =Ox + Cry + O0zI~yo oo oov2 2 212= xG y + z 0 + z -- xy2 -- Tyz _ xzTI3 = uxuyou + 2rxyTgzZXZ -- oxyz2 -CyyTn2 -UzZ"2Expressions for 3- D Stress ValuesCa = 2S[cos(c /3)1+ -I131ab = 2Sfcos[(a /3)+1200 ]}+ 13o-, = 2Sfcos[(a /3)+ 240' ]) + 13Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 26Here the Constants are as follows:S = R)1ax = o-12R=-I -131227Obtain the Maximum SM, and Minimum SM,, for all Sa' Sb and S, PairsThen Maximum Stress Intensity =1 Sm. -SM,,,6.1.1.3 Primary Plus Secondary StressesPrimary plus secondary stresses in the nozzle are produced by internal pressure,applied piping reactions and temperature distributions in the nozzle and adjacentstructure. The pressure and thermal stresses are the equivalent linearized stresses ateach cut obtained from the ANSYS finite element model solution and post-processingroutine. The temperature distributions developed in the primary nozzle thermal analysisare input into the finite element solution with the corresponding primary pressures. Thestresses from the piping loads (if any loads are specified) are calculated by a separatefinite element analysis, and the results are superimposed on the pressure and thermalstresses.The primary plus secondary stress intensity ranges are calculated by introducing thelinearized stresses into the ANSYS fatigue routine, which uses the procedures of NB-3216.2.6.1.1.4 Fatigue EvaluationIn the fatigue evaluation, total stresses, which include primary plus secondary stressesand peak stresses, are evaluated. These stresses are produced by the combination ofinternal pressure, thermal loads, and external piping loads. The ANSYS Post1 FatigueModule is used for post-processing the stresses for the ASIVME Code evaluation.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 276.1.1.5 Application of Pipe LoadsTypically the ANSYS computer program is used to obtain stresses due to externalforces and moments transferred into the safe-end from external piping. []a,c classical expressions can be used for evaluating their contributions to Normal,Upset and Faulted Load Conditions. Reference 12 determined the limit criteria forexternal loads. They are listed here in Section 6.3.2.1.6.1.2 Calculation of Stresses in the Nozzle Safe EndThe "free field" stresses in the Nozzle Safe End were not a direct objective of this calculationnote. Nevertheless, the Linearized Stresses were obtained interactively for the DesignCondition at two (2) cuts and are provided for general information and comparison with resultstypically obtained by hand calculations. No transient evaluations were performed for theDischarge Nozzle Safe End sections.6.2 INPUT6.2.1 Geometry InformationAll geometry and materials data were obtained from the Plant X Reactor Coolant Pump DesignDrawings of Reference 3.Figures 6-1 and 6-2 show the main dimensions for the Plant X RCP Nozzle Safe End PressureTap Nozzles. It is seen that the Suction side nozzle is somewhat shorter and has a "bulkier" tipconfiguration (distance between nozzle end and centerline of exterior line connection is onlyI ]ac [mm], Figure 6-2, compared with [ ]a,c [mm], Figure 6-1). Furthermore, the insidebore diameter of [ ]`c [mm] is less that the [ ]a,c [mm] bore for the Discharge side nozzle.Consequently analysis of the Discharge side nozzle is conservative and, therefore, covers bothnozzle configurations.Figures 6-3 and 6-4 show details of the weld preparation machining of the base metal and theI ].,c Buttering and Weld sections following installation of the Pressure Tap Nozzle.Figure 6-5 shows the internal nozzle support arrangement provided by the specified clearanceswith the bore in the Safe End shell.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 28a,cFigure 6-1 Main Dimensions of Plant X RCP Discharge Side Pressure Tap Nozzlea,cKFigure 6-2 Main Dimensions of Plant X RCP Suction Side Pressure Tap NozzleWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 29-\acK-Figure 6-3 Dimensions of Countersink Weld Preparation into Base Metal and SS Cladding-a,c-IFigure 6-4 Dimensions of [ ]a"c Buttering (Yellow), [ ]a.c Weld (Green) followingInstallation of Pressure Tap Nozzle (12 mm Minimum Weld Length)Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 30a~cFigure 6-5 Pressure Tap Nozzle Showing Region of Interference Fit with Safe End BoreWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 316.2.2 Material Property InformationThe material properties were obtained from Reference 9 of the 1995 Section II ASME CodeEdition with 1996 and 1997 Addenda which, per the Design Specification (Reference 2), providethe Material Specifications and Properties for the Plant X Reactor Coolant Pump. The tablescited in the following Tables 6-1 through 6-4 refer to those of Reference 9.6.2.2.1 RCP Casing and Nozzle Safe End Shell Material: ASME SA-508, Grade 3 Class 1Table 6-1 RCP Casing and Nozzle Safe End Shell Material PropertiesTemp. TC TD pCp p Cp a E Su Tensile Sy Yield Sn,('F) TableTCD TableTCD (Btu / ft3-°F) (lbs/ft3) (Btu / lb-°F) Table TE-1 Table TM-1 Table U Table Y-1 Table 2A(p. 603) tP 6°3 _____ pp. 588-589) (p. 614) (pp. 434-435) (pp. 504-507) (pp.304-306)70 21.8 0.420 51.90 483.8 0.107 6.41 27.8 80.0 50.0 26.7100 22.0 0.415 53.01 483.8 0.110 6.50 27.6 80.0 50.0 26.7150 22.3 0.407 54.79 483.8 0.113 6.57 27.4 80.0 48.6 26.7200 22.4 0.399 56.14 483.8 0.116 6.67 27.1 80.0 47.2 26.7250 22.4 0.390 57.44 483.8 0.119 6.77 26.9 80.0 46.3 26.7300 22.4 0.382 58.64 483.8 0.121 6.87 26.7 80.0 45.3 26.7350 22.4 0.373 60.05 483.8 0.124 6.98 26.4 80.0 44.9 26.7400 22.3 0.364 61.26 483.8 0.127 7.07 26.1 80.0 44.5 26.7450 22.1 0.355 62.25 483.8 0.129 7.15 25.9 80.0 43.9 26.7500 22.0 0.345 63.77 483.8 0.132 7.25 25.7 80.0 43.2 26.7550 21.8 0.335 65.07 483.8 0.134 7.34 25.5 80.0 42.6 26.7600 21.5 0.325 66.15 483.8 0.137 7.42 25.2 80.0 42.0 26.7650 21.3 0.315 67.62 483.8 0.140 7.52 24.9 80.0 41.4 26.7700 21.0 0.305 68.85 483.8 0.142 7.59 24.6 80.0 40.6 26.7TC is Thermal Conductivity, Btuthr-ft-°FTD is Thermal Diffusivity, ft?/hrp is Density (lIb/ft3)Cp is Specific Heat (Btu / Ib-°F)PCp is Density x Specific Heat = TC I To (Btu / ft3-°F )Su, Sy, S. in Units of [ksi]TD = TC (Btulhr-ft-'F)Density (lb/ft ) x Specific Heat (Btu / Ib-°F)I3/4Ni-1/2Mo-CVa is Mean Coefficient of Thermal Expansion X 10- (in./in./°F) in going from 70'F to Indicated Temperature.E is Modulus of Elasticity x 106 psiChecked by DEK, 2/f 7/09Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 326.2.2.2 RCP Pressure Tap Nozzle, Weld and Weld Pad Material: ASME SB-166 (UNS N06690)and ASME SB-168 (UNS N06690)Table 6-2 RCP Pressure Tap Nozzle, Weld and Weld Pad Material PropertiesTemp. TC TO pCp p Cp a E Su Tensile Sy Yield So(°F) TableTCD TableTCD (Btu/ ft3-'F) (lbs/ft3) (Btu / Ib-°F) Table TE-4 Table TM-4 Table U Table Y-1 Table 2B(p. 608) (p. 608) TC/TD (pp. 596-597) (p. 617) (pp. 420-421) (pp. 572-575) (pp. 370-372)70 6.8 0.125 54.40 506.3 0.107 7.73 30.3 80.0 35.0 23.3100 7.0 0.128 54.69 506.3 0.108 7.76 30.1 80.0 35.0 23.3150 7.3 0.131 55.73 506.3 0.110 7.80 29.8 80.0 33.9 23.3200 7.6 0.134 56.72 506.3 0.112 7.85 29.5 80.0 32.7 23.3250 7.9 0.137 57.66 506.3 0.114 7.89 29.3 80.0 31.9 23.3300 8.2 0.140 58.57 506.3 0.116 7.93 29.1 80.0 31.0 23.3350 8.5 0.144 59.03 506.3 0.117 7.98 29.0 80.0 30.4 23.3400 8.8 0.147 59.86 506.3 0.118 8.02 28.8 80.0 29.8 23.3450 9.1 0.151 60.26 506.3 0.119 8.06 28.6 80.0 29.3 23.3500 9.4 0.153 61.44 506.3 0.121 8.09 28.3 80.0 28.8 23.3550 9.7 0.157 61.78 506.3 0.122 8.13 28.2 80.0 28.4 23.3600 10.0 0.161 62.11 506.3 0.123 8.16 28.1 80.0 27.9 23.3650 10.3 0.164 62.80 506.3 0.124 8.20 27.9 80.0 27.4 23.3700 10.6 0.167 63.47 506.3 0.125 8.25 27.6 80.0 27.0 23.3TC is Thermal Conductivity, Btu/hr-ft-°F Su, Sy, S, in Units of [ksi] l72Ni-15Cr-8FeTD is Thermal Diffusivity, ft2lhrp is Density (Ib/ft') TO = TC (Btu/hr-ft-°F)Cp is Specific Heat (Btu / lb-°F) Density (Ib/ft ) x Specific Heat (Btu / lb-°F)pCp is Density x Specific Heat = TC / TO (Btu / ft'-Fra is Mean Coefficient of Thermal Expansion x 10.0 (in./in.F) in going from 70°F to Indicated Temperature.E is Modulus of Elasticity x 106 psi Checked by DEK. 2/18/09Notes: SB-166 and SB-168 have identical Properties, SB-166 is for the Nozzle, SB-168 is for the Weld.Alloy 690 Weld Metal (Alloy 152 or Alloy 52)6.2.2.3 RCP Cladding Material: ASME SA-240, Type 304LTable 6-3 RCP Pressure Housing Cladding Material PropertiesTemp. TC TD pCp p Cp a E Su Tensile Sy Yield* Si,(°F) TableTCD TableTCD (Btu / ft3-F) (Ibs/ft3) (Btu / lb-°F) Table TE-1 Table TM-1 Table U Table Y-1 Table 2A(p. 606) (p. 606) TCiTD _ (pp. 590-591) (p. 614) (pp. 440-441) (pp. 524-527) (pp. 320-322170 8.6 0.151 56.95 501.1 0.114 8.46 28.3 70.0 25.0 16.7100 8.7 0.152 57.24 501.1 0.114 8.55 28.1 70.0 25.0 16.7150 9.0 0.154 58.44 501.1 0.117 8.67 27.9 68.1 23.2 16.7200 9.3 0.156 59.62 501.1 0.119 8.79 27.6 66.2 21.4 16.7250 9.6 0.158 60.76 501.1 0.121 8.90 27.3 63.6 20.3 16.7300 9.8 0.160 61.25 501.1 0.122 9.00 27.0 60.9 19.2 16.7350 10.1 0.162 62.35 501.1 0.124 9.10 26.8 59.7 18.4 16.3400 10.4 0.165 63.03 501.1 0.126 9.19 26.5 58.5 17.5 15.8450 10.6 0.167 63.47 501.1 0.127 9.28 26.2 58.2 17.0 15.3500 10.9 0.170 64.12 501.1 0.128 9.37 25.8 57.8 16.4 14.8550 11.1 0.172 64.53 501.1 0.129 9.45 25.6 57.4 16.0 14.4600 11.3 0.174 64.94 501.1 0.130 9.53 25.3 57.0 15.5 