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NEDO-33445, Rev.0, Browns Ferry Unit 1, Pressure and Temperature Limits Report (PTLR) Up to 25 and 38 Effective Full-Power Years.
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Site:	Browns Ferry
Issue date:	12/18/2013
From:	; GE-Hitachi Nuclear Energy Americas
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ML13358A064	List: CNL-13-148, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484); ML13358A068; NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484);
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ENCLOSURE 3 NEDO-33445 - Pressure and Temperature Limits Report (PTLR) Up to 25 and 38 Effective Full- Power Years (Non-Proprietary)

GE Hitachi Nuclear Energy 0 HITACHI 3901Castle Hayne Rd Wilmington, NC 28401 NEDO-33445 Revision 0 December 2013 Non-ProprietaryInformation-ClassI (Public)

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNI 1 Pressure and Temperature Limits Report (PTLR)

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

INFORMATION NOTICE This is a non-proprietary version of the document NEDC-33445P, Revision 0, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here ((

IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT PLEASE READ CAREFULLY The design, engineering, and other information contained in this document are furnished for the purposes of supporting a License Amendment Request by Tennessee Valley Authority (TVA) for a pressure temperature limits in proceedings before the U.S. Nuclear Regulatory Commission.

The only undertakings of the GEH respecting information in this document are contained in the contract between TVA and GEH, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than TVA, or for any purpose other than that for which it is intended, is not authorized; and, with respect to any unauthorized use, GEH makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe privately owned rights.

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ABBREVIATIONS & ACRONYMS .............................................................................................. iv 1.0 Pu rp o se ................................................................................................................................... 1 2 .0 A pp licab ility ........................................................................................................................... 1 3 .0 M ethodology .......................................................................................................................... 1 3.1 Chemistry . ...... 22....................

3.2 Initial Reference Temperature of Nil Ductility Transition (RTNDT) .......................... 2 3.3 Adjusted Reference Temperature ............................................................................................ 2 3.4 Surveillance Program ........................................................................................................... 3 3.5 Reactor Coolant Pressure Boundary ......................................................................................... 4 3.6 Futu re C hanges .............................................................................................................................. 5 4.0 Operating L im its ............................................................................................................ 5 5 .0 D iscussio n .............................................................................................................................. 6 6 .0 R eferen ces ............................................................................................................................ 10 APPENDICES Appendix A Reactor Vessel Material Surveillance Program .......................................................... 25 Appendix B BFNP Unit 1 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific In form ation ........................................................................................................................................... 26 Appendix C BFNP Unit 1 Reactor Pressure Vessel P-T Curve Checklist .................................... 37 Appendix D Sample P-T Curve Calculations .................................................................................. 42 TABLES Table 1: BFNP Unit I Tabulation of Curves - 25 EFPY ................................................................. 15 Table 2: BFNP Unit 1 Tabulation of Curves - 38 EFPY ............................................................... 20 Table B-i: BFNP Unit 1 Initial RTNDT Values for RPV Plate and Flange Materials ...................... 28 Table B-2: BFNP Unit 1 Initial RTNDT Values for RPV Nozzle and Weld Materials ..................... 29 Table B-3: BFNP Unit 1 Initial RTNDT Values for RPV Appurtenance and Bolting Materials ......... 30 Table B-4: BFNP Unit 1 Adjusted Reference Temperatures for Up to 25 EFPY .......................... 31 Table B-5: BFNP Unit 1 Adjusted Reference Temperatures for Up to 38 EFPY .......................... 33 Table B-6: BFNP Unit 1 RPV Beltline P-T Curve Input Values for 38 EFPY .............................. 35 Table B-7: BFNP Unit 1 Definition of RPV Beltline Region[] ...................................................... 36 Table C-I: BFNP Unit 1 Checklist ................................................................................................ 38 FIGURES Figure 1: BFNP Unit I Composite Curve A Pressure Test P-T Curves Effective for Up to 2 5 E FP Y ................................................................................................................................................ 11 Figure 2: BFNP Unit 1 Composite Curve B Core Not Critical Including Bottom Head and Curve C Core Critical P-T Curves Effective for Up to 25 EFPY ............................................................... 12 Figure 3: BFNP Unit 1 Composite Curve A Pressure Test P-T Curves Effective for Up to 3 8 E FP Y ................................................................................................................................................ 13 Figure 4: BFNP Unit I Composite Curve B Core Not Critical Including Bottom Head and Curve C Core Critical P-T Curves Effective for Up to 38 EFPY ............................................................... 14 Figure B-i: BFNP Unit 1 Reactor Pressure Vessel ........................................................................ 27 C o m p on en t ............................................................................................................................................ 36 iii

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ABBREVIATIONS & ACRONYMS Short Form Description

%Cu Weight percent Copper

%Ni Weight percent Nickel 1/4T /4 depth into the vessel wall from the inside diameter 3/4T 33/4 depth into the vessel wall from the inside diameter ASME American Society of Mechanical Engineers ART Adjusted Reference Temperature BAF Bottom of Active Fuel BFNP Browns Ferry Nuclear Plant BWR Boiling Water Reactor BWR/6 BWR Product Line 6 BWRVIP BWR Vessel and Internals Project CF Chemistry Factor CMTR Certified Material Test Report CRD Control Rod Drive EFPY Effective Full Power Years EPRI Electric Power Research Institute ESW Electroslag Weld FW Feedwater GEH GE-Hitachi Nuclear Energy Americas LLC GL Generic Letter ID Inside Diameter ISP Integrated Surveillance Program LTR Licensing Topical Report n/cmP neutrons per square centimeter (measure of fluence)

N 16 BFNP Unit I Water Level Instrumentation Nozzle NDT Nil Ductility Transition NRC Nuclear Regulatory Commission P/T Pressure and Temperature P-T Pressure-Temperature PTLR Pressure and Temperature Limits Report RCPB Reactor Coolant Pressure Boundary RCS Reactor Coolant System RG Regulatory Guide RPV Reactor Pressure Vessel RTNDT Reference Temperature of Nil Ductility Transition RVID Reactor Vessel Integrity Database (by NRC)

SAW Submerged Arc Weld SSP Supplemental Surveillance Program TAF Top of Active Fuel TS Technical Specification TVA Tennessee Valley Authority UFSAR Updated Final Safety Analysis Report iv

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Short Form Description US United States WLI Water Level Instrumentation WRC Welding Research Council V

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 1.0 Purpose The purpose of the Browns Ferry Nuclear Plant (BFNP) Unit 1 Pressure and Temperature Limits Report (PTLR) is to present operating limits relating to:

1. Reactor Coolant System (RCS) Pressure versus Temperature limits during Heatup, Cooldown and Hydrostatic/Class I Leak Testing;

2. RCS Heatup and Cooldown rates;

3. Reactor Pressure Vessel (RPV) to RCS coolant AT requirements during Recirculation Pump startups;

4. RPV bottom head coolant temperature to RPV coolant temperature AT requirements during Recirculation Pump startups;

5. RPV head flange bolt-up temperature limits.

This report has been prepared in accordance with the requirements defined in Reference 6.2.

2.0 Applicability This report is applicable to the BFNP Unit 1 RPV for up to 25 and 38 Effective Full Power Years (EFPY), representing a 60-year license.

