ML13305A122

Enclosure 3 - Areva Document No. 32-9212003-000, Lst Considering RCS Piping and RVCH Limit for B&W Plant Designs, September 2012

ML13305A122
Person / Time
Site:	Oconee
Issue date:	11/25/2013
From:	Noronha S J AREVA
To:	Office of Nuclear Reactor Regulation
References
32-9212003-000
Download: ML13305A122 (21)

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License Amendment Request No. 2012-10, Supplement 2October 25, 2013ENCLOSURE 3AREVA Document No. 32-9212003-000 "LST considering RCS Piping and RVCH Limit for B&W Plant Designs"September 2012Non-Proprietary Version Controlaed Document0402-01-FOI (Rev. 017, 11/19/12)

A CALCULATION SUMMARY SHEET (CSS)AREVADocument No. 32 -9212003 -000 Safety Related:

Z Yes D NoTitle LST considering RCS Piping and RVCH Limit for B&W Plant DesignsPURPOSE AND SUMMARY OF RESULTS:AREVA NP Inc. proprietary Information In the document are removed and their locations are Indicated bypairs of brackets

"[ 1". This document is the non-proprietary version of AREVA Document 32-9208072-001.The P-T limits are required to be generated for all the ferritic pressure boundary components of the reactor coolant system(RCS) as prescribed in 10 CFR 50 Appendix G. For B&W nuclear steam supply systems, Topical Report BAW-10046A, Revision 2 [2] describes methods for compliance with the requirements of 10 CFR 50 Appendix G [1]. BAW-10046A, Rev 2uses procedures of ASME Code Section III Appendix G [3] to calculate the pressure-temperature limits of the reactor vesselbeltline region, reactor vessel closure head (RVCH) region and reactor vessel nozzle region; it uses lowest servicetemperature (LST) criterion to determine the P-T limits of RCS loop piping and the control rod drive mechanism (CRDM) motortubes. The purpose of this document is to determine the limiting component in the ferritic pressure components of RCS thatestablishes the lowest service temperature.

BAW-1 0046 Rev 2 [2] prescribes

[ ] IF as the LST for control rod drive mechanism (CRDM) motor tubes which includesan additional margin of [ I IF beyond the required values. Here we prescribe the LST of the CRDM as [ I IF byremoving the additional margin. The [ I OF LST still satisfies the ASME Code and 10CFR Appendix G requirements.

BAW-10046 Rev 2 [2] used ASME Code [3] Section III NB-3211(d)(2) to establish an LST of ( I IF for RCS piping. In thisdocument we followed the alternate provision prescribed in ASME Code Section III NB-321 1 (d)(1). The evaluation performed in Section 7.2 shows that the allowable pressures for the RCS piping are significantly higher than the RVCH and are thus notlimiting at any temperature.

The evaluation in Section 7.2 demonstrates that the limiting component at low temperatures is theRVCH and removes the requirement to include the LST of RCS piping in the P-T limits.The evaluation establishes LSTs for the B&W designed plants that are approximately

[ O 0F greater than the minimumtemperature requirements of 10CFR50, Appendix G. Based on the results of this evaluation, it is determined that for the B&Wdesigned plants the LST is established by the RVCH. In other words, the RVCH continues to remain as the limiting LSTcomponent in the RCS as concluded in BAW-1 0046 Rev. 2 [2].THE DOCUMENT CONTAINSASSUMPTIONS THAT SHALL BETHE FOLLOWING COMPUTER CODES HAVE BEEN USED IN THIS DOCUMENT:

VERIFIED PRIOR TO USECODENERSION/REV CODENERSION/REV E'- YES42Z YESPTPC 4.2ZNPage 1 of 20 Doc trient/ .,0402-01-FOl (Rev. 017, 11/19/12)