14.0650 11.6 0.177 65.54 501.1 0.131 9.61 25.1 56.6 15.2 13.7700 11.8 0.179 65.92 501.1 0.132 9.69 24.8 56.2 14.9 13.5TC is Thermal Conductivity, Btuthr-ft-'FTO is Thermal Diffusivity, ft/ thrSu, Sy, S, in Units of [ksil* taken for SA-240 Type 304L (conservative)I 18Cr-8Niip is Density (lb/ft3) TO = TC (Btu/hr-ft-°F)Ce is Specific Heat (Btu I lIb-'F) Density (lIb/ft3) x SpecifipCp is Density x Specific Heat = TC / TO (Btu / ftt-°F )a is Mean Coefficient of Thermal Expansion x 1O'c (iniin./°F) in going from 70'F to Indicated Temperature.E is Modulus of Elasficity x 106 psic Heat (Btu I lb-'F)Checked by DEK, 2116/09Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 336.2.2.4 RCP Pressure Tap Nozzle Material Property Summary for 650 OFTable 6-4 RCP Pressure Tap Nozzle Material Property Summary for 650 OFComponent Material ~ Propes at 650 OF (pýe Reference 9)Compor,___nt MaSm [ksi] E [ksl] a [in/inPF]Nozzle Safe End SA-508, Gr. 3 CI. 1 26.7 24.9E3 7.52E-6Nozzle and Weld Pad ASME SB-1 66 23.3 27.9E3 8.2E-6Cladding SA-240, Type 304L01) 13.7 25.1 E3 9.61E-6Note 1: Per Reference 3 ([ ]"'RCP-ES-02), the stainless steel Cladding Material used in the fabrication of the RCP isSS309L/308L. SA-240, Type 304L base material properties are used here since it has equivalent material properties asSS309L/308L weld material for which specific properties are not listed in the ASME Code.6.2.2.5 Fatigue Strength Properties for Nozzle and Weld Pad MaterialsThe Fatigue Strength Properties were obtained from [4, Figure 1-9.2.1 and Tables 1-9.1and 1-9.2.2]. The values used by ANSYS include an E/Ec multiplier of 0.927 to accountfor the ratio of the modulus of elasticity used in the analysis (here Design temperature ofI ]a,c) and the modulus of elasticity of the fatigue design curve temperature at 70°F(NB-3222.4(e)(4), [4]).Table 6-5 ASME Code Fatigue Strength Properties for [ ]a,c Nozzle and Weld Pad MaterialsF a fto~ S tm a g .R ef .4 T a b e -9 1N Ft. 921 EE. atigue CuErve for= 07ozzle and Cladding Malal[ 1S .[p siJ S ,E E d p_ i[ I .E+ (37ii o o .. ........... .345 ,0 Q0400 41,00 7 Ea EOEcold201.000 -.1-9.2,1 & 1 2-2.2.C c)S$3.0 aYE,,200,000 35,S0 33,29410,0000 141D1300I.E÷04 -1,000.000ý ="0 l"6bL 12, 1,+0 1.+210G Z06 1E08 IE 1Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 346.2.3 Specified Loads for Plant X RCPsThe Reference 2 Design Specification is the source for the applicable design data and dynamicloads.6.2.3.1 Design DataMechanical Design DataDesign PressureDesign Temperature[[IIacaxc[psia]rF]Thermal-Hydraulic Design DataNormal Operating PressureNormal Operating PressureNormal Operating Temperature[[[8,caca,c[psia] (at Pump Suction)[psia] (RCS)[rF] (at Pump Suction)Nozzle Safe End Pressure Tap Nozzles LoadsReference 2, Section 6.5.2, specifies the followingnozzles.for Partial Penetration WeldedThe supplier shall provide the load criteria which satisfy the requirements of NB-3337.3of Reference 4. The load criteria shall be defined in terms of axial (FA), shear (Fs),Bending (MB), and Torsional (MT) loading at the end of the nozzle based on a maximumallowable stress of 10% of yield for Class 1 design at the critical section where thenozzle is welded to the component.Reference 12 establishes the load criteria that meet these Section 6.5.2 requirements.They are repeated here in Table 6-6. It is seen that the NOp limits are based on the10% of yield criterion for the weld region. The Faulted criteria are based on primarymembrane stress limits for the nozzle shank section.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 35Table 6-6: External Nozzle Load Criteria for RCP Pressure Taps [121DDS 2 Nozzle Load Criteria for RCP Pressure TapsPakDhcam oul N..,.Mtej'oe!VgssgaSucloma Nomaia Procure Ti.The ferve sad Iouagneat iafck e poke 'A' dull ketmruckno to point 'B"'. The nesultg nozzle loads dhallmet die nmama. nozzle loa~dcnrwmi show below.NOTES. 1, Unit ae kips and inh.ldps,2. All loads an absolute value,3. (4. Lovet D Servec loads do not include pipe rpwur loads in the rupture pipe.5. Zero dewace at Cu 2I6. J-Weld at Cut 1.a,c6.2.3.2 Faulted Design Requirements (Optional)[]ac [Hz]. Consideration ofEarthquake loads is also permitted by paragraph NB-3337.3 of [4].Since, for Plant X, in addition to seismic loads, Reference 2 also specifies BLPB (BranchLine Pipe Break) loads and IRWST (In-Containment Refueling Water Storage Tank)Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 36loads, some consideration of the dynamic effects during Faulted conditions was made.The region of amplification for the IRWST spectra is limited to frequencies below [ ]a,c[Hz]. The BLPB spectra contain amplification up to [ ]ac Hz.The Seismic SSE, BLPB and IRWST spectra were combined in Reference 11 intoFaulted condition spectra. The combination method specified in Reference 2 wasapplied.]a~c However,Figure 6-8 presents the final Faulted condition spectra. The individual, global X, Y andZ direction spectra are plotted. Because of different nozzle orientations with respect tothe global coordinates, the horizontal envelope spectrum is to be applied equally in allthree local component coordinates (conservative).Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 37Figure 6-6 IRWST RRS for RCP Components & Appurtenances (H & V-Dir.), [Figure 6-7 SSE RRS for RCP Components & Appurtenances (H & V-Dir.), [Saca,cIa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 38a,cFaulted Condition Response Spectra, Global X, Y and Z Axes, Horizontal Envelope andRSS Spectra, [ ]a.cFigure 6-8Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 396.2.3.3Table 6-7Normal, Upset, Emergency, Faulted and Test Transient Conditions (Reference 2)Definition of Normal, Upset, Emergency, Faulted and Test Transient Conditionsa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 406.3 EVALUATION, ANALYSIS, DETAILED CALCULATIONS AND RESULTSThe Plant X RCP Nozzle Safe End Pressure Tap Nozzles were evaluated in accordance withASME Code Section III of Reference 4 for specified Design, Faulted, Normal, Upset,Emergency and Test conditions (per Design Specification of Reference 2).6.3.1 Plant X Pressure Tap Nozzle ANSYS Model6.3.1.1 Pressure Tap Nozzle ANSYS ModelThe Discharge Nozzle Safe End Pressure Tap Nozzle is modeled in ANSYS as aI ]a-c representation of the nozzle, [ ]aC weld pad, andRCP Nozzle Safe End section. The entire model is made of ANSYS 3-DStructural Solid Elements []a,cThe Discharge Nozzle Safe End is modeled with a relatively course mesh. Themesh density increases around the nozzle bore as it does for the weld pad. []ac Thefocus of the analysis are the stresses at this weld region, both in the longitudinaldirection along the weld and in the radial direction, originating at the root of theweld and going towards the inside surface of the nozzle.aCThe PRSECT command from ANSYS is used for "linearization" of stresses thatbecome input into the ANSYS fatigue module.a,cFigure 6-9 shows the global model of the Pressure Tap Nozzle ANSYS model.Figure 6-10 shows a close-up view of the nozzle. Figures 6-11, 6-12, 6-13 and6-14 provide detailed information regarding the nozzle to inside pad weld. Theyillustrate the mesh density used for each component, the three (3) differentmaterials used in this region (namely RCP nozzle safe end, pressure tap nozzleand weld pad, and SS cladding materials), and also the "Model Area" patternWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 41used. The weld penetration is identified by the "common" line/surface along thenozzle and the shell inside areas and is a minimum of [ ]a,c [mm] or [ ]a,c [in]long (Reference 3 Drawing 8124-101-2001, Revision 01, Sheet 2 of 2 andProduction Order [6]).Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 42a,cFigure 6-9 Plant X 3-D RCP Pressure Tap Nozzle ANSYS Modela,cFigure 6-10RCP Pressure Tap Nozzle ANSYS Model Close-up ViewWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 43a,cFigure 6-11 RCP Pressure Tap Nozzle, ANSYS Model Details at Nozzle to Weld Pad Regiona,cFigure 6-12RCP Pressure Tap Nozzle, Cladding and Shell Materials at Nozzle to Pad WeldRegionWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 44I-a,cFigure 6-13RCP Pressure Tap Nozzle, Nozzle Shank/Tip Modeling Detailsa,cFigure 6-14ANSYS Pressure Tap Nozzle Model Areas at Nozzle to Pad Weld RegionWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 456.3.1.1.1 ANSYS Model Coordinate SystemThe ANSYS model used for the Plant X Nozzle Safe End Pressure Tap Nozzles uses aGlobal Coordinate System shown in Figure 6-9, with the X-Axis pointing from the Center Lineof the RCP Nozzle Safe End radially outwards through the nozzle, with the Y-Axisrepresenting the discharge pipe centerline toward the RCP outlet, and the Z-Axis followingthe "right-hand" rule. The nozzle stress results are provided in the Local CylindricalCoordinate System 6 with the X-Axis representing the Radial Direction of the Pressure TapNozzle, the Y-Axis representing the Hoop Direction, and the Z-Axis following the axis of theNozzle.6.3.1.1.2 ANSYS Model Boundary Conditionsa,cFigure 6-15 Plant X ANSYS Pressure Tap Nozzle Model Boundary ConditionsWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 46a,cFigure 6-16Close-up View of Boundary Conditions at RCP Pressure Tap Nozzle to Pad