The following Technical Specification (TS) is affected by the information contained in this report:

TS 3.4.9 RCS Pressure and Temperature (P/T) Limits 3.0 Methodology The limits in this report were derived from the Nuclear Regulatory Commission (NRC)-approved methods listed in the specific revisions listed below:

1. The neutron fluence was calculated per Licensing Topical Report (LTR), General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation, NEDC-32983P-A, Revision 2, January 2006, approved in Reference 6.1.

2. The pressure and temperature limits were calculated per GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves, NEDC-33178P-A, Revision 1, June 2009, approved in Reference 6.2.

3. This revision of the pressure and temperature limits is to incorporate the following changes:

Application of GEH Topical Report for Pressure-Temperature (P-T)

Curves

The Water Level Instrumentation (WLI) nozzle that occurs in the beltline region was fabricated from non-ferritic Inconel material and has been considered in the Adjusted Reference Temperature (ART) evaluation. The 1

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) material properties of the (( 1] material have been considered with the fluence for the nozzle location.

Application of new Integrated Surveillance Program (ISP) testing and analysis results from the BFNP Unit 2 surveillance capsule that are applicable to BFNP Unit 1.

3.1 Chemistry The N16 WLI nozzle is defined as being within the beltline region, and is evaluated for ART.

This nozzle is fabricated from non-ferritic Inconel materials. Therefore, the chemistry for the R)) to evaluate the ART to represent this nozzle forging.

Chemistry for all other materials remains unchanged from those used in the development of the currently licensed P-T curves.

Surveillance materials are evaluated using the chemistries obtained from Boiling Water Reactor (BWR) Vessel and Internals Project (BWRVIP)-135, Revision 2, as presented in Section 3.4. It is noted that there are no best estimate chemistries for the BFNP Unit 1 beltline materials described in BWRVIP-135.

The Chemistry Factors (CFs) for all materials are calculated based upon the requirements of Regulatory Guide (RG) 1.99, Revision 2.

3.2 Initial Reference Temperature of Nil Ductility Transition The N 16 WLI nozzle is evaluated for ART. As the nozzle forging is fabricated from Inconel, for which fracture toughness evaluations are not required, the ((

1] are used.

Surveillance materials are evaluated using the limiting initial RTNDT of the beltline plate or weld material.

Initial RTNDTS for all other beltline materials remain unchanged from those used in the development of the currently licensed P-T curves.

3.3 Adjusted Reference Temperature The ART values for 25 and 38 EFPY included in Appendix B are developed considering the latest BWRVIP ISP data available that is representative of the applicable materials in the BFNP Unit I RPV (Reference 6.3). The surveillance data used in the BFNP Unit I ART calculations are not obtained from actual BFNP Unit 1 RPV test specimens. The ISP plate materials are not limiting with respect to the ART. The ISP weld is the limiting material; this value is considered in the development of the P-T curves because the ISP material is the identical heat to the material in the BFNP Unit I RPV.

The N 16 nozzle ART is determined considering the initial RTNDT E[]

material together with the fluence at the nozzle elevation.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 3.4 Surveillance Program As discussed in Appendix A, BFNP Unit 1 participates in the ISP. All three (3) of the surveillance capsules, installed at plant startup, remain in the vessel. As BFNP Unit 1 is not a host plant, the three (3) surveillance capsules have an ISP status designation of deferred (standby) per Reference 6.4.

BWRVIP-135, Revision 2 and Reference 6.5 provide the surveillance data considered in determining the chemistry and any adjusted CFs for the beltline materials.

Excerpt from BWRVIP-135, Revision 2:

For BFNP Unit 1, the ISP representative plate, heat Er )) target plate. This heat was contained in two (2) BFNP Unit 2 capsules that have been tested and analyzed. The resultant chemistry is (( )) Cu and (( )) Ni. The CF from RG 1.99, Revision 2 is Er )). The fitted CF is (( )); however, as the ISP material ((

target material, the ART table evaluated the ISP plate material (( )). This material (( )) in determining the limiting ART for the PT curves; this ((

)) the limiting material.

Excerpt from BWRVIP-135, Revision 2:

Er For BFNP Unit 1, the ISP representative weld, heat ((

)) target weld. This heat was contained in Supplemental Surveillance capsules that have been tested and analyzed. The resultant chemistry is Er )) Cu and (( )) Ni. The CF from RG 1.99 is (( )). The fitted CF is Er )), calculated using surveillance data. The scatter in this data ((

)). Because the ((

)) in the ART calculation. In addition, the EE 1] This material (( )) the limiting ART for the PT curves.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Excerpt from BWRVIP-135, Revision 2:

((I Should actual surveillance capsules be withdrawn and tested from the BFNP Unit 1 RPV (e.g., status change to be an ISP host plant under the BWRVIP ISP), compliance with 10 CFR 50 Appendix H requirements on reporting test results and evaluations on the effects to plant operations parameters (e.g., P-T limits, hydrostatic and leak test conditions) will be in accordance with Section 3 of Reference 6.3.

3.5 Reactor Coolant Pressure Boundary American Society of Mechanical Engineers (ASME) Code Section XI, Appendix G, Article G-3000, paragraph G-3 100 states that for materials "used for piping, pumps, and valves for which impact tests are required (NB-23 11), the tests and acceptance standards of Section III, Division 1 are considered to be adequate to prevent non-ductile failure under the loadings and with the defect sizes encountered under normal, upset, and testing conditions. Level C and Level D Service Limits should be evaluated on an individual case basis (G-2300)." As described in Section 4.3 of Reference 6.1, (( )) the development of all non-beltline PT limits.

ASME Section III, Paragraph NB-2332 states that "Pressure-retaining materials (other than bolting) with nominal thickness over 2.5 inches for piping (pipe and tubes) and materials for pumps, valves and fittings with any pipe connection of nominal wall thickness greater than 2.5 inches shall meet the requirements of NB-233 1. The lowest service temperature shall be not lower than RTNDT + 100°F unless a lower temperature is justified by following the methods similar to those contained in Article G-2000." All BFNP Unit 1 ferritic Reactor Coolant Pressure Boundary (RCPB) piping has nominal wall thicknesses less than 2.5 inches. Other Class 1 RCPB components are significantly smaller with nominal wall thicknesses well below 2.5 inches, including all of the ferritic RCPB components. The lowest service temperatures may be less than 250'F in some cases; however the methods of Appendix G have been followed to justify lower temperatures. Therefore, the requirements of NB-2332 have been met, and there are no ferritic RCPB piping components that require consideration in the RPV P-T curves for BFNP Unit 1.

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The ((

)), are more limiting relative to stress than any of the Class 1 ferritic branch piping in the RCPB.

With respect to concern regarding irradiation effects on RCPB piping, a qualitative fluence assessment was performed. With a 38 EFPY peak surface Inside Diameter (ID) fluence of 2

1.58e18 n/cm 2 as the maximum fluence of concern, accrual of fluence greater than 1.Oel 7 n/cm outside the vessel for 38 EFPY is not expected, based on historical calculations of flux vs. vessel thickness.

As discussed in the BFNP Updated Final Safety Analysis Report (UFSAR), it is noted that the manner in which the RCPB was designed and constructed was to ensure a high degree of integrity with adequate toughness throughout the plant life. The RCPB components were designed and fabricated, and are maintained and tested such that adequate assurance is provided that the boundary will behave in a non-brittle manner throughout the life of the plant.