Document No. 32-9212003-000 LST considering RCS Piping and RVCH I-imit for B&W Plant DesignsReciew Method: v] Design Review (Detailed Check)L-] Alterl ale Calculation Signature BlockName and Title(printed or typed)P/RIAandLP/LRPages/Sections PreparedlReviewed/Approved Signature DateSilvester J Noronhap,.icipal Engineer l'"1,1 ALLDouglas E KillianTechnical Consultant R ALLTimothy M. WigeriUn it Manager-A V?71zALL, Note: P/R/A designates Preparer (P), Reviewer (R), Approver (A);LP/LR designates Lead Preparer (LU), Lead Reviewer (LR)Project Manager Approval of Customer References (N/A if not applicable)

Name Title(printed or typed) (printed or typed) Signature DateN/A N/A N/A N/AMentoring Information (not required per 0402-01)Name Title Mentor to:(printed or typed) (printed or typed) (P/R) Signature DatePage 2 Controfled Docurnent AAR EVA0402-01 -F01 (Rev. 017, 11/19/12)

Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsRecord of RevisionRevision Pages/Sections/Paragraphs No. Changed Brief Description I Change Authorization 000 ALL Original Releasei iI. 4i iI. 4Page 3 AAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsTable of ContentsPageSIG NATURE BLOCK .............................................................................................................................

2RECORD O F REVISIO N .......................................................................................................................

3LIST O F TABLES ..................................................................................................................................

6LIST O F FIG URES ................................................................................................................................

61.0 INTRO DUCTIO N ........................................................................................................................

72.0 BACKG RO UND ..........................................................................................................................

73.0 M ETHOD O F ANALYSIS

....................................................................................................

93.1 Assessment of CRDM LST ........................................................................................................

93.2 Appendix G Evaluation Methodology for RCS Piping ..................................................................

93.3 LST Evaluation of RVCH ...........................................................................................................

104.0 ASSUM PTIO NS .......................................................................................................................

104.1 Unverified Assumptions

..............................................................................................................

104.2 Engineering Judgment

...................................................................................................................

104.3 Modeling Simplifications

...........................................................................................................

115.0 DESIGN INPUTS FOR APPENDIX G EVALUATION OF RCS PIPING ................................

115.1 G e o m e try D a ta ...............................................................................................................................

1 15.2 Hot Leg Piping Materials

...........................................................................................................

115.3 Heatup and Cooldown Transient Definitions

............................................................................

125.4 Convection Film Coefficient

.......................................................................................................

125.5 Closure Head Limits .......................................................................................................................

136.0 CO M PUTER USAGE ...............................................................................................................

146.1 Software and Hardware

..............................................................................................................

146 .2 C o m p ute r F ile s ...............................................................................................................................

147.0 RESULTS .................................................................................................................................

157.1 LST Evaluation of CRDM Nozzle ...............................................................................................

157.2 Appendix G Evaluation of RCS Piping .....................................................................................

15Page 4 Controfled DocumentAAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsTable of Contents(continued)

Page7.3 Evaluation of LST for RV C H ......................................................................................................

188 .0 C O N C L U S IO N .........................................................................................................................

199 .0 R E F E R E N C E S .........................................................................................................................

2 0Page 5 Controfled DocumentAAR EVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsList of TablesPageTable 5-1: G eom etry Data for H L Piping ..........................................................................................

11T a b le 5-2 : H L M ate ria ls .......................................................................................................................

1 1T able 5-3: M aterial P roperties

........................................................................................................

..12T a ble 6-1: C om p ute r F ile s ..................................................................................................................

14Table 7-1: HL P-T Limit Data for Normal Ramp Heatup at [ ) °F/hr ...........................................

16Table 7-2: HL P-T Limit Data for Normal Ramp Cooldown at [ ] OF/hr .......................................

17List of FiguresPageFigure 5-1: RVCH Uncorrected P-T Limits for B&W designed plants .............................................