WeldRegion6.3.1.2 ANSYS Model Material PropertiesThe material properties used for the 3-dimensional ANSYS model are those provided inSection 6.2.2.6.3.1.3 ANSYS Model Applied Mechanical Load ConditionsExternal force components (e.g., FA, Fv, MB, and MT) are specified in Reference 12.These were applied only to the nozzle shank region since the "narrow" annular regioninside the nozzle/safe-end wall is intended to "unload" the weld region from theseexternal loads. Whereas this radial restriction reduces the effects from both shear forcesand bending moments, it is ineffective to reduce axial force and torsional moment loads.However, these were adequately evaluated as part of the "free-length" nozzle shankevaluation. The stress contribution at the weld region is considered in the fatigueanalysis.For evaluation of the nozzle for Primary Stresses, the Design, Upset and Test conditionsWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 47were evaluated using respective internal pressures of [ ]a,c [psi].The Upset pressure of [ ]axc [psi] occurs during the Upset Transient Event 2. NoEmergency condition is specified. The Faulted condition pressure value is typically]ac [psi]. However, the Faulted Transient Event 2 has a pressure spike as high as[psi]. This "higher" pressure of [ ]ac [psi] has been assumed for all Faultedcondition evaluations; although, this is considered to be "quite conservative".6.3.1.4 ANSYS Model Applied Thermal Transient Load CasesTransient thermal analyses were performed for the Pressure Tap Nozzles usingapproximately twenty (20) transient runs. The transient definitions are provided inAppendix B.1 and are consistent with the listing in Table 6-7. There are no Emergencyevents and the Faulted transients are not considered in the fatigue evaluations. [].,c Hydrostatic Test cycles are specified, ten of which are exempted based onASME code rules. Thus only [ I ax are considered in the fatigue analysis. TheI ]a-c Leak tests are included in the Heatup and Cool Down transients.A Heat Transfer Coefficient of "Infinite" was used for wetted surfaces for all transients.This selection is conservative and reflects the high flow velocities that exist inside theRCP casing.6.3.1.5 ANSYS Model Cut Locations]a,c These controlling cuts are shown inthe following Figure 6-17 and are identified by Key Points. The corresponding NozzleNode Numbers are listed in Table 6-8.Table 6-8 Association between Cuts, Keypoints and Nodes at Inside Weld"-,a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 48_1Figure 6-17ANSYS RCP Pressure Tap Nozzle Model Cuts, Through Nozzle []a.c and Along Weld Seam [ ]a.cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NPP 1 49In order to determine the Primary Membrane and Primary Membrane plus BendingStress Intensities for the nozzle "shank" section, it was evaluated at [ ]",' cuts.Figure 6-18 shows cuts [ ]a-c and [ ]a c at the straight nozzle portions near the"near-zero" gap region with the pipe wall.a~cThe association between Keypoint and Node numbers is given in Table 6-9.Table 6-9Figure 6-18Association between Cuts, Keypoints and Nodes at Nozzle Shank/Tipa,cNozzle Tip Analysis Path Locations, Plant X RCP Pressure Tap NozzleWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 50Figure 6-19 shows two cuts through the RCP Discharge Nozzle Safe End section. Thelinearized stress results for both cuts are provided for general information, and wereobtained from "interactive" analyses for a Design Condition run. These "PIPEAXI andPIPERAD" results represent the "free-field" shell stress conditions in the DischargeNozzle Safe End. Figure 6-20 shows the applied pressure loads on the dischargenozzle safe end and the pressure tap nozzle inside. Figure 6-21 is a close-up view ofthe pressure loading at the pressure tap nozzle inside.a cFigure 6-19 Plant X RCP Pressure Tap Nozzle Safe End Cut Locations Pipe_Axi and Pipe RadWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 51a,cNote, applied Pressure in Units of [psi], Loads in Units of [Ibs]Figure 6-20Plant X RCP Pressure Tap Nozzle, Applied Internal Pressure (Red) andBlow-off (Blue and Yellow) Load Vectors a,cFigure 6-21 Plant X RCP Pressure Tap Nozzle, Close-up View of Applied PressuresWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 526.3.1.6 ANSYS Model Input ListingsThe input listings for the 3-dimensional ANSYS model are included in Appendix B.2.The basic analysis model was generated by "batch" files that called out the following"input" files:acDetailed information about the input and output files for each run is provided in theComputer Run Logs of Appendix A.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 536.3.2 Plant X RCP Pressure Tap Nozzle Stress Analysis ResultsThe primary stresses are calculated from the ANSYS output results obtained from the 3-D FEAmodel for Design Pressure and Temperature conditions. They are also calculated for thevarious Plant Transients. The ANSYS results are comprised of six (6) Membrane and (2x6, forInside and Outside Walls) Membrane plus Bending stress components for each of the []a,c principal cut locations (in the case of the Design Condition, [ ]a,c additional nozzleTip cuts and [ ]a,c Shell cuts were evaluated). The stress criteria and the required loadcases are from References 2 and 4. External loads are from Reference 12. The materialallowables are taken from Reference 9. The following Load Cases of Table 6-10 wereinvestigated:Table 6-10: Load Cases for Primary Stress Analysis(2) LoadCondition Description Loading Components ReferencesI Design Design Pressure + DW Poesign = [ ],[ksi] Ref. 2, Page 112 andDesign Pressure + NOP Ref. 4 Para. NB-3221.1, 2 & 311 Upset NOP + DW Pupset = [ ]a.c(1) Ref. 2, Page 16 and(Level B) Upset Load + OBE(4) [ksi] Ref. 4 Para. NB-3223(a)III Emergency None n/a Ref. 2, Page 113, but(Level C) n/a in this case.IV Faulted NOP +(SSE2 + (IRWST + PNOP = [ ]a.c [ksi] Ref. 2, Page 113 and(Level D) BLPB)2)1/2 PFaulted + TNOP per Ref. 4 Para. NB-3225Level D Transients(3)(5) and Appendix F, F-1331.V Test Test Loading PT-st= [ ]a [ksi] Ref. 2, Page 1125 &Figure 12 and Ref. 4Para. NB-3226Not(1)(2)(3)(4)(5)es:Maximum Pressure during Upset Event -2.SSE, IRWST and BLPB Loads are assumed to be "Zero" for the Inlet/Outlet Nozzle Safe End Pressure Tap Nozzles.Maximum Pressure during Faulted Event -2 is [ ]a,c [ksi]. It is used here, conservatively, for all Faulted ConditionEvaluationsNo OBE Loads are specified by Reference 2.External Nozzle Load Limits are specified in Reference 12.The evaluation of the Pressure Tap Nozzles, located at the Suction and Discharge Nozzles, forPrimary Membrane and Primary Membrane plus Bending stresses was confined to theconditions at the nozzle shank region rather than at the nozzle to interior pad weld location.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 54[]a'C This fact justifies classification of the RCPpressure stresses as Secondary Stresses.In order to satisfy the ASME Code requirements for evaluation of primary membrane andprimary membrane plus bending stresses, [ ]a,c cuts were selected.IaCThese ANSYS runs did not consider the effects from external loads. These results aresummarized in the following Section 6.3.2.1.The combined effects from specified pressure plus specified external loads are evaluated andsummarized in Section 6.3.2.2.The applicable evaluation criteria are repeated as follows:Design ConditionPrimary MembranePer Paragraph NB-3221.1 of Reference 4, the allowable is Pm < Sm. The value of Sm is 23.3 [ksi]for the Nozzle material (Section 6.2.2.5). In addition, the average Local Membrane StressIntensity shall meet the criterion of Paragraph NB-3227.5 of Reference 4. Thus, the allowable isPL < 1.5 Sm = 34.95 [ksi]. The more conservative criterion of Pm shall be used.Primar_ Membrane plus BendingPer Paragraph NB-3221.3 of Reference 4, the Local Primary plus Bending Stress shall notexceed a Sm. Assuming that a equals [ ],ac 1, the allowable becomes Pm + Pb < [ Iac Sim.The value of Sm is 23.3 [ksi] for the Nozzle material (Section 6.2.2.5). This means that theallowable stress is [ ]ac [ksi].Emergency ConditionNo Emergency conditions are specified for the Plant X RCP Pressure Tap Nozzles.Using nozzle dimensions of[ ]"cis used.]a,c mm and [ ]a` mm, a is[]a,c, thus maximum permissible value ofWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 55Faulted ConditionPrimary MembranePer Paragraph NB-3225 of Reference 4, the allowable is the lesser of 2.4Sm or 0.7 Su foraustenitic (Nozzle) material. Using the material properties of Section 6.2.2 (assumed faultedcondition temperature is [ ]a,c OF) we find:0.7 Su = 0.7 x 80.0 = 56.0 [ksi] and 2.4 Sm= 2.4 x 23.3 = 55.92 [ksi] for the Nozzle. The lesservalue is 55.92 [ksi].It is noted that the maximum faulted condition transient pressure of [ ]a'c [psi] is greater thanthe design pressure of [ ]ac [psi].Primary Membrane plus BendingThe Primary Membrane plus Bending stress intensities for the Faulted Load condition must alsobe addressed. Per Paragraph NB-3225 of Reference 4, the allowable at design temperature ofI ]-c OF is the lesser of 1.5 (2.4Sm) or 1.5 (0.7 Su) for non-ferrous (Nozzle) material. Using thematerial properties of Section 6.2.2 we find:1.5 (0.7 Su) = 1.5 x 0.7 x 84.0 = 88.2 [ksi] and 1.5 (2.4 Sm) = 1.5 