3.6 Future Changes Changes to the curves, limits, or parameters within this PTLR, based upon new irradiation fluence data of the RPV, or other plant design assumptions in the UFSAR, can be made pursuant to 10 CFR 50.59, provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance.

4.0 Operating Limits The P-T curves provided in this report represent steam dome pressure versus minimum vessel metal temperature and incorporate the appropriate non-beltline limits and irradiation embrittlement effects in the beltline region.

The operating limits for pressure and temperature are required for three categories of operation:

(a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatup/cooldown (core not critical), referred to as Curve B; and (c) core critical operation, referred to as Curve C.

Complete P-T curves were developed for 25 and 38 EFPY. The P-T curves are provided in Figures 1 through 4, and a tabulation of the curves is included in Table 1 (25 EFPY) and Table 2 (38 EFPY).

Other temperature limits applicable to the RPV and controlled by the Technical Specification are:

" Heatup and Cooldown rate limit during Hydrostatic and Class 1 Leak Testing:

< 15'F/hour.

" Normal Operating Heatup and Cooldown rate limit: __100lF/hour.

RPV bottom head coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: < 145°F.

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Recirculation loop coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: < 50'F.

RPV flange and adjacent shell temperature limit: > 80'F.

5.0 Discussion The procedures described in References 6.1 and 6.2 were used in the development of the P-T curves for BFNP Unit 1.

The method for determining the initial RTNDT for all vessel materials is defined in Section 4.1.2 of Reference 6.2. Initial RTNDT values for all vessel materials considered are presented in tables in Appendix B of this report.

In order to ensure that the limiting vessel discontinuity has been considered in the development of the P-T curves, the methods in Sections 4.3.2.1 and 4.3.2.2 of Reference 6.2 for the non-beltline and beltline regions, respectively, are applied.

In order to determine how much to shift the P-T curves, an evaluation is performed using Tables 4-4a and 4-5a from NEDC-33178P-A (Reference 6.2). These tables define the ((

)) curves.

Each component listed in these tables is (( )) for each component. The required temperature is then determined by ((

)), thereby resulting in the required T for the curve. As the upper vessel curve is initially based on the (( )) T-RThNyT, all resulting T values are compared to the (( )). The ((

)) the upper vessel curve. The same method is applied for the (( )) curve. In this manner, it is assured that each curve bounds the

[)) that is represented.

For the BFNP Unit 1 upper vessel curve, the maximum T value from the method described above is (( )). The initial required T-RTN-oT for the U)); this is then adjusted by the BFNP Unit 1-specific

[R )), resulting in ((

Comparing this to the other components bounded by the upper vessel curve, the limiting value is for the (( )). The required T-RTNDT for the ((

)), which is (( )). It is seen that the resulting T required for the (( )). As (( )) is limiting, the BFNP Unit 1 upper vessel curve is based on an RTNDT of ((

)). As noted above, this calculation was performed for each component shown in Table 4-4a of NEDC-33178P-A (Reference 6.2); only the limiting cases are presented here.

For the BFNP Unit 1 bottom head or CRD ((

)), the maximum T value from the method described above is ((

)). The required T-RTNDT for the EE

)); this is adjusted by the BFNP Unit 1-specific maximum ((

)), resulting in (( )). Comparing this to the next limiting value, the 6

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) required T-RTNDT is (( )), which is added to the ((

)). It is seen that the resulting T required for the (( )). As

((i )), the BFNP Unit 1 bottom head (CRD) curve is based on an E(( )). As noted above, this calculation was performed for each component shown in Table 4-5a of NEDC-33178P-A (Reference 6.2); only the limiting case is presented here.

Appendix H of NEDC-33178P-A (Reference 6.2) contains the details of an analysis performed to determine the baseline requirement (non-shifted) for the ((

)). It can be seen in Section H.5 of Appendix H that the stresses developed in this finite element analysis demonstrated that the 11 11, resulting in a baseline non-shifted required T-RTNDT of [

)). Therefore, considering the determination of the required shift from the paragraph above for (( )), calculations for all components listed in Table 4-5a of NEDC-33178P-A were compared to the CRD T, which is (( )) (where ((

)) materials). Therefore, the shift for the bottom head [.

For BFNP Unit 1, the limiting surveillance material, E[ )), was considered using (( )) as defined in Appendix I of Reference 6.2. This procedure was used because the target vessel material and the surveillance material (( )). As this material is a (( )), the use of the ((

)) is considered.

The calculated value of [l

)) material for the beltline P-T curves.

For BFNP Unit 1, there are thickness discontinuities in the vessel: (1) between the bottom head upper and lower torus; and (2) between the bottom head torus and the support skirt attachment.

The P-T curves defined in Section 4.3 of Reference 6.2 are based upon an RTNDT of 56'F for the bottom head (( )), and 51 'F for the upper vessel. The 25 EFPY beltline curves are based on an ART of 128'F, and the 38 EFPY beltline curves are based on an ART of 146'F. Curves based on these temperatures bound the requirements due to the beltline thickness discontinuities.

The ART of the limiting beltline material is used to adjust the beltline P-T curves to account for irradiation effects. RG 1.99, Revision 2 provides the methods for determining the ART. The basis for the difference in the margin terms in Tables B-4 and B-5 is due, in part, to the effective fluence associated with 25 and 38 EFPY. For many of the BFNP Unit 1 materials, the margin term is dependent on the ARTNDT. This is consistent with Position 1.1 of RG 1.99, Revision 2, which provides the methodology for determining ART. The final paragraph of this section of the RG states that aA (standard deviation for ARTNDT) is 170F for plates and 28'F for welds, but that aA need not exceed 0.5*ARTNDT. The BFNP Unit 1 ART calculation has incorporated the use of 7

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 0.5*ARTND- for all materials, where applicable. The full margin term was used for the ((

The vessel beltline copper and nickel values were obtained from plant-specific vessel purchase order records, Certified Material Test Reports (CMTRs), or are values previously approved by the NRC, and remain unchanged from previous submittals.

The pressure head for the beltline hydrostatic test curve (Curve A) for BFNP Unit 1 is

(( )). This is determined using the height of the vessel and the elevation of the bottom of active fuel. The full vessel pressure head is (( )). This pressure is used in the P-T curve analysis, considered in the determination of KI for the bottom head curve as discussed in Sections 4.3.2.1.1 and 4.3.2.2.2 of the LTR.

The P-T curves for the non-beltline region were conservatively developed for a BWR ((

)) with nominal ID of (( )). As discussed in Section 4.3.2.1.1 of the LTR, if the plant-specific result of Equation 4-3 is greater than that of the (( ))

from Equation 4-2, the user is directed to perform a plant-specific evaluation. The plant-specific BFNP Unit 1 geometry demonstrates that it is bounded by the Equation 4-2 result:

BFNP Unit 1: R / t1/ 2 = (( ))

The analysis is therefore considered appropriate for BFNP Unit 1. The (( )) was adapted to the conditions at BFNP Unit 1 using plant-specific RTNDT values for the RPV.