13Figure 7-1: Comparison of RVCH and HL Uncorrected P-T Limits for B&W designed plants ...... 18Page 6 ConrolUed DocumentAAR EVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designs

1.0 INTRODUCTION

Code of Federal Regulations Title 10, Part 50 (10 CFR 50) Appendix G [1] dictates that for all ferriticmaterial pressure boundary components of the reactor coolant system (RCS), pressure-temperature (P-T) limit curves should be developed per ASME Code Section IHl/XI Appendix G [3, 4]. 10CFR 50,Appendix G prescribes additional pressure and temperature requirements, including minimumtemperature requirements for the reactor pressure vessel that are summarized in Table 1 of [1]. Theseminimum temperature requirements

[1] will also be discussed in addressing and establishing thelimiting component that defines the lowest service temperature (LST) in the development of the P-Tlimit curves. For Babcock & Wilcox (B&W) nuclear steam supply systems, topical report BAW-10046A, Revision 2 [2] describes methods for compliance with the requirements of 10 CFR 50 Appendix G [1].BAW-10046A Rev 2 [2] uses the procedures of ASME Code [3, 4] Appendix G to calculate the P-Tlimits of reactor vessel beltline region, reactor vessel closure head (RVCH) region and reactor vesselnozzle region which are identified as the controlling regions that regulate the pressure-temperature limitations of the reactor coolant system (RCS) for normal operation and in-service pressure tests. TheRCS loop piping and the control rod drive mechanism (CRDM) motor tubes are addressed using theLST criterion.

The RVCH was evaluated considering a relatively high RTNDT value of [ ] 0 F andthe LST for the closure head flange (per Figures 5-8 through 5-11 of Ref. [2]) was determined to begreater than 2000 F. As a result, the LST corresponding to the closure head flange was demonstrated to bound the LST of the RCS piping and the CRDM [2]. The purpose of this document is to reevaluate the minimum temperature requirements of RVCH, RCS piping and the CRDM.2.0 BACKGROUND The pressure-temperature (P-T) limits and minimum service temperature requirements of pressureretaining components of reactor coolant systems (RCS) that are made of ferritic materials areprescribed by Code of Federal Regulations Title 10, Part 50 (10 CFR 50) Appendix G [1]. Forpressures above 20% of the pre-service system hydrostatic test pressure, the requirement of Item 2.bin Table 1 of Appendix G to 10 CFR Part 50 [1] states that the temperature must be at least 120 OFabove the reference temperature of the closure head flange material.

The 10 CFR 50 Appendix G alsorequires that the requirements of ASME Boiler and Pressure Vessel Code (ASME Code) be met inaddition to the requirements set forth in 10CFR 50. ASME Code Section III [3] Article NB-3211 definesPage 7 Contr.csl DocumenAAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsLowest Service Temperature (LST) as "the minimum temperature of the fluid retained by thecomponent or, alternatively, the calculated volumetric average metal temperature expected duringnormal operation, whenever pressure within the component exceeds 20% of the pre-operational systemhydrostatic test pressure".

As per ASME Code Section Ill [3], Article NB-3211 (d) "Protection againstnonductile fracture shall be provided by satisfying one of the following provisions:

(1) performing an evaluation of service and test conditions by methods similar to thosecontained in Appendix G; or(2) for piping, pump, and valve material thickness greater than 2% in. (64 mm) establishing alowest service temperature(LST) that is not lower than RTNDT (NB-2331)

+ 100°F (56°C);(3) for piping, pump, and valve material thickness equal to or less than 2/ in. (64 mm), therequirements of NB-2332(a) shall be met at or below the lowest service temperature as established inthe design specification."

Topical Report BAW-10046A, Revision 2 [2] describes methods for compliance with the requirements of 10 CFR 50 Appendix G [1] for the B&W plants. The safety evaluation report (SER) for BAW-10046A, Revision 2 [2], states "BAW 10046, Rev. 2 describes acceptable methods for the development ofallowable pressure-temperature limits for normal operation and for test conditions to assure theprevention of non-ductile fracture.

It may be referenced in future applications..."

The methodology used for B&W plants includes all the ferritic components in the Reactor CoolantSystem (RCS). Acceptable methods for the determination of P-T limits for the closure head, thereactor vessel outlet nozzle, and beltline region are documented.

As stated in BAW-1 0046A, Revision 2"These three regions are the only ones that, at different stages of the vessel's design life, regulate thepressure-temperature limitations of the RC system for normal operation and inservice pressure tests."The P-T limits determined for these components are determined and the resulting composite limitingcurve is then determined utilizing the standard B&W methodology.