x 2.4 x 23.3 = 83.88 [ksi] for theNozzle. The lesser value is 83.88 [ksi].Upset ConditionThe [ ]a-c is required to meet the primary stress criteria stated inNB-3223(a) of Reference 4, since the system pressure of [ ]a,c [psi] exceeds the designpressure of [ ]2"C [psi] by 4.2%. However, the allowable stress intensity for the UpsetCondition is 10% greater than that for the Design Condition. Consequently, by satisfying theDesign Condition, assurance is given that the Upset Condition stresses are acceptable.Hydrostatic Test ConditionFor the Hydro Test Condition, the RCP system pressure of [ ]a [psi] is 25% higher than theDesign Pressure of [ ]a,c [psi]. The Primary Membrane Stress allowable, per NB-3226 ofReference 4, is 0.9 x Sy at maximum test temperature of [ ]a, F. Using the materialproperties from Section 6.2.2 we find:0.9 Sy = 0.9 x 28.6 = 25.74 [ksi] for the NozzleWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 566.3.2.1 Linearized Stress Results for the Primary Stress Evaluation for Design, Upset,Emergency, Faulted and Test Conditions for the Nozzle Cuts (Without External LoadEffects)The Table 6-11 stress results are based on the ANSYS computer runs (Tables 6-12through 6-19 provide complete results for Design and representative [ ]a,c results forUpset, Faulted and Test conditions) made at the specified pressures and eventtemperatures. They are identical to those for assumed event temperatures of 70 °F.Use of 70 OF would be permitted according to the ASME code to eliminate the effects ofthermal stresses due to any bi-metallic connections, such as the nozzle shank to safeend welds. This step is not necessary here. It is seen that the Primary Membrane StressCriteria are met for all load cases, Design, Upset, Emergency, and Test.Table 6-11: Results of Primary Stress Evaluation for RCP Pressure Tap Nozzles, Pressure andTemperature EffectsRCP Pressure Tap Nozzles (Pressure and Temperature Effects) a,c_1\Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 57Table 6-12 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [Pressure and Temperature Conditions]a,c Designa cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 58Table 6-13 Linearized Stresses for Plant X RCP Pressure Tap NozzlePressure and Temperature Conditions]a,c, Designa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 59Table 6-14 Linearized Stresses for Plant X RCP Pressure Tap NozzlePressure and Temperature Conditions]a,c, Designa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 60Table 6-15 Linearized Stresses for Plant X RCP Pressure Tap NozzlePressure and Temperature Conditions]a,c, Designa, cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 61Table 6-16 Linearized Stresses for Plant X RCP Pressure Tap NozzleCondition without Temperature Effects]a,c, Designa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 62Table 6-17 Linearized Stresses for Plant X RCP Pressure Tap Nozzle []a,c, Upset Conditiona,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 63Table 6-18 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [Condition]a,c, TestacWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 64Table 6-19 Linearized Stresses for Plant X RCP Pressure Tap Nozzle [Condition]a,c, Faulteda,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 656.3.2.2 Evaluation of the Effects from Faulted Condition Response SpectraThe allowable external nozzle loads were determined in Reference 12 and are providedin Table 6-6. Here only the effects from the Faulted condition spectra are examined.As demonstrated below, the Pressure Tap nozzles have resonance frequencies greaterthan [ ]a,c [Hz]. Using the longer "free nozzle length" geometric properties for thedischarge side pressure tap nozzle (which offsets the somewhat heavier end of thesuction side pressure tap nozzle), the following inertia loads are derived. Refer toAppendix B5 for details regarding the weight and CG properties.Weight of "free" Nozzle Portion [ ]a[c [ibs]Moment due to 1-G Load [ ]a~c [in-lbs]The lowest natural frequency for the "free" portion of the Pressure Tap Nozzle isdetermined by assuming a conservative representation where the entire mass islumped at the nozzle tip and the stiffness is represented by that of the nozzle shanksection with a total (free) length of [ ]ac [mm] or [ ]a-c [in]. The calculation is asfollows:Stiffness of a Cantilever Beam with End Load. k= 3EJ, (Reference 7)13 ,Mass of Free Nozzle Portion. m = Weight/G = [ ]ac/386.4Natural Frequency:f= -l;27r 27r mAssu min g E= [ [lb/in2 ], Modulus of Elasticity1= [ ] [in], Free Lengthj= [ ]a.c fin4], Area Moment of InertiaNatural Frequency f = [ ]`C [Hz], which is well above the FrequencyRanges of Amplification( a, Hz for SSE and IR WS T, and <[ ]jc Hz for BLPB)A conservative Zero-Period-Acceleration (ZPA) value of [ ]a,c Gs is obtained fromFigure 6-8 for the three Faulted Load contributors. Resultant reaction loads are listed inTable 6-20. The table also lists the stress contribution in the nozzle shank due to theinertia loading. It is seen that the contribution to the primary membrane stresses wouldbe less than [ ]` psi. The bending moment stress contribution is [ ]a'c psi. It isWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 66small when compared with the allowable Faulted D stress [ ]a,c ksi of Reference12, which also includes a [ ]ac margin. Thus the inertia load stresses are negligible.Table 6-20 Zero-Period-Acceleration Levels for Faulted Events and Resulting Nozzle Loads andStressesa,cThe nozzle properties are given in Table 6-21.Table 6-21 Properties for RCP Pressure Tap NozzlesWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 676.3.2.3 RCP Suction/Discharge Nozzle Safe End Design Condition StressesThe following provides stress results for the RCP Suction/Discharge Nozzle Safe Enddue to Design Pressure and Temperature Conditions. Figures 6-22 and 6-23 show thestress intensity distributions in the RCP Nozzle Safe End Pressure Tap Nozzles and inthe vicinity of its attachment to the shell. Tables 6-22 and 6-23 provide the LinearizedPrimary Membrane and Primary Membrane plus Bending Stresses through the RCPShell at two locations away from the Weld Pad region (Free Field).acFigure 6-22 Overall Stress Intensity Profile due to Design Pressure and TemperatureConditionsWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NPP 1 68ra,cJFigure 6-23 Stress Intensity Profile due to Design Pressure and Temperature ConditionsWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCRevision1Calculation Note NumberCN-NPE-06-XXXX-03-NP/I-ge69Figure 6-24 Linearized Stress Graph at Safe End Location [Figure 6-25 Linearized Stress Graph at Safe End Location ['a,cJ]a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 70Table 6-22 Linearized Stress Results, Free-Field RCP Inlet/Outlet Nozzle Safe End [Design Pressure and Temperature]a~c,acWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 71Table 6-23 Linearized Stress Results, Free-Field RCP Inlet/Outlet Nozzle Safe End [Design Pressure and Temperature]ac,a ,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 72From the above tables the maximum free-field primary membrane stress intensity in theshell section is [ ]ac [psi]. It is also seen that the stresses at both cuts, asexpected are virtually identical. The "free-field" stress of [ ]a,c [psi] comparesfavorably with a Design Primary Membrane Stress Allowable of [ ]ac [psi]. Theprimary membrane plus bending stress is [ ]ac psi. The allowable is a'Sm orI ]a'C psi.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 736.3.2.4 Fatigue Analysis6.3.2.4.1 Fatigue Analysis MethodologyThe fatigue analysis for the Nozzle Safe End Pressure Tap Nozzles was performed in strictcompliance with the ASME Code of Reference 4. The evaluations were based on the"Elastic" methods and allowed for the "Linearized Elastic-Plastic" methodologies. TheANSYS computer code of Reference 5 was used exclusively for generating the results, withsome minor mathematical manipulations to invoke the "desired" Stress Intensification Factorsfor the [ ]a,c significant nozzle/weld end cuts.The ANSYS model was exercised to compute the transient responses to a total of]a,c transients, the majority, including [ ]ac transient events specified forNormal Operation, [ ]a,c Zero Load Case, [ ]a.C specified for Upset Condition, nonespecified for Emergency Condition, and [ ]a"c Hydro Test cases. Since the ASME Codeonly permits exclusion of [ Iac hydrostatic load cases, [ ]a,c cycles needed to beconsidered here. With respect to the Leak Test cases, these were already accounted for inthe [ ]a'c Heatup/Cooldown cycles.The transient analysis features of the ANSYS computer code first compute the thermaltemperature distributions throughout the model for different steps in time that typically alsosignify changes in temperature and/or pressure conditions. Following the thermalcomputations, the ANSYS code converts the model into "stress" elements and computes theresulting stress information for each specified time step. The thermal results are written tofilename.rth files, and the stress results to filename.rst files for additional processing. ThePOST1 processing consisted of computing the "Linearized Stress" information for each timestep and also of tabulating the Linearized Membrane plus Bending Stress components as afunction of time (steps). These stresses are provided in the Local Cylindrical CoordinateSystem 6 with the following identification:Sx Radial Direction Stresses in NozzleSy Hoop Direction Stresses in NozzleSz Axial Direction Stresses in NozzleSxy Shear Stress in Radial/Hoop PlaneSyz Shear Stress in Hoop/Axial PlaneSxz Shear Stress in Radial/Axial PlaneA Fatigue Stress Intensification Factor (FSIF)2 of [ ]a,c is applied to all [ ]ac weldroot stress components. The [ ]C stress components for the "inside the pressureboundary" nodes had FSIF factors of [ ]ac.2 Fatigue Stress Intensification Factor (FSIF or SIF) is interchangeable with Fatigue Strength Reduction Factor(FSRF).Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 74a,cThe [ ]ac "filename.rst" files were stored in one directory and the "Fatigue"module of the ANSYS code was programmed to retrieve the pertinent information for theI[ ]a'c cut locations, each for both inner and outer nodes. Specifically, the informationwas assembled sequentially for all transient events and within each event, sequentially foreach loading step. The tabular information provided by the ANSYS fatigue module(filename.fatg) consisted of the six linearized membrane plus bending stress componentsand the six peak stress components, as well as the temperature values.I a,cFrom the tabulated ANSYS outputs, all usage factors were compared with the Reference 4limit of one (1). A second ASME Code check requires that the Primary Membrane plusBending Stress Ranges for the load pairings meet the 3Sm criterion (NB-3228.5, Item (a)). Itis realized here that the ANSYS results also include the temperature induced bendingmoment contributions. Therefore, whenever the first 3Sm checks do not pass this criterion,the temperature induced bending stress components are subtracted to demonstratecompliance with the ASME Code criterion of NB-3228.5.Typically, the SSE event is a Faulted Condition event which is not subject to fatigueconsiderations. [acWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 75Using information from Section 6.3.2.2 Table 6-20 it is seen that the Faulted condition inertiastresses are less than [ ]ac [psi]. Consequently it is justifiable to ignore these loadssince the fatigue contribution due to [ ]a,c cycles with [ ]a'c [psi] alternating stress isessentially "zero". Section 6.3.2.4.3 examines the impact of "external" IRWST and SSEpiping loads that may be permitted by Reference 12.Figures 6-26 and 6-27 show the temperature profiles in the Pressure Tap Nozzle and SafeEnd section during the [ ]'l time steps of the Heatup transient with "high" pressure.Figure 6-28 shows the stress intensity profile with the fluid temperature at [ ]a,c OF,immediately after stepping up to [ ] psi pressure. Figure 6-29 shows the stressintensity profile after reaching the maximum operating temperature at the end of the Heatuptransient.Figures 6-30 and 6-31 show the stress intensity profiles in the Pressure Tap Nozzle and SafeEnd section during the [ ]"'° time steps of the Heatup transient with "high" pressure.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N P E-06-XXXX-03-N P 1 76a,cFigure 6-26 Temperature Profiles During Plant Heatup, [I a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 77d,UFigure 6-27 Temperature Profiles During Plant Heatup, []a.cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 78a,cK-Figure 6-28 RCP Pressure Tap Nozzle Stress Intensity Profile, Heatup atFigure 6-29 RCP Pressure Tap Nozzle Stress Intensity Profile, Heatup at []ac OF and [ ]a.c Psia,c]ac OF and []a"c PsiWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 79a,cFigure 6-30 General Stress Intensities during Heatup Transient, [jacWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 80caC4Figure 6-31 General Stress Intensities during Heatup Transient, [Ia,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 816.3.2.4.2 Fatigue Analysis Result Summary (Without SSE)The results from the fatigue analyses for the [ ac cut locations were entered intoTables 6-27 through 6-34 to provide the typical complement of data considered relevant forfatigue evaluations. Table 6-24 identifies the Transient Events. Table 6-25 summarizes theUsage Factors for the [ ]a,c cuts based on Fatigue Strength Reduction Factors (FSRFs)of [ ]a,c for all six (6) Stress Components applied at the outside locations. This tablesummarizes the results for the [ ]` different combinations of "low" and "high" pressureprofiles associated with the heatup and cooldown transients.The usage factors for all locations and load combinations were close to "zero". At]ac Outside location the highest usage factor of [ ],,c occurred for the loadingcombination with low pressure during heatup and high pressure during cooldown. Table 6-26 lists the maximum usage factors for the [ ] cuts.The maximum resulting fatigue usage factors for the [ ]ac "through-nozzle" cuts isI ac for [ ]ac. The maximum fatigue usage factor for the "along-the-weld" cuts is[ ac for [ ]8c, Outside Location. All fatigue usage factors are well within the limit ofone (1). It is, therefore, concluded that the Nozzle Safe End Pressure Tap Nozzles meet theASME Code (Reference 4) fatigue usage factor requirements when subjected to thecomplement of transients specified for the Plant X RCPs in Reference 2.The computed Primary Membrane plus Bending stresses were always less than the 3Sm limit(NB3228.5, Item (a)). The narrowest margin for "through-nozzle" occurs at [ Ia, InsideI Ia',c with a Primary Membrane plus Bending Stress Range of [ ]ac [psi]versus a 3Sm limit of 69,900 [psi]. For the "along-weld" cuts, the narrowest margin is] ac [psi] versus a 3Sm limit of 69,900 [psi] and occurs at [ ]ac Outside]". Table 6-35 summarizes the results for all fatigue analysis runs.Section 6.3.2.4.3 provides a bounding evaluation that considers the effects of external SSEloads that may be permitted by Reference 12.The discussion of Section 6.3.2.4.4 is offered as general information to further demonstrateabsence of any concerns due to Thermal Ratcheting of the Pressure Tap Nozzles toSuction/Discharge Nozzle Safe End Weld region.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 82Table 6-24 Description of Transient Events with Event ID Numbers/I--I/Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 83Table 6-25 Plant X RCP Pressure Tap Nozzle Fatigue Usage Factor for [Heatup and Cooldown Pressure (High and Low) Conditions]a,c Combinations ofa,cTable 6-26 Plant X RCP Pressure Tap Nozzle Maximum Fatigue Usage Factor Summary withall Fatigue Strength Reduction Factors equal to [ ]a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 84/I'-Table 6-27 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside Node []a'c, Through Nozzle [ ]ac, LP Heatup & HP CooldownTable 6-28 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Outside Node []a.c, Through Nozzle [ ]axC, LP Heatup & HP Cooldown-a,c__1>a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 85Table 6-29 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside Node []a.c, Through Nozzle [ ]ax, LP Heatup & HP CooldownK-a cTable 6-30 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Outside Node []a.c, Through Nozzle [ ]a.c, LP Heatup & HP Cooldowna, CKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 86Table 6-31 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside Node-]a,c, Through Nozzle [ ]a'c, LP Heatup & HP Cooldown--a,cJ2Table 6-32 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Outside Node []Jac, Through Nozzle [ ].c, LP Heatup & HP CooldownWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 87Table 6-33 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Inside Node []a~c, Through Nozzle [ ]a.c, LP Heatup & LP CooldownTable 6-34 Fatigue Analysis Summary, Plant X RCP Pressure Tap Nozzle Outside Node []a.c, Through Nozzle [ ]a~c LP Heatup & LP Cooldown.,a,c_1/Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 88raC-ITable 6-35:Summary of Primary Membrane plus Bending Stress Ranges for all Fatigue Runs6.3.2.4.3Fatigue Analysis Result Summary (Including [ ]a~c SSE Cycles)The fatigue evaluations documented in Section 6.3.2.4.2 disregard contributions from anydynamic loads (IRWST, BLPB and SSE). While the effects from IRWST are small, SSEloads can be significant, although being part of the Faulted load complement, they aretypically not considered in the fatigue evaluations. However, the Plant X specification ofReference 2 stipulates consideration of [ ]a,c SSE events (or [ ]a,c SSE Halfcycles) and [ ]",c IRWST discharge cycles. The SSE loads are to cycle about zero, noguideline is provided for the IRWST cycles.In order to determine acceptable interface loads, Reference 2 refers to Section NB-3337.3 [4]and also stipulates that "the external loads be limited to those that produce a maximumallowable stress of 10% of yield at the critical weld section". NB-3337.3 cites that "partialpenetration nozzles shall be used when there are no substantial piping reactions".Furthermore is stated that "earthquake loads need not be considered in determining whetherpiping reactions are substantial".Reference 12 specifies the Pressure Tap Nozzle load criteria. It should be recognized thatthese limit equations are based on Nozzle Strength criteria. Whereas the external NOploads are small, the permitted Faulted loads are quite large. Rather than ignoring thecontributions from the [ ]ac IRWST and the [ ] SSE cycles on fatigue, the followingconservative evaluation was made.