The peak RPV ID fluence used in the P-T curve evaluation for BFNP Unit 1 at 25 EFPY is 1.01 e 18 n/cm 2 and at 38 EFPY is 1.58e18 n/cm 2. These values were calculated using methods that comply with the guidelines of RG 1.190, (as discussed in Reference 6.1). This fluence applies to the lower-intermediate shell plates and longitudinal welds. The fluence is adjusted for the lower plates, associated longitudinal welds, and the girth weld based upon the axial fluence distribution calculated as part of the fluence evaluation; hence, the peak ID surface fluence for these components is 8.14e17 n/cm 2 for 25 EFPY and 1.28e18 n/cm2 for 38 EFPY. Similarly, the fluence is adjusted for the N16 nozzle based upon the axial fluence distribution; hence, the peak ID surface fluence used for this component is 3.04e1 7 n/cm 2 for 25 EFPY and 4.77e1 7 n/cm 2 for 38 EFPY.

The P-T curves for the heatup and cooldown operating conditions at a given EFPY apply for both the 1/4T and 3/4T locations. When combining pressure and thermal stresses, it is usually necessary to evaluate stresses at the 1/4T location (inside surface flaw) and the 3/4T location (outside surface flaw). This is because the thermal gradient tensile stress of interest is in the inner wall during cooldown and the outer wall during heatup. However, as a conservative simplification, the thermal gradient stress at the l/4T location is assumed to be tensile for both heatup and cooldown. This results in the approach of applying the maximum tensile stress at the 1/4T location. This approach is conservative because irradiation effects cause the allowable toughness, KI, at 1/4T to be less than that at 3/4T for a given metal temperature. This approach causes no operational difficulties, because the BWR is at steam saturation conditions during normal operation, well above the heatup/cooldown curve limits.

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For the core not critical curve (Curve B) and the core critical curve (Curve C), the P-T curves specify a coolant heatup and cooldown temperature rate of < 1000F/hr for which the curves are applicable. However, the core not critical and the core critical curves were also developed to bound transients defined on the RPV thermal cycle diagram and the nozzle thermal cycle diagrams. For the hydrostatic pressure and leak test curve (Curve A), a coolant heatup and cooldown temperature rate of < 15°F/hr must be maintained. The P-T limits and corresponding heatup/cooldown rates of either Curve A or B may be applied while achieving or recovering from test conditions. Curve A applies during pressure testing and when the limits of Curve B cannot be maintained.

As shown in Tables B-4 and B-5, the ((

)). However, the material is contained in the ((

)). When comparing the required T-RTNDT for the ((

)) provides a more restrictive curve. This is due to the reduced ((

)) as discussed in Section 4.3.2.2.2 of the LTR. Therefore, for BFNP Unit 1, the axial electroslag weld heat is the limiting material for the beltline region for 25 and 38 EFPY. The initial RTNDT for electroslag weld heat material is 23.1 OF. The generic pressure test P-T curve is applied to the BFNP Unit I beltline curve by shifting the P vs. (T - RTNDT) values to reflect the ART value of 128°F for 25 EFPY and 146 0 F for 38 EFPY.

Using the fluence discussed above, the P-T curves are beltline limited for Curves A, B, and C, for 25 and 38 EFPY. For 25 EFPY, Curve A is beltline limited above 640 psig; Curve B and Curve C are beltline limited above 500 psig. For 38 EFPY, Curve A is beltline limited above 570 psig; Curve B and Curve C are beltline limited above 410 psig and 420 psig, respectively.

For Curve C, the upper vessel and beltline regions are bounding at pressures up to 50 psig. For pressures between 60 psig and 312.5 psig, the upper vessel is bounding; this is true for both 25 and 38 EFPY.

The N16 WLI nozzle is a partial penetration design similar to that shown in Figure 1 in Appendix J of the LTR, fabricated with a (( )). Reference to this status is contained in the BFNP UFSAR. Therefore, the evaluation is performed, consistent with the statement in Appendix J, ((

)). Appendix J of the LTR provides detailed results of an analysis performed for the WLI nozzle that provides the ((

)) a specific curve applicable for the WLI nozzle to ensure that this location is bounded in the P-T curves. The nozzle curve (( )) for BFNP Unit 1 Curves A, B, or C. Sample calculations are provided in Appendix D.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 6.0 References 6.1 Letter, Herbert N Berkow (NRC) to George B. Stramback (GE), Final Safety Evaluation Regarding Removal of Methodology Limitationsfor NEDC-32983P-A, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation (TAC NO.

MC3 788), November 17, 2005.

6.2 Letter, Thomas B. Blount (NRC) to Doug Coleman (BWROG), Final Safety Evaluation for Boiling Water Reactors Owners' Group Licensing Topical Report NEDC-33178P, General Electric Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves (TAC NO. MD2693), April 27, 2009.

6.3 B WR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations, BWRVIP-135, Revision 2, Electric Power Research Institute, Palo Alto, CA, October 2009 (EPRI Proprietary).

6.4 B WR Vessel and Internals Project, UpdatedB WR IntegratedSurveillance Program (ISP)

Implementation Plan, BWRVIP-86, Revision 1, EPRI, Palo Alto, CA: September 2008.

1016575. (EPRI Proprietary).

6.5 Letter 2013-050, Bob Carter (EPRI) to Victor Schiavone (TVA), Evaluation of the Browns Ferry Unit 2 1200 Surveillance Capsule Data, EPRI, Palo Alto, CA, April 10, 2013 (EPRI Proprietary).

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 1400 - -

1300 INITIAL RTNDT VALUES ARE 23°F FOR BELTLINE, 51°F FOR UPPER VESSEL, AND 1100AN 56°F FOR BOTTOM HEAD 1000 BELTLINE CURVES

/ADJUSTED AS SHOWN:

EFPY SHIFT ('F)

I- 25 105 0

11 800 HEATUP/COOLDOWN IU RATE OF COOLANT

>~< 15oFIHR W 700 0 640 psig W 600 ---

Z- ACCEPTABLE REGION OF OPERATION IS TO

"* 500 THE RIGHT OF THE wU APPLICABLE CURVE 400 BOTTOM U) ~ HEAD w) 68*F 300

-UPPER VESSEL 200 AND BELTLINE LIMITS BOTTOM HEAD 100 CURVE 0 -

0 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Figure 1: BFNP Unit 1 Composite Curve A Pressure Test P-T Curves Effective for Up to 25 EFPY 1l

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

B C 1400 INITIAL RTNDT VALUES 1300 ARE 23.1°F FOR BELTLINE, 51°F FOR UPPER 1200 VESSEL, AND 56"F FOR BOTTOM HEAD 1100 BELTLINE CURVES

.9 1000 ADJUSTED AS SHOWN:

EFPY SHIFT (*F) 25 105

[ I CL 900 HEATUP/COOLDOWN 0 RATE OF COOLANT

_j < 15°F/HR FOR CURVE A, LU 800 100°F/HR FOR LU CURVES B&C 0) 700 I-600 ACCEPTABLE REGION OF OPERATION ISTO THE LU RIGHTOFTHE 500 APPLICABLE CURVE LU 400 Co 300

Bottom Head Curve B

-Composite Curve B 200 -Composite Curve C 100 0

0 25 50 75 100 125 150 175 200 225 250 275 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (=F)

Figure 2: BFNP Unit 1 Composite Curve B Core Not Critical Including Bottom Head and Curve C Core Critical P-T Curves Effective for Up to 25 EFPY 12

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 1400 1300 INITIAL RTNDT VALUES ARE 23.1°F FOR BELTLINE, 1200 51°F FOR UPPER VESSEL, AND 1100 56"F FOR BOTTOM HEAD Is