Per BAW-10046, Revision 2, "The components for which the lowest service temperature must bedefined include the RC loop piping and the control rod drive mechanism."

"The lowest servicetemperature of these components is [ ] OF (based on RTNDT + 100 OF) for the piping and [ ] OF forthe CRDM." Thus BAW-10046A Revision 2 used ASME Code Section III NB-3211 (d) (2) to satisfy theconditions for protection against non-ductile failure.Page 8 Contrdlld DocurnenAAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsSince BAW-10046A Rev 2 (2] was approved:

(a) the ASME Section XI Appendix G fracture toughness reference curve KIR [4] has beenchanged from K18 (critical stress intensity factor for crack arrest) to KI, (critical stress intensity factor for static crack initiation),

and(b) the Reactor Vessel Closure Heads (RVCHs) have been replaced in all the B&W designedplants.The new/replacement RVCHs have much lower RTNDT value than O ] 0F reported in BAW-10046 Rev 2 [2]. The RTNDT of current RVCH materials for ANO-1, DB-1 and TMI-1 is O ] 0F [5,6,7] andthat for ONS Units 1, 2 and 3 is [ ] 0F[8].3.0 METHOD OF ANALYSISIn this report, we reevaluate the LST requirements for:(1) CRDM by assessing the evaluation in Reference

[2](2) RCS piping, following the provisions of ASME Code Section III NB-3211 (d)(1), and(3) RVCH using the current RTNDT of replacement RVCH.3.1 Assessment of CRDM LSTIn BAW-10046 Rev 2 [2] it is determined that the required LST based on 10CFR 50 Appendix G forCRDM nozzles is [ 1 0F. However, BAW-1 0046 Rev 2 [2] suggests using a LST of O 1 0F forpressures above [ ] psig (20% of [ ] psig). In Section 7.1, we reassess this LST value.3.2 Appendix G Evaluation Methodology for RCS PipingA detailed Appendix G evaluation as permitted per ASME Code Section III NB-3211 (d)(1) will be usedin this evaluation in lieu of the provisions of NB-3211 (d)(2) as used in BAW-10046, Rev 2 for thedetermination of the LST of the RCS piping. The P-T limits for RCS piping are developed inaccordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section III and XI,Appendix G [3, 4] which permits the use of the K1, fracture toughness curve. Hot Leg (HL) piping isanalyzed here as the most limiting section of the RCS piping. Allowable pressures are calculated as afunction of reactor coolant inlet temperature based on the approved linear elastic fracture mechanics Page 9 Controled DocumentAAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designsmethodology in topical report BAW-10046A

[2], using a safety factor of 2 on pressure for the normalheatup and cooldown (HUCD) transients considered herein. The computer code PTPC [9] is used tocalculate uncorrected allowable pressures for the beftline and nozzle regions of the reactor vesselaccording to:KIR -KITSF xwhere P6,,,, allowable pressureKIR reference stress intensity factor = KicKIT thermal stress intensity factorR = unit pressure stress intensity factor (due to 1 psig)SF = safety factorFor each analyzed transient, the uncorrected allowable pressure is determined as a function of fluidtemperature at 1/4t inside and outside surface flaw locations in the HL.3.3 LST Evaluation of RVCHThe RTNDT value of RVCH reported in BAW-10046 Rev 2 [2] is [ ] OF. Thus, based on 10CFR50Appendix G the minimum temperature at which the service pressure can be just above 20% of the pre-service hydrostatic test pressure

( [ ] psi) was [ ] OF. The replacement RVCHs in B&WPlants have RTNDT values lower than [ ] OF that was used as a generic value for the original B&Wdesigned RVCH. In Section 7.3, the minimum temperature requirement as per 1OCFR50 Appendix G isreevaluated based on the new RTNDT values.4.0 ASSUMPTIONS 4.1 Unverified Assumptions There are no unverified assumptions.