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 89The nozzle weld region is considered the weakest portion of the nozzle. For NormalOperation, the permissible external loads are limited by the following equation [12].PL + Pb =1a~cj<0.isy =2.208ks1In further consideration of the effects of [ ]a,, IRWST cycles on fatigue, it is assumed thatthe permitted, total stress intensity of [ ]a-c ksi is additive to the stress intensitiesinvolving all Heatup and Cooldown transient events.With respect to consideration of the SSE event, the following equation [12], providing theexternal Faulted condition load limits, controls:PL + I J,c0.8. (1.05SU -0.5P) = 57.63 ksi]a,cThe stress levels stated so far are based on a "realistic" interpretation of Reference 12.Nevertheless, a "worst" case scenario was added where it is assumed that the external axialforces and torsional moments produce a Faulted stress of [ ]a ksi at the weld. Thisscenario uses the earlier values multiplied by 2.The information of Tables 6-27 through 6-34 was reprocessed by adding both SSE andIRWST stresses and cycles. For convenience all pairings affected by the inclusion of IRWSTor SSE used a fatigue curve based on [ ]a~c OF. The SSE cycles are paired with eachother. Tables 6-37 through 6-44 document the fatigue usage factor computations for the]aC nodes. Table 6-36 summarizes the results and compares them with the fatigueWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 90usage factors computed in Section 6.3.2.4.2 without considering the contributions from theexternal IRWST and SSE loads.Referring to Table 6-36, the maximum usage factors are found for the outside location of]a,c. Disregarding the effects from external SSE loads, as may be permitted by NB-3337.3[4] the usage factor is [ ]a,c. Using a "realistic" limit for external SSE loads it increasesto [ ]a.o. Assuming a "worst" SSE case, the usage factor increases to [ ]a',c stillwell within the allowable of 1.0.Table 6-36 Summary of Fatigue Usage Factor Not Considering and Considering Contributions fromExternal Nozzle Loadsa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 91rTable 6-37 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External Nozzle Loads,Inside Node [ ]a.,c, Through Nozzle [ ]a.cTable 6-38 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External NozzleLoads, Outside Node [ ]c, Through Nozzle [ ]a~ca,cCWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 92Table 6-39 Fatigue Usage Factors Considering "Realistic" and "Worst Case"Loads, Inside Node [ a.c, Through Nozzle [ ]a,cExternal NozzleacTable 6-40 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External NozzleLoads, Outside Node [ ]ac, Through Nozzle [ ]a~cI-jWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 93I-Table 6-41 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External NozzleLoads, Inside Node [ ]a.c, Through Nozzle [ ]axc, LP Heatup & HPCooldownTable 6-42 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External NozzleLoads, Outside Node [ ]a~c, Through Nozzle [ ]a~c-,,,CJ7-->a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 94Table 6-43 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External NozzleLoads, Inside Node [ ]a.c, Through Nozzle [ ]a.c-a,CTable 6-44 Fatigue Usage Factors Considering "Realistic" and "Worst Case" External Nozzle Loads,Outside Node [ ]a8c, Through Nozzle [ ]a~c/I--K1Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 956.3.2.4.4 Thermal Stress Ratchet ConsiderationsThe evaluation of primary plus secondary stress intensity, without thermal bending,addresses a concern for progressive plastic deformation, which could result in unacceptablelevels of distortion, displacement, or wall thinning.The following discussions provide logic for accepting exceedances of the 3Sm criterion for thePlant X RCPs (which is not the case for the Pressure Tap Nozzles). The discussionaddresses in detail why the intent of the ASME Code (Reference 4) is satisfied for thermalstress ratcheting. The same logic is applicable to the primary plus secondary, withoutthermal bending requirements and provides justification for why the intent of the Coderequirement is satisfied (not applicable for the Pressure Tap Nozzles).a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 96arcIn summary,[]a,c the nozzle is not capable of thermal ratcheting. Anyinitial plastic deformation will be self-limiting since the majority of the pressure loading in thenozzle is due to a displacement controlled expansion process, rather than being caused by atrue pressure load application.Again, it is repeated that the Plant X RCP Pressure Tap Nozzles do not violate any of theReference 4 criteria.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 977.0 References1. Not used.2. Plant X Design Specification, XXXXX-FS-DS480, Rev. 04, "Design Specification for ReactorCoolant Pumps," December 29, 2009.3. Westinghouse Design and Manufacturing Drawings for Reactor Coolant Pump.Drawing 8124-101-2001, Rev. 01, "Pump Casing 'A'," (2-Sheets)Drawing 5244, Rev. 00, "Pump Casing -Rough Machining"Drawing 8000-101-2036, Rev. 02, "Nozzle -Pressure, Wall Static"Drawing 8114-101-2008, Rev. 01, "Nozzle- Pressure, Wall Static"Drawing 5150, Rev. 04, "Welding -Joint Identification, RCP Casing"4. ASME Boiler and Pressure Vessel Code, Section III, Nuclear Power Plant Components,1995 Edition with 1997 Addenda.5. "ANSYS 11.0 for XP Release Letter," LTR-SST-08-18, April 1, 2008.6. Production Order "VBM-Machine Casing SIN (1124-A)," Job No. 2400360, Production No.40022009.7. Warren C. Young, "Roark's Formulas for Stress and Strain," 6th Edition, 1989 McGraw-Hill.8. Not used.9. ASME Boiler and Pressure Vessel Code, Section II, Material Specifications, 1997 Editionwith 1997 Addenda.10. ASME Code Case N-474-2, Approval Date, December 9, 1993.11. Westinghouse Calculation Note CN-NPE-06-XXXX-22, Revision 2, "Plant X -ReactorCoolant Pump Transients and Design Loads," dated February 26, 2010.12. Westinghouse Calculation Note CN-NPE-06-XXXX-23, Revision 3, "DDS 2 Nozzle LoadCriteria for RCP Pressure Taps for Plant X Nuclear Power Plant Units X & X," dated March12, 2010.13. Westinghouse Calculation Note CN-NPE-06-XXXX-04, Revision 1, "Plant X -StructuralEvaluation of the RCP Suction Nozzle and Safe End," dated March 8, 2010.14. Not used.15. E. E. Messal, "Finding True Maximum Shear Stress," Machine Design pp. 166-169,December 7, 1978.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 98Appendix A: Computer Run LogsNone of the computer runs was affected by issue of Revision 1. However, for convenience, allfiles are also attached to this version of the document.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 99Computer Run Log Summarya,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 100Computer Run Log Summary (cont)a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalcuiation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 101Computer Run Log Summary (cont)a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 102Computer Run Log Summary (cont)a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 103Computer Run Log Summary (cont)a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 104Computer Run Log Summary (cont)/-a,c__1-/Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revfsion PageCN-NPE-06-XXXX-03-NP 1 105Computer Run Log Summary (cont)a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 106Computer Run Log Summary (cont)ra,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 107Appendix B: Supporting DocumentationWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 108a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 109a,ciKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 110a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 111a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 112a,cI-Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 113I-a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-NP 1 114a,c9Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 115a,cWord Version 5.0 Westinghouse 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Number Revision PageCN-NPE-06-XXXX-03-NP 1 148a,crWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 149a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 150ra,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 151I-a,c-jWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 152a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 153/I,a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 154a,c-IWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 155a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 156a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 157a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 158a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 159a,c-IWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 160a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 161ra,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 162a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 