.S1000 BELTLINE CURVES ADJUSTED AS SHOWN:

Z 900 EFPY SHIFT ('F)

IL 38 123 0

w 800 HEATUP/COOLDOWN LU RATE OF COOLANT

< 15°F/HR a 700 0

S600 z ACCEPTABLE REGION OF OPERATION ISTO N 500 THE RIGHT OF THE LU APPLICABLE CURVE 400 U3 LU 300

-UPPER VESSEL 200 AND BELTLINE LIMITS

BOTTOM HEAD 100 CURVE 0

0 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE ('F)

Figure 3: BFNP Unit 1 Composite Curve A Pressure Test P-T Curves Effective for Up to 38 EFPY 13

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

B C 1400 INITIAL RTNDT VALUES 1300 ARE 23.1°F FOR BELTLINE, 51"F FOR UPPER 1200 VESSEL, AND 560 F FOR BOTTOM HEAD 1100 BELTLINE CURVES 1000 ADJUSTED AS SHOWN:

EFPY SHIFT (*F) 38 123 I.

0 900 w

800 0

700 Lu 600 ACCEPTABLE REGION OF Cn w OPERATION ISTO THE RIGHT OF THE 500 APPLICABLE CURVE 400 300 ------- Bottom Head Curve B

- Composite Curve B 200 - Composite Curve C 100 0 I!IL 0 25 50 75 12LTU 100 125 150 175 200 225 250 275 300 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure 4: BFNP Unit 1 Composite Curve B Core Not Critical Including Bottom Head and Curve C Core Critical P-T Curves Effective for Up to 38 EFPY 14

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table 1: BFNP Unit 1 Tabulation of Curves - 25 EFPY BOTTOM UPPER RPV & BOTTOM UPPER RPV &

LIMITING PRESSURE25EP HEAD BELTLINE AT HEAD BELTLINE AT (PSIG)25 EFPY 25 EFPY 25 EFPY (PSIG) CURVE A CURVE A CURVE C CURVE B CURVE B (OF)

(OF) (OF) (OF) (OF) 0 68.0 83.1 68.0 83.1 83.1 10 68.0 83.1 68.0 83.1 83.1 20 68.0 83.1 68.0 83.1 83.1 30 68.0 83.1 68.0 83.1 83.1 40 68.0 83.1 68.0 83.1 83.1 50 68.0 83.1 68.0 83.1 83.1 60 68.0 83.1 68.0 83.1 91.0 70 68.0 83.1 68.0 83.1 98.2 80 68.0 83.1 68.0 83.1 104.2 90 68.0 83.1 68.0 83.1 109.3 100 68.0 83.1 68.0 83.1 113.8 110 68.0 83.1 68.0 83.1 117.9 120 68.0 83.1 68.0 83.1 121.7 130 68.0 83.1 68.0 85.2 125.2 140 68.0 83.1 68.0 88.4 128.4 150 68.0 83.1 68.0 91.2 131.2 160 68.0 83.1 68.0 93.9 133.9 170 68.0 83.1 68.0 96.5 136.5 180 68.0 83.1 68.0 98.9 138.9 190 68.0 83.1 68.0 101.2 141.2 200 68.0 83.1 68.0 103.3 143.3 210 68.0 83.1 68.0 105.3 145.3 220 68.0 83.1 68.0 107.3 147.3 230 68.0 83.1 68.0 109.1 149.1 240 68.0 83.1 68.0 110.9 150.9 250 68.0 83.1 68.0 112.6 152.6 260 68.0 83.1 68.0 114.2 154.2 270 68.0 83.1 68.0 115.8 155.8 280 68.0 83.1 68.0 117.3 157.3 290 68.0 83.1 68.0 118.8 158.8 300 68.0 83.1 68.0 120.2 160.2 310 68.0 83.1 68.0 121.5 161.5 312.5 68.0 83.1 68.0 121.9 161.9 312.5 68.0 113.1 68.0 143.1 183.1 15

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BOTTOM UPPER RPV & BOTTOM UPPER RPV &

LIMITING HEAD BELTLINE AT HEAD BELTLINE AT PRESSURE 25 EFPY 25 EFPY 25 EFPY CURVE C (PSIG)

CURVE A CURVE A CURVE B CURVE B (OF) (OF) (OF)

(OF) (OF) 320 68.0 113.1 68.0 143.1 183.1 330 68.0 113.1 68.0 143.1 183.1 340 68.0 113.1 68.0 143.1 183.1 350 68.0 113.1 68.0 143.1 183.1 360 68.0 113.1 68.0 143.1 183.1 370 68.0 113.1 68.0 143.1 183.1 380 68.0 113.1 68.0 143.1 183.1 390 68.0 113.1 68.0 143.1 183.1 400 68.0 113.1 68.0 143.1 183.1 410 68.0 113.1 68.0 143.1 183.1 420 68.0 113.1 68.0 143.1 183.1 430 68.0 113.1 68.0 143.1 183.1 440 68.0 113.1 70.4 143.1 183.1 450 68.0 113.1 73.3 143.1 183.1 460 68.0 113.1 76.0 143.1 183.1 470 68.0 113.1 78.6 143.1 183.1 480 68.0 113.1 81.1 143.1 183.1 490 68.0 113.1 83.4 143.1 183.1 500 68.0 113.1 85.6 143.1 183.1 510 68.0 113.1 87.8 143.8 183.8 520 68.0 113.1 89.8 145.5 185.5 530 68.0 113.1 91.8 147.0 187.0 540 68.0 113.1 93.7 148.6 188.6 550 68.0 113.1 95.5 150.1 190.1 560 68.0 113.1 97.3 151.5 191.5 570 68.0 113.1 99.0 152.9 192.9 580 68.0 113.1 100.6 154.3 194.3 590 68.0 113.1 102.2 155.6 195.6 600 68.0 113.1 103.8 156.9 196.9 610 68.0 113.1 105.3 158.1 198.1 620 68.0 113.1 106.7 159.4 199.4 630 68.0 113.1 108.1 160.6 200.6 640 68.0 113.1 109.5 161.7 201.7 650 68.2 115.3 110.8 162.9 202.9 660 69.9 117.4 112.1 164.0 204.0 16

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

BOTTOM UPPER RPV & BOTTOM UPPER RPV &

LIMITING HEAD BELTLINE AT HEAD BELTLINE AT PRESSURE 25 EFPY 25 EFPY 25 EFPY (PSIG) CURVE C CURVE A CURVE A CURVE B CURVE B (OF)