4.2 Engineering JudgmentHL piping is judged to bound the RCS piping for the analysis.

Page 10 Contrnohd Documentn AAREVADocument No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designs4.3 Modeling Simplifications There are no modeling simplification assumptions other than those used in the PTPC program [9].6.0 DESIGN INPUTS FOR APPENDIX G EVALUATION OF RCS PIPINGThe design input information that will be used in performing the P-T limits analysis is addressed in thissection.5.1 Geometry DataTable 5-1: Geometry Data for HL Pipinga. Reactor Coolant Piping GeometryHL outer radius, RoHL inner radius, RFCladding thickness

b. Hot Leg Flaw Per Article G-2120 of ASME Code Section Xl [4], alongitudinal semi-elliptical surface flaw 1/4t (wheret= wall thickness) deep and 3/2t long is postulated at both the inside and outside surfaces of the HLpiping.6.2Hot Leg Piping Materials The HL Piping Materials which are relevant to the development of P-T limits are listed below.Table 5-2: HL Materials Vessel Component Type of Original MaterialMaterial Designation Hot Leg Piping LThe properties that are used for these materials in the present P-T limits analysis are listed in Table5-3. These properties were obtained from the ASME Code [11] and Reference

[12] for the HL material(and thermal conductivity for cladding material used to compute an effective base metal filmcoefficient).

A typical Poisson's ratio of 0.3 is used.Page 11 Con'trofld DocumentAAREVADocument No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsTable 5-3: Material Properties Temp. Elastic Thermal(2)

Thermal Specific Density ThermalModulus Expansion Conductivity Heat Conductivity for Cladding Material[11] [11] [12] [12] [12] [12](OF) (106 psi) (10" in/inf F) (Btu-in/hr-ft 2-OF) (Btu/lb-0F) (lb/ft3) (Btu-in/hr-ft 2-°F)70 29.2 6.4 376.3 0.104 490.9 103.9100 29.06(1) 6.5 372.8 0.107 490.5 105.6150 28.83(1) 6.6 367 0.111 489.9 108.4200 28.6 6.7 361.1 0.115 489.2 111.3250 28.35(1) 6.8 355.3 0.118 488.6 114.2300 28.1 6.9 349.4 0.120 487.9 117.0350 27.90(1) 7.0 343.6 0.123 487.3 119.9400 27.7 7.1 337.7 0.125 486.7 122.7450 27.4(1) 7.2 331.8 0.126 486.0 125.6500 27.1 7.3 326 0.128 485.4 128.5550 26.75(1) 7.3 320.1 0.130 484.7 131.3600 26.40 7.4 314.3 0.133 484.1 134.2650 25.85(')

7.5 308.4 0.135 483.4 137.0700 25.30 7.6 302.6 0.139 482.8 139.9Note: 1') The values are obtained by interpolating the available values; I Mean coefficients of thermalexpansion are used.The RTNDT value for the piping material

[] is [ ] IF [2]. A value of 200 ksi/in [13] isused for the upper shelf fracture toughness for the HL piping material.

6.3Heatup and Cooldown Transient Definitions The transients are analyzed for a linear ramp rate of [cooldown,

] 0F/hr for normal heatup and normal6.4Convection Film Coefficient A value of [] BTU/hr-ft 2-OF [13] is used for an effective convection heat transfer film coefficient atthe cladding-to-base metal interface for all the times during heatup and cooldown.

The outside surfaceis always modeled as a perfectly insulated boundary.

Page 12 AAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designs6.5 Closure Head LimitsPressure-temperature limits for the reactor vessel head-to-flange closure region have been evaluated inReferences

[5, 6, 7] and [8] based on the results from the detailed finite element stress analysis of theRVCH flange region and the use of the Kic curve for fracture toughness, as permitted by ASME CodeSection III and XI [3, 4]. These closure head limits are shown below in Figure 5-1.Figure 5-1: RVCH Uncorrected P-T Limits for B&W designed plantsPage 13 Conirdoltej Doc~u nnenAAR EVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designs6.0 COMPUTER USAGE6.1 Software and HardwareTest cases test6c h.inp and test6cc.inp

-influence coefficient solution for Kit from Reference

[9] arerun to verify that the answers are correct.