163a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 164a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 165a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 166a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 167a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 168a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 169a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 170a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 171ra,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 172A AracWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 173a,crWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 174a,cr\I,Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 175a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NPP 1 176a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 177a,cJWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 178a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 179a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 180fa,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 181a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 182AracjWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NPP 1 183a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 184a,c2Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 185ra,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 186a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 187a,crKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 188a,crWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 189a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 190a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 191ra,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 192a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 193acI-Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 194a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 195a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 196a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 197a,li_Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 198a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 199a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-N P 1 200a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 201/I-a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 202a,cK.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 203a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 2041~~a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 205a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 206a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 207a,cKWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 208a,c-'Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 209^ ^acI/Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 210a,c/Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 211a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 212facWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 213a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 214a,cWord Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-N PE-06-XXXX-03-NP 1 215Checklist A: Proprietary Class Statement ChecklistDirections (this section is to be completed by authors): Authors are to determine the appropriate proprietaryclassification of their document. Start with the Westinghouse Proprietary Class 1 category and review forapplicability, proceeding to Westinghouse Proprietary Class 2 -Non-Releasable and finally to WestinghouseProprietary Class 2 -Releasable. The proprietary classification is established when the first criterion is satisfied.Westinghouse Proprietary Class 1D] If the document contains highly sensitive information such as commercial documents, pricing information,legal privilege, strategic documents, including business strategic and financial plans and certaindocuments of the utmost strategic importance, it is Proprietary Class 1. Check the box to the left and seeAppendix B of Procedure 1.0 in WCAP-7211, Revision 5, for guidance on the use of Form 36 and thedistribution of this document. This document can be found athttp://worldwide.westinlhouse.com/pdf/e3 wcap-7211.pdf.Westinghouse Proprietary Class 2 -Non-ReleasableReview the questions below for applicability to this calculation, checking the box to the left of each question that isapplicable. If one or more boxes are checked, the calculation is considered a Westinghouse ProprietaryClass 2 -Non-Releasable document. See Appendix B of Procedure 1.0 in WCAP-721 1, Revision 5, for guidanceon the use of Form 36 and the distribution of this document.D] Does the document contain one or more of the following: detailed manufacturing information ortechnology, computer source codes, design manuals, priced procurement documents or design reviews?D] Does the document contain sufficient detail of explanation of computer codes to allow their recreation?FD Does the document contain special methodology or calculation techniques developed by or forWestinghouse using a knowledge base that is not available in the open literature?D] Does the document contain any cost information or commercially or legally sensitive data?[] Does the document contain negotiating strategy or commercial position justification?[] Does the document contain Westinghouse management business direction or commercial strategicdirections?FD Does the document contain third party proprietary information?F1 Does the document contain information that supports Westinghouse patented technologies, includingspecialized test data?D] Does the document contain patentable ideas for which patent protection may be desirable?Westinghouse Proprietary Class 2 -Releasable[] If the calculation note is determined to be neither Westinghouse Proprietary Class 1 nor WestinghouseProprietary Class 2 -Non-Releasable, it is considered Westinghouse Proprietary Class 2 -Releasable.Check the box to the left and refer to Appendix B of Procedure 1.0 in WCAP-7211, Revision 5, forguidance on use of Form 36 and the distribution of the document.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 216Checklist B: Calculation Note Methodology Checklist(Completed By Author)No. Self Review Topic Yes No N/A1 Is all information in the cover page header block provided appropriately? X2 Are all the pages sequentially numbered, and are the calculation note number, revision Xnumber, and appropriate proprietary classification listed on each page?3 Are the page numbers in the Table of Contents provided and correct? X4 Are the subject and/or purpose of the calculation clearly stated in Section 1.1? X5 Have the limits of applicability been identified in Section 1.2? X6 Is the Summary of Results and Conclusions provided in Section 2.0 consistent with the Xpurpose stated in Section 1.1 and calculations contained in Section 6.3?7 Are the assumptions clearly identified and justified in Section 3.1? X8 Are open items properly identified in Section 3.2 and the calculation note cover page? X9 Are the Acceptance Criteria clearly and appropriately provided in Section 4.0? X10 Are the methods clearly identified in the Method Discussion in Section 6.1? X11 Are the required inputs and their sources provided in Section 6.2, and are they appropriate for Xthe current calculation?12 Does Section 6.3 sufficiently describe the analysis details and results? X13 Is sufficient information provided for all References in Section 7.0 to facilitate their retrieval X(e.g., from EDMS, NRC's ADAMS system, open literature, etc.), or has a copy been providedin Appendix B?14 Are all computer outputs documented in Appendix A and consistent with Table 5-1? X15 Are all computer codes used under Configuration Control and released for use? X16 Are the computer codes used applicable for modeling the physical and/or computational Xproblem contained in this calculation note?17 Have the latest versions of all computer codes been used? X18 Have all open computer code errors identified in Software Error Reports been addressed? X19 Is Checklist A completed properly, and are the proprietary classification, proprietary clause Xand designation for release provided and consistent with the checklist?20 Are the units of measure clearly identified? X21 Are approved design control practices followed without exception? X22 Are all hand-annotated changes to the calculation note initialed and dated by author and Xverifier? Has a single line been drawn through any changes with the original informationremaining legible?23 Was a Pre-Job Brief held prior to beginning the analysis? XM24 Was a Peer Check performed to review inputs documented in Section 6.2 prior to performing XManalyses?25 Was a Peer Check performed to review results before documenting them in Section 6.3? XM26 If required, have computer files been transferred to archive storage? Provide page number for Xlist of files if not included in Appendix A. PageIf 'NO' to any of the above, provide page number of justification or provide additional explanation below or onsubsequent pages. (1) Work commenced prior to deployment of new procedure.