(OF) (OF) (OF) (OF) 670 71.6 119.5 113.4 165.1 205.1 680 73.2 121.5 114.7 166.2 206.2 690 74.7 123.4 115.9 167.2 207.2 700 76.2 125.2 117.0 168.2 208.2 710 77.7 127.0 118.2 169.2 209.2 720 79.1 128.7 119.3 170.2 210.2 730 80.5 130.3 120.4 171.2 211.2 740 81.8 131.9 121.5 172.1 212.1 750 83.1 133.5 122.6 173.1 213.1 760 84.4 135.0 123.6 174.0 214.0 770 85.6 136.5 124.6 174.9 214.9 780 86.8 137.9 125.6 175.8 215.8 790 88.0 139.3 126.6 176.6 216.6 800 89.2 140.6 127.5 177.5 217.5 810 90.3 141.9 128.5 178.3 218.3 820 91.4 143.2 129.4 179.2 219.2 830 92.5 144.4 130.3 180.0 220.0 840 93.5 145.6 131.2 180.8 220.8 850 94.6 146.8 132.0 181.5 221.5 860 95.6 148.0 132.9 182.3 222.3 870 96.6 149.1 133.7 183.1 223.1 880 97.5 150.2 134.6 183.8 223.8 890 98.5 151.3 135.4 184.6 224.6 900 99.4 152.4 136.2 185.3 225.3 910 100.4 153.4 137.0 186.0 226.0 920 101.3 154.4 137.7 186.7 226.7 930 102.1 155.4 138.5 187.4 227.4 940 103.0 156.4 139.3 188.1 228.1 950 103.9 157.3 140.0 188.8 228.8 960 104.7 158.3 140.7 189.5 229.5 970 105.6 159.2 141.5 190.1 230.1 980 106.4 160.1 142.2 190.8 230.8 990 107.2 161.0 142.9 191.4 231.4 1000 108.0 161.9 143.6 192.0 232.0 1010 108.7 162.7 144.2 192.7 232.7 17

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BOTTOM UPPER RPV & BOTTOM UPPER RPV &

LIMITING PRESSURE25EP HEAD BELTLINE AT HEAD BELTLINE AT 25 EFPY (PSIG)25 EFPY 25 EFPY (PSIG) CURVE A CURVE A CURVE C CURVE B CURVE B (OF)

(OF) (OF) (OF) (OF) 1015 109.1 163.1 144.6 193.0 233.0 1020 109.5 163.6 144.9 193.3 233.3 1030 110.3 164.4 145.6 193.9 233.9 1035 110.6 164.8 145.9 194.2 234.2 1040 111.0 165.2 146.2 194.5 234.5 1050 111.7 166.0 146.9 195.1 235.1 1055 112.1 166.4 147.2 195.4 235.4 1060 112.4 166.8 147.5 195.7 235.7 1070 113.2 167.6 148.1 196.3 236.3 1080 113.9 168.4 148.8 196.9 236.9 1090 114.6 169.1 149.4 197.4 237.4 1100 115.2 169.9 150.0 198.0 238.0 1105 115.6 170.2 150.3 198.3 238.3 1110 115.9 170.6 150.6 198.6 238.6 1120 116.6 171.3 151.2 199.1 239.1 1130 117.2 172.0 151.8 199.6 239.6 1140 117.9 172.7 152.3 200.2 240.2 1150 118.5 173.4 152.9 200.7 240.7 1160 119.1 174.1 153.5 201.2 241.2 1170 119.8 174.8 154.0 201.8 241.8 1180 120.4 175.4 154.6 202.3 242.3 1190 121.0 176.1 155.1 202.8 242.8 1200 121.6 176.7 155.7 203.3 243.3 1210 122.2 177.4 156.2 203.8 243.8 1220 122.8 178.0 156.8 204.3 244.3 1230 123.3 178.6 157.3 204.8 244.8 1240 123.9 179.2 157.8 205.3 245.3 1250 124.5 179.9 158.3 205.8 245.8 1260 125.0 180.5 158.8 206.2 246.2 1270 125.6 181.0 159.3 206.7 246.7 1280 126.1 181.6 159.8 207.2 247.2 1290 126.7 182.2 160.3 207.6 247.6 1300 127.2 182.8 160.8 208.1 248.1 1310 127.7 183.4 161.3 208.6 248.6 1320 128.3 183.9 161.8 209.0 249.0 18

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

BOTTOM UPPER RPV & BOTTOM UPPER RPV &

LIMITING PRESSURE25EP HEAD BELTLINE AT HEAD BELTLINE AT EFPY 25 EFPY (PSIG)25 25 EFPY (PSIG) CURVE A CURVE A CURVE C CURVE B CURVE B (OF)

(OF) (OF) (OF) (OF) 1330 128.8 184.5 162.2 209.5 249.5 1340 129.3 185.0 162.7 209.9 249.9 1350 129.8 185.6 163.2 210.3 250.3 1360 130.3 186.1 163.6 210.8 250.8 1370 130.8 186.6 164.1 211.2 251.2 1380 131.3 187.1 164.5 211.6 251.6 1390 131.8 187.7 165.0 212.1 252.1 1400 132.3 188.2 165.4 212.5 252.5 19

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table 2: BFNP Unit 1 Tabulation of Curves - 38 EFPY UPPER RPV UPPER RPV BOTTOM & BOTTOM &

LIMITING HEAD BELTLINE HEAD BELTLINE PRESSURE 38 EFPY AT AT (PSIG) CURVE C CURVE A 38EFPY CURVE B 38 EFPY (OF) CURVE A (OF)

(OF) CURVE B (OF)

(OF) 0 68.0 83.1 68.0 83.1 83.1 10 68.0 83.1 68.0 83.1 83.1 20 68.0 83.1 68.0 83.1 83.1 30 68.0 83.1 68.0 83.1 83.1 40 68.0 83.1 68.0 83.1 83.1 50 68.0 83.1 68.0 83.1 83.1 60 68.0 83.1 68.0 83.1 91.0 70 68.0 83.1 68.0 83.1 98.2 80 68.0 83.1 68.0 83.1 104.2 90 68.0 83.1 68.0 83.1 109.3 100 68.0 83.1 68.0 83.1 113.8 110 68.0 83.1 68.0 83.1 117.9 120 68.0 83.1 68.0 83.1 121.7 130 68.0 83.1 68.0 85.2 125.2 140 68.0 83.1 68.0 88.4 128.4 150 68.0 83.1 68.0 91.2 131.2 160 68.0 83.1 68.0 93.9 133.9 170 68.0 83.1 68.0 96.5 136.5 180 68.0 83.1 68.0 98.9 138.9 190 68.0 83.1 68.0 101.2 141.2 200 68.0 83.1 68.0 103.3 143.3 210 68.0 83.1 68.0 105.3 145.3 220 68.0 83.1 68.0 107.3 147.3 230 68.0 83.1 68.0 109.1 149.1 240 68.0 83.1 68.0 110.9 150.9 250 68.0 83.1 68.0 112.6 152.6 260 68.0 83.1 68.0 114.2 154.2 270 68.0 83.1 68.0 115.8 155.8 280 68.0 83.1 68.0 117.3 157.3 290 68.0 83.1 68.0 118.8 158.8 300 68.0 83.1 68.0 120.2 160.2 310 68.0 83.1 68.0 121.5 161.5 312.5 68.0 83.1 68.0 121.9 161.9 20

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

UPPER RPV UPPER RPV BOTTOM & BOTTOM &

LIMITING HEAD BELTLINE HEAD BELTLINE PRESSURE 38 EFPY AT AT (PSIG) CURVE C CURVE A 38 EFPY CURVE B 38 EFPY (OF)