The file test6ch.out contains output from the test casetest6c-h.inp, and the file test6cc.out contains output from the test case test6c.c.inp.

Review of theoutput files shows that the answers are identical to those contained in Reference

[9].1. Computer program tested: PTPC 4.22. Computer hardware used: Intel Core i7 CPU 2640 M @ 2.80 GHz, 8.0GB RAM,Windows 7 Enterprise 64-bit OS (Tag# 5VKW5S1)3. Name of person running test: Silvester J Noronha4. Date of test: 05-15-2012

5. Results and acceptability:

The results in Test6ch.out and Test6cc.out listed in Table 6-1agree exactly with the values in the verification report [9].6.2 Computer FilesAll computer files, including the computer input/output files for the analysis in this document, and thecomputer program test cases are listed in this section.

All files are available in AREVA NP Inc. ColdStorstorage \cold\General-Access\32\32-9000000\32-9208072-000\official.

Table 6-1: Computer FilesPage 14 Controlled DocumentAAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designs7.0 RESULTS7.1 LST Evaluation of CRDM NozzleBAW-10046 Rev 2 [2] prescribes

[ ] OF as the LST for the control rod drive mechanism (CRDM)motor tube. However it is noted that (Sec 3.3.2, Reference

[2]) based on the test data of [] steels the LST for CRDM materials is only [ ] OF and an additional margin of [ ' IFwas included beyond the Code required values. In Reference

[2] it is stated that "This specified lowestservice temperature is [ ] OF above the temperature at which the fracture toughness requirements are specified and met. The additional

[ ] OF provides margins of safety beyond that required by theASME Code and by Appendix G to 10 CFR 50." In this analysis we propose to reduce the LST of theCRDM motor tube to [ ] OF by removing the additional margin used in BAW-10046 Rev 2 [2]. The[ ] 0F LST still satisfies the ASME Code and 1 OCFR Appendix G requirements.

7.2 Appendix G Evaluation of RCS PipingThe inputs provided in Section 5.0 are used to calculate the uncorrected P-T limits for the HL pipingfollowing the methodology discussed in Section 3.2. For both heatup and cooldown transients aconservative rate of [ ] °F/hr is used.Page 15 AAREVADocument No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsTable 7-1: HL P-T Limit Data for Normal Ramp Heatup at [ 100 ] OF/hrPage 16 Conrria~d Docu~ment AAREVADocument No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant DesignsTable 7-2: HL P-T Limit Data for Normal Ramp Cooldown at [ 100 ] °F/hrFrom Table 7-1 it can be seen that the allowable pressure values during heat up are quite high even atlow temperatures.

For temperatures

[ ] OF and above the minimum allowable pressure is greaterthan 2400 psi. Also during cool down as seen in Table 7-2, the allowable pressure values are greaterPage 17 AAREVADocument No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designsthan 2400 psi for temperatures above [ ] OF. On comparing the allowable (minimum) pressurevalues from Table 7-1 and Table 7-2 with the RVCH as shown in Figure 7-1, it can be seen that theallowable pressures for HL are much higher than the RVCH and that allowable pressure values ofRVCH are controlling.

Figure 7-1: Comparison of RVCH and HL Uncorrected P-T Limits for B&W designedplants7.3 Evaluation of LST for RVCHThe RTNDT value of RVCH reported in BAW-10046 Rev 2 [2] is [ O 0F. Thus, based on 10CFR50Appendix G the minimum temperature at which the service pressure can be above 20% of the pre-service hydrostatic test pressure

([ ] psi) was [ ] OF (RTNDT + 120 OF). With thereplacement RVCH the RTNDT for ANO-1, DB-1 and TMI-1 is [ ] OF [5, 6, 7] and that for ONS Unitsis [ ] OF [8]. Thus per 1OCFR50 Appendix G, the minimum temperature at which the pressure canPage 18 Controlled DocumentAAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designsbe above [ I psig (20% of [ ] psig) reduces to [ ] OF for ANO-1, DB-1 and TMI-1 and[ ] OF for ONS-1, 2 and 3. However, as can be seen in Figure 7-1, the LST for ANO-1, DB-1 andTMI-1 RVCH is [ ] OF and that for ONS-1, 2 and 3 is [ ] OF based on the results from thedetailed finite element stress analysis and Appendix G [3, 4] evaluation of the RVCH. Thus, the LSTsfor the RVCH are 10OF greater than the required minimum temperature of the RVCH per 10CFR50,Appendix G.