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NPP 1 217Checklist C: Verification Methodology Checklist(Completed By Verifier(s))Initial IfVerification Method (One or more must be completed by each verifier) Performed1 Independent review of document. (Briefly explain method of review below or attach.) RFR2 Verification performed by alternative calculations as indicated below.01)a. Comparison to a sufficient number of simplified calculations which give persuasivesupport to the original analysis.b. Comparison to an analysis by an alternate verified method.c. Comparison to a similar verified design or calculation.d. Comparison to test results.e. Comparison to measured and documented plant data for a comparable design.f. Comparison to published data and correlations confirmed by experience in theindustry.3 Completed Group-Specific Verification Checklist. (Optional, attach if used.)4 Other (Describe)(1) For independent verification accomplished by comparisons with results of one or more alternate calculations orprocesses, the comparison should be referenced, shown below, or attached to the checklist.Verification: The verifier's signature (or Electronic Approval) on the cover sheet indicates that all comments ornecessary corrections identified during the review of this document have been incorporated as required and that thisdocument has been verified using the method(s) described above. For multiple verifiers, appropriate methods areindicated by initials. If necessary, technical comments and responses (if required) have been made on the"Additional Verifier's Comments" page.Additional Details of Verifier's ReviewReviewed by the 3-pass method.Word Version 5.0 Westinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCCalculation Note Number Revision PageCN-NPE-06-XXXX-03-NP 1 218Additional Verifier's CommentsThe signatures of the Author(s) and Verifier(s) on the cover page (or Electronic Approval) indicate acceptance of thecomments and responses.No. Verifier's Comments Author's Response (if Required)1 Make editorial changes as noted in mark-up copy Changes were made.2 Make changes in weld geometry per discussion Changes were made.with author and revised ANSYS input file.I __LWord Version 5.0 Calculation Note NumberCN-NPE-06-XXXX-03-NPWestinghouse Non-Proprietary Class 3WESTINGHOUSE ELECTRIC COMPANY LLCRevision Page1 219Customer Review Comments and ReconciliationsWord Version 5.0 EnclosureNon-proprietary Documents for Relief Request 53Attachment 7Drawings Referenced in Responses to NRC Questions* C-8000-101-2017-NP, Rev 2, Wall Static Pressure Suction* STD-009-0009-NP, Rev. 2, Coolant Pumps Weld JointIdentification and Fabrication Requirements* DWG 339-0054-NP, Rev. 0, Safe End Mach. Of Pressure TapHoles and Weld Prep. (Suction)* C-1 4473-220-002-NP, Rev. 0, Replacement Pressure TapNozzle" E-1 4473-220-001 -NP, Rev. 0, Pump Casing -A Pressure TapNozzle Modification Assembly" SE-14473-220-003-NP, Rev. 0, Pressure Tap NozzleReplacement Palo Verde Unit 3 Eiectronlcally approved records am authenticated In the electronic document management system. This record was final approved on Jul-08M2015,(This statement was added by the EDMS system to the quality record upon Its validation.)HI-'91,11%L4L-W7/T,G/MV104AFRO=7~#.5 ~S7~4NI______ ______ 6N\N\VKIi~\X\ \~ NKM1~II/di,-, /3/---41-FE2 M~Q'[.Cr800707104MC/M017'NRDUmAPPROVED,cPER RFOS-WOSR-15-37W95MM9O4D NO-N*90-M141 CASSW.33IOIINJ.BHEOEJARZGARYM. TROCOLAERIC M.WEISELArMAIL 2SZABO1FRYR. STACKI RICHARD P. ONEILL_________________________ ~LIYIRA.I' 10.A.,ser, INDa,UNLESS OT ERWISE' SPECIFIEDDRAWNM U le" W -UN1.1ER a', S81035 30, Eo i a 3 TO 3l'CE-KS9 PUMP CO.AINCtNEWINTON, N.H.;03W,B316 iTU..0M 1660 10 M169 29TOm 96OVER46D6I INCH -23K400 MM IEXACTI ANE54lSFINISHWPA 3.15 MICRO Ni -CHIAMFER *5*'9.AULA.E/I 1 DO, NOT SCALE DWG.7rX-E/~ /0/W,44 5477~XMC9Ic" 5CRE M942V4:BREAK19 l.OI4NM9N.4 915M A D.MA .ll ClIAIIFEIIF1ILLET"O.4TO 0A RADI US CHR D-.OMSRC w-C8000;0-07-P~DIMENSIONS IN.MM BASE1 ON 209CME"p j O I. ILRV" _ _ _ _ _ ._ I --. .----.......- -'n , r r --76ý53I tic:Ii.t 73WAN CLADJ mt.1 .- N&? CTOPLUAIL 31LOt 500 EmS 1 RONWAjMAWf1.O&NO AISCm0Rn 5SP R 005 V$A5.I96.P. 500.1$ SYNONYMOUS 3A~wI RP'PL/CA&A .toa AMI L~oloONrc/tOL¥ IIcAIW IOPER RF0S-WDSR-15-37 5[ °I1AO"WN00050VMOAAI($2' II SNATURES ARE FOR CIJ0RREN REVISION IWESTINGHOUSE NON-PROPRIETARY CLASS 3Copyright 2015 \VestitighowLce Electric Company LLCAll Rights Reserved Electronically approved records am authenticated In the eiectronie document management system. This record was final approved on Jui.08-2011(This statement was added by the EDMS system to the quality reord upon its validation.)2I;1g'REISIONS MOUZIELRUESC0iPFDOt 'DATE" ýAPMiDbFinMDENT RREA -DC'NOTE5:-1.01 S10N~t~ 1 RNc~IG. PR U~isiYI.1.5- 19L4BF-U--~---7--SIGNATUaESARECFORC.UUEIlTRt"IONrJJOHN J., BEDNARZIInI' iPER RFDOSWDSR-15-37ATTILAM SZABO, 2.j C- 339- .00O9-Z[PUM¶CR51NG SAFE END'JEFFREYR. STACK f4....- -jJ054- EAK IMARCH.RICHARD P.'O'NEILL' PTNO IQl lCT U&lrl;EINAIWAELD PREPL ________ -________ 0.A'.SUTY.rER ASSY:., ZA-ILtTMTIO.1~114~J~J~LEJLUAVEE *-~=: Il[4 IL A_~zDATEýý_CHIM-21160--AWESTINGHOUSE NON-PROPRIETARY CLASS, 3qWEEIND, MR OAF PRSMUKTAP'HOLES N AELD, PREPR(5Ut I ._:"M-4 4 4- I ~ ~ ' r ~DATE1- Vai CI I,___ -_ IM D DPTR tm -tFIUMES 704 M RADIUSiNS-~-~' CI I U W' IVilgI i AlRighis Reserved IL L APPLICATION UISNr1N35 D I m -lb- D=U=tt h-- A..13mI-~ ~ m (inn .~, .55.5 by 5* 5~IS .,c.,t 0,~ q,,sAyssd ,,~,, lb43a210D91ANOTES:1. THIS ITEM IS A PRESSURE BOUNDARY COMPONENT PER SECTION III OFTHE ASME CODE, FOR REACTOR COOLANT PUMP (RCP) PRESSURETAP NOZZLE MODIFICATION APPLICABLE TO ARIZONA NUCLEARPOWER PROJECT (PVNGS) UNIT 3. MATERIAL: SB-166, ALLOY N06690.2. EACH PIECE SHALL BE LOW STRESS STAMPED OR VIBROETCHED,WITH THE FOLLOWING INFORMATION, AFTER THE MODIFICATIONS SHOWN(IF NOT ON THE PART): HEAT NUMBER, WESTINGHOUSE PO NUMBER,PART/DRAWING NUMBER.3. AFTER TRIMMING/MACHINING IS COMPLETED, MACHINED AREASTO BE RE-INSPECTED BY PT LIQUID PENETRANT EXAMINATIONS I ACCEPTANCECRITERIA PER SECTION III OF THE ASME CODE.4. ORIGINAL PIECE PROCUREDCSCALE 1:1CBY WESTINGHOUSE, TO BE MODIFIED ON SITE.5. ACTUAL CUT LENGTH DIMENSION TO BE DETERMINED AFTER EXISTING NOZZLEMODIFICATION, BEFORE FIELD TRIMMING OF REPLACEMENT NOZZLE.(02.00) STOCK_____--_ (1.69)+-BB.03 X 45' CHAMFER-ADD AFTER TRIMMINGNOTE 3SECTION A-ASCALE 1 : 1NOTE: DESIGN DIMENSIONS ARE IN INCHES. DIMENSIONS IN PARENTHESES () ARE FOR REFERENCE ONLY.UAIAEASE FILE U@ 2015 Westinghouse Electric Company LLCSTATUS: CERTIFIED FOR CONSTRUCTIONELECTRONICALLY APPROVED RECORDS ARE AUTHENTICATEDIN THE ELECTRONIC DOCUMENT MANAGEMENT SYSTEMSEE EDMS FOR DRAWnING APPROVAL DATE(S)SIGNATURES SHOWN ARE FORCURRENT REVISIONDATABASE FILE IDC-14473-220-O02-NP.idw4 4 -_________________AC)z0 .z0BTOLERANCE & MACHINE NOTES(UNLESS OTHERWISE SPECIFIED)DRAWING PRACTICES. GEOMETRIC SYMBOLS, DIMENSIONING,TOLERANCING & INTERPRETATION BASED ON ASME Y14.5M-1994.DIMENSIONS IN INCHES BASED ON 6REF.TOLERANCES:ONE PLACE DECIMAL 5 .1TWO PLACE DECIMAL +/- .02THREE PLACE DECIMAL .05__ +/- .RADIUS OR CHAMFER ALL EDGES __ .005 -.030FILLET RADII .03+/- .01CHAMFERS_+/- 2'ANGLES +/- .5MAXIMUM MACHINED SURFACE -125 pin Ra 4SMAXIMUM SURFACE ROUGHNESS -250 Oin Ra vWESTINGHOUSE NON-PROPRIETARY CLASS 30". REF. !NEXT-Y. 44ý' E:EaI Nip"-Fn A-VVJ II443 lx 2I1 I 7 I 6 I 5 4 3 I 2 I 1CONG R ATEE IS 1- 1 -IAS I A. .ASLOA'..OUCDAeT SAT IHGFDETAIL ASCALE 11.GONRCTICON11 ON ES EDDETAI L CSCL I I 0RTCTOR COOLANT FMPS RC THIS MCIFICOTD* TSCO AATZONA NUC CFOOAC TAVNGO ANTS2 ORIGINAL PRESSURE TAP NOZZL D O RE PARTIASLY REOVED AT HCR REMAINING PFECESNLAI APPROXMATELY GD NHSS 17MCHSLNDETAIL SSCALE I IA VARIOUSTH CHHESS STMNMESSTEUEOMSIMGS 000 0005INGHESTH0-- 'WNO SORE ANO THE O OESSMMT -TO EQUALITY RELXTED NýC)(SI.E SHAL BE-_..Z.DRING OE.nN51 R 1NG OF TIE RCASINGBORE TO REASATSEITSSUPPON MIVATE-TE-LAITING T.CLEPT THEN- R 5T B 52 APPROPRIATE THOCNESS STANLESS STEEL -IMS (ITEM 4) TO BEINSTALLED INTO THE BOTTOM 1 1NCH AREA IF THREPLACEMAENT PRESSULRE TAP N (ITEM3) TOUMT THERAMAICLEARANCEýGAPTORENNANTFBE ,r G8HONG DECON-ENSONSARSININCHIM ..ENSO1111 --Gj)AR-Rll-ENGSlNLl.02I -ATSE'~MAAE-OCMCT-S .MST SF0I I----------------------------------I TOSRTAACREUACSOOREOOMS COAT OSTOJEM RON FROST START CLASTS ASTS STALOLTADIoIAýCING lgfES NON-PROMRIETARy CLASS 3 TA FPSU MPCASING -A.PRESSURE TAP NOZZLE MODIFICAKONIS TS S ________ E -14473-220-001-NP 08 7 6 5 4 3 2TO765T432 IHSECTION S-BSEE NOTE 2SECTION C-CSEE NOTES3SECTION A-ANOTES:1. REMOVEWELD ON THE 3/4" PIPE TO SQUARE FITTING. AFTER CUTTING THE NOZZLE, THESQUARE FITTING CAN BE ROTATED AND MOVED AWAY. ADJUST U-DOLT PIPE SUPPORT ONTHE 314" PIPE AS NECESSARY TO ALLOW ADJUSTMENT OF PIPE.2. REMOVE THE NOZZLE EXTENSION PIECE AND CONNECTING WELDS SHOWN IN SECTION XA.INSTALL WATER PLUG INTO ORIFICE AS FME BARRIER.3. DRILL AND REMOVE A LARGE PORTION OF THE NOZZLE LEAVING A SHORT REMNANT OF THEORIGINAL ORIFICE. MACHINEIGRIND A NEW PARTIAL PENETRATION WELD PREP INTO THECASING EXTENSION BASE MATERIAL4. PRIOR TO REAMING. MEASURE THE AS-FOUND BORE DIAMETER (HORIZONTAL & VERTICALMEASUREMENTS) IN (3) LOCATIONS ALONG THE BORE. REPORT THESE MEASUREMENTS TOENGINEERING FOR DETERMINATION OF THE REAMER OIE, AND SHIMS USED.5. INSTALL NEW REPLACEMENT ONE PIECE NOZZLE BY WELDING A NEW PARTIAL PENETRATIONWELD. INSTALL THE VERTICAL STAINLESS STEEL PIPE W]TH A SOCET WELD.SECTION 5-0SEE NOTES5REFERENCE DRAWINGS:1. C-I73A-220,XO12.C-14473-220ý'__ foCURRENT CONFIGURATIONSTEP 1STEP 2STEP 3}}