(OF) CURVE A (OF) CURVE B (OF) (OF) 312.5 68.0 113.1 68.0 143.1 185.6 320 68.0 113.1 68.0 143.1 185.6 330 68.0 113.1 68.0 143.1 185.6 340 68.0 113.1 68.0 143.1 185.6 350 68.0 113.1 68.0 143.1 185.6 360 68.0 113.1 68.0 143.1 185.6 370 68.0 113.1 68.0 143.1 185.6 380 68.0 113.1 68.0 143.1 185.6 390 68.0 113.1 68.0 143.1 185.6 400 68.0 113.1 68.0 143.1 185.6 410 68.0 113.1 68.0 143.1 185.6 420 68.0 113.1 68.0 144.1 185.6 430 68.0 113.1 68.0 146.4 186.4 440 68.0 113.1 70.4 148.6 188.6 450 68.0 113.1 73.3 150.8 190.8 460 68.0 113.1 76.0 152.8 192.8 470 68.0 113.1 78.6 154.7 194.7 480 68.0 113.1 81.1 156.6 196.6 490 68.0 113.1 83.4 158.4 198.4 500 68.0 113.1 85.6 160.2 200.2 510 68.0 113.1 87.8 161.8 201.8 520 68.0 113.1 89.8 163.5 203.5 530 68.0 113.1 91.8 165.0 205.0 540 68.0 113.1 93.7 166.6 206.6 550 68.0 113.1 95.5 168.1 208.1 560 68.0 113.1 97.3 169.5 209.5 570 68.0 113.1 99.0 170.9 210.9 580 68.0 114.9 100.6 172.3 212.3 590 68.0 118.0 102.2 173.6 213.6 600 68.0 120.9 103.8 174.9 214.9 610 68.0 123.6 105.3 176.1 216.1 620 68.0 126.2 106.7 177.4 217.4 630 68.0 128.7 108.1 178.6 218.6 640 68.0 131.0 109.5 179.7 219.7 650 68.2 133.3 110.8 180.9 220.9 21

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

UPPER RPV UPPER RPV BOTTOM & BOTTOM &

LIMITING PRESSURE HEAD BELTLINE A HEAD BELTLINE (PSIG)AT 38 EFPY AT (PSIG) CURVE A 38 EFPY CURVE C CURVE B 38 EFPY (OF)

(OF) CURVE A (OF) CURVE B (OF) (OF) 660 69.9 135.4 112.1 182.0 222.0 670 71.6 137.5 113.4 183.1 223.1 680 73.2 139.5 114.7 184.2 224.2 690 74.7 141.4 115.9 185.2 225.2 700 76.2 143.2 117.0 186.2 226.2 710 77.7 145.0 118.2 187.2 227.2 720 79.1 146.7 119.3 188.2 228.2 730 80.5 148.3 120.4 189.2 229.2 740 81.8 149.9 121.5 190.1 230.1 750 83.1 151.5 122.6 191.1 231.1 760 84.4 153.0 123.6 192.0 232.0 770 85.6 154.5 124.6 192.9 232.9 780 86.8 155.9 125.6 193.8 233.8 790 88.0 157.3 126.6 194.6 234.6 800 89.2 158.6 127.5 195.5 235.5 810 90.3 159.9 128.5 196.3 236.3 820 91.4 161.2 129.4 197.2 237.2 830 92.5 162.4 130.3 198.0 238.0 840 93.5 163.6 131.2 198.8 238.8 850 94.6 164.8 132.0 199.5 239.5 860 95.6 166.0 132.9 200.3 240.3 870 96.6 167.1 133.7 201.1 241.1 880 97.5 168.2 134.6 201.8 241.8 890 98.5 169.3 135.4 202.6 242.6 900 99.4 170.4 136.2 203.3 243.3 910 100.4 171.4 137.0 204.0 244.0 920 101.3 172.4 137.7 204.7 244.7 930 102.1 173.4 138.5 205.4 245.4 940 103.0 174.4 139.3 206.1 246.1 950 103.9 175.3 140.0 206.8 246.8 960 104.7 176.3 140.7 207.5 247.5 970 105.6 177.2 141.5 208.1 248.1 980 106.4 178.1 142.2 208.8 248.8 990 107.2 179.0 142.9 209.4 249.4 1000 108.0 179.9 143.6 210.0 250.0 22

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

UPPER RPV UPPER RPV BOTTOM & BOTTOM &

LIMITING HEAD BELTLINE HEAD BELTLINE PRESSURE 38 EFPY AT AT (PSIG) CURVE C CURVE A 38 EFPY CURVE B 38 EFPY (OF)

(OF) CURVE A (OF) CURVE B (OF) (OF) 1010 108.7 180.7 144.2 210.7 250.7 1015 109.1 181.1 144.6 211.0 251.0 1020 109.5 181.6 144.9 211.3 251.3 1030 110.3 182.4 145.6 211.9 251.9 1035 110.6 182.8 145.9 212.2 252.2 1040 111.0 183.2 146.2 212.5 252.5 1050 111.7 184.0 146.9 213.1 253.1 1055 112.1 184.4 147.2 213.4 253.4 1060 112.4 184.8 147.5 213.7 253.7 1070 113.2 185.6 148.1 214.3 254.3 1080 113.9 186.4 148.8 214.9 254.9 1090 114.6 187.1 149.4 215.4 255.4 1100 115.2 187.9 150.0 216.0. 256.0 1105 115.6 188.2 150.3 216.3 256.3 1110 115.9 188.6 150.6 216.6 256.6 1120 116.6 189.3 151.2 217.1 257.1 1130 117.2 190.0 151.8 217.6 257.6 1140 117.9 190.7 152.3 218.2 258.2 1150 118.5 191.4 152.9 218.7 258.7 1160 119.1 192.1 153.5 219.2 259.2 1170 119.8 192.8 154.0 219.8 259.8 1180 120.4 193.4 154.6 220.3 260.3 1190 121.0 194.1 155.1 220.8 260.8 1200 121.6 194.7 155.7 221.3 261.3 1210 122.2 195.4 156.2 221.8 261.8 1220 122.8 196.0 156.8 222.3 262.3 1230 123.3 196.6 157.3 222.8 262.8 1240 123.9 197.2 157.8 223.3 263.3 1250 124.5 197.9 158.3 223.8 263.8 1260 125.0 198.5 158.8 224.2 264.2 1270 125.6 199.0 159.3 224.7 264.7 1280 126.1 199.6 159.8 225.2 265.2 1290 126.7 200.2 160.3 225.6 265.6 1300 127.2 200.8 160.8 226.1 266.1 1310 127.7 201.4 161.3 226.6 266.6 23

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

UPPER RPV UPPER RPV BOTTOM & BOTTOM &

LIMITING HEAD BELTLINE HEAD BELTLINE PRESSURE 38 EFPY AT AT (PSIG) CURVE C CURVE A 38 EFPY CURVE B 38 EFPY (OF)

(OF) CURVE A (OF) CURVE B (OF) (OF) 1320 128.3 201.9 161.8 227.0 267.0 1330 128.8 202.5 162.2 227.5 267.5 1340 129.3 203.0 162.7 227.9 267.9 1350 129.8 203.6 163.2 228.3 268.3 1360 130.3 204.1 163.6 228.8 268.8 1370 130.8 204.6 164.1 229.2 269.2 1380 131.3 205.1 164.5 229.6 269.6 1390 131.8 205.7 165.0 230.1 270.1 1400 132.3 206.2 165.4 230.5 270.5 24

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Appendix A Reactor Vessel Material Surveillance Program None of the BFNP Unit I surveillance capsules have been removed from the reactor vessel. All three capsules have been in the reactor vessel since plant startup.