8.0 CONCLUSION

BAW-10046 Rev 2 [2] prescribes

[ O 0F as the LST for the control rod drive mechanism (CRDM)motor tube. However it is noted that (Sec 3.3.2, Reference

[2]) based on the test data of Type 403modified steels the LST for CRDM materials is only [ ] OF and an additional margin of [ ] OF isincluded beyond the Code required value. In this analysis, we propose to reduce the LST of the CRDMmotor tube to [ ] OF by removing the additional margin. The [ ] OF LST still satisfies the ASMECode and 1 OCFR Appendix G requirement.

The LST prescribed for RCS piping in BAW-1 0046 Rev 2 [2] is [ O 0F, which is based on RTNDT +100OF for the RCS piping (RTNDT = [ ] OF for the piping [2]), a provision prescribed in ASME CodeSection III NB-321 1 (d)(2). In this document we followed the alternate provision prescribed in NB-3211(d)(1) which states that "Protection against non-ductile fracture shall be provided by satisfying oneof the following provisions:

(1) performing an evaluation of service and test conditions by methodssimilar to those contained in Appendix G". The evaluation performed in Section 7.2 shows that theallowable pressures for the RCS piping are significantly higher than the RVCH and are thus not limitingat any temperature.

The evaluation in Section 7.2 demonstrates that the limiting component at lowtemperatures is the RVCH and removes the requirement to include the LST of RCS piping in the P-Tlimits.The evaluation establishes LSTs for the B&W designed plants that are approximately 1 0°F greater thanthe minimum temperature requirements of 10CFR50, Appendix G. Based on the results of thisevaluation, it is determined that for the B&W designed plants the LST is established by the RVCH. Inother words, the RVCH continues to remain as the limiting LST component in the RCS as concluded inBAW-10046 Rev. 2 [2].Page 19 Contirolled DOCUrie~nt AAREVA Document No. 32-9212003-000 LST considering RCS Piping and RVCH Limit for B&W Plant Designs

9.0 REFERENCES

1. Code of Federal Regulations, Title 10, Part 50 -Domestic Licensing of Production andUtilization Facilities, Appendix G -"Fracture Toughness Requirements",

[Federal Register Vol.78, p. 34248, June 7, 2013]2. AREVA Document BAW-10046A, Rev. 2, "Methods of Compliance with Fracture Toughness and Operational Requirements of 10CFR50, Appendix G," by H. W. Behnke et al., June 1986.3. ASME Boiler & Pressure Vessel Code,Section III, July 20104. ASME Boiler & Pressure Vessel Code,Section XI, July 20105. AREVA Document 32-5041911-002, "ANO-1 Appendix G RV Closure Head Limit"6. AREVA Document 32-9037975-002, "DB-1 Section Xl Replacement RV Closure Head (Chalon)P-T Limits"7. AREVA Document 32-9037825-000, "TMI Unit Replacement RV Closure Head P-T Limits"8. AREVA Document 32-9001959-001, "Oconee Units 1,2 & 3 Replacement RV Closure HeadP-T Limits"9. AREVA Document 32-1171775-010, "Verification of PTPC & User's Manuar'10. AREVA Document 02-146628E-04, "Details for 36" ID Coolant Outlet Piping"11. ASME Boiler and Pressure Vessel Code (B&PVC)Section II, July 201012. AREVA Document NPGD-TM-500, Rev. D, "NPGMAT -NPGD Material Properties ProgramUser's Manual,"

March 198513. AREVA Document 51-1143704-00, "Procedure for Generating P-T Limits"Page 20