As described in the BFNP Unit 1 UFSAR Section 4.2.6, Inspection and Testing, the BWRVIP ISP will determine the removal schedule for the remaining BFNP Unit 1 surveillance capsules.

The BFNP Unit 1 material surveillance program is administered in accordance with the BWRVIP ISP. The ISP combines the United States (US) BWR surveillance programs into a single integrated program. This program uses similar heats of materials in the surveillance programs of BWRs to represent the limiting materials in other vessels. It also adds data from the BWR SSP. Per the BWRVIP ISP, BFNP Unit 1 is not a host plant; all surveillance capsules are classified as "Deferred".

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Appendix B BFNP Unit 1 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information 26

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TOP HEAD TOP HEAD FLANGE

- SHELL FLANGE SHELL COURSE #5 SHELL COURSE #4 SHELL COURSE #3 TOP OF SHELL COURSE #2 ACTIVE FUEL (TAF) 368.3" BOTTOM OF SHELL COURSE #1 ACTIVE FUEL (BAF) 218.3" BOTTOM HEAD SUPPORT SKIRT Note: The WLI nozzle centerline is at 366" elevation, at the top of active fuel.

Figure B-i: BFNP Unit 1 Reactor Pressure Vessel 27

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table B-i: BFNP Unit 1 Initial RTNDT Values for RPV Plate and Flang Materials Test Drop Test Charpy Energy (T50r60) Weight RTNDT Component Heat Temp (ft.lb) (*F) NDT (°F)

(*F) _ (*F)

PLATES & FORGINGS:

Top Head & Flange Shell Flange (IDK48) 48-127-1 ALU 55 10 118 90 79 -20 10 10 Top Head Flange (rMK209) 209-127-1 AMW 56 10 120 109 126 -20 10 10 Top Head Dollar (MK201) Not 201-122-2 C-1354-3 40 67 58 51 10 Available 40 Top Head Side Plates (MK202) 202-122-1 A0057-2 10 45 41 55 -2 10 10 202-122-2 A0057-2 10 37 30 42 20 10 20 202-122-5 C1182-1 10 41 60 50 -2 10 10 202-122-6 C1182-1 10 57 45 62 -10 10 10 202-139-5 C2737-2 10 68 90 86 -20 10 10 202-139-6 C2737-2 10 84 78 86 -20 10 10 Shell Courses Upper Shell Plates (MK60) 6-127-7 A0973-1 10 57 60 41 -2 10 10 6-127-12 C1942-2 10 46 52 52 -12 10 10 6-127-19 C2496-2 10 56 58 54 -20 10 10 Transition Shell Plates (MK16) 15-127-2 C-2533-2 10 53 48 43 -6 10 10 15-127-5 A-0954-3 10 46 40 32 16 10 16 15-127-6 A-0954-3 10 41 52 45 -2 10 10 Upper Intermediate Shell Plates (MK59) 6-127-3 B5842-1 10 63 62 61 -20 10 10 6-127-8 A0954-1 10 52 60 55 -20 10 10 6-127-10 B5853-2 10 70 65 66 -20 10 10 Lower Intermediate Shell Plates (MK58) 6-139-19 C2884-2 10 33 55 34 14 0 14 6-139-20 C2868-2 10 46 55 25 30 0 30 6-139-21 C2753-1 10 39 58 57 2 -20 2 Lower Shell Segments (MK57) 6-127-2 B5864-1 10 84 73 62 -20 -20 -20 6-127-4 A1009-1 10 62 84 77 -20 -10 -10 6-127-1 A0999-1 10 56 59 66 -20 -20 -20 Bottom Head Bottom Head Upper Torus (MK2) 2-122-7 B5924-1 40 75 70 75 10 40 40 2-122-8 B5924-1 40 37 61 44 36 40 40 2-122-10 A0942-2 40 62 62 65 10 40 40 2-127-7 C2412-3 40 91 90 57 10 40 40 2-127-8 C2412-3 40 95 92 82 10 40 40 2-127-9 C2393-2 40 105 125 112 10 40 40 Bottom Head Lower Torus (MK4) 4-122-5 A0927-2 40 71 50 59 10 40 40 4-122-6 A0927-2 40 75 66 64 10 40 40 4-122-7 C1412-3 40 30 41 40 50 40 50 4-122-8 C1412-3 40 27 35 49 56 40 56 Bottom Head Dollar (MiK) 1-122-2 B5861-1 40 45 50 49 20 40 40 Note: Minimum Charpy values are provided for all materials.

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Table B-2: BFNP Unit 1 Initial RTNDT Values for RPV Nozzle and Weld Materials Test Drop Heat or CharpyEnergy (T5or60) Weight RTNDT Component HeatlFluxiLot Te(p (ft-lb) (OF) NDT (°F)

_ __ __ _ (*F )

Nozzles:

Ni Recirc Outlet Nozzle (MK8) 8-127-1 E31VW 431H-1 40 109 86 90 10 40 40 8-139-2 AV1696 7J-6327 40 34 46 44 42 40 42 N2 Recirc Inlet Nozzle (MK7) 7-122-1 ZT2872 9709-1 40 65 54 58 10 30 30 7-122-7 ZT2869 9704-1 40 31 38 39 48 30 48 7-127-9 E25VW 433H-9 40 93 103 110 10 40 40 7-122-10 ZT2872 9709-2 40 65 54 58 10 30 30 7-122-11 Zr2885 9711-1 40 34 37 41 42 30 42 7-122-12 ZT2885 9711-2 40 34 37 41 42 30 42 7-122-13 ZT2885-3 9710-2 40 64 48 36 39 30 39 7-122-16 ZT-2885 40 38 38 48 35 30 35 7-122-18 ZT2885 9712-2 40 54 52 49 12 30 30 7-122-19 ZT2869 9705-1 40 69 53 42 27 30 30 N3 Steam Outlet Nozzle (MK14) 14-127-1 E26VW 435H-1 40 97 77 94 10 40 40 14-127-2 E26VW 435H-2 40 86 84 76 10 40 40 14-127-3 E26VW 435H-3 40 102 92 105 10 40 40 14-127-4 E26VW 435H-4 40 119 94 94 10 40 40 N4 Feedwater Nozzle (WK10) 10-127-1 E25VW 436H-1 40 98 97 92 10 40 40 10-127-2 E25VW 436H-2 40 124 98 105 10 40 40 10-127-3 E25VW 436H-3 40 99 84 92 10 40 40 10-127-4 E25VW 436H-4 40 111 98 101 10 40 40 10-127-5 E25VW 436H-5 40 114 114 110 10 40 40 10-127-6 E25VW 436H-6 40 117 111 112 10 40 40 N5 Core Spray Nozzle (00 1) 11-111-1 BT2001-2 7098 40 48 32 42 46 40 46 11-111-2 BT2001-3 6945-1 40 54 36 49 38 40 40 N6 Top Head Instrumentation Nozzle (W206) 206-139-1 &-4 BT2615-4 40 123 143 144 10 40 40 N7 Vent Nozzle (MK204) 204-127-1 ZT3043-3 40 102 130 117 10 40 40 N8 Jet Pump Instr. Nozzle (vg19) 19-127-1 &-2 ZT3043 40 107 112 113 10 40 40 N9 CRD HYD System Return Nozzle (MK13) 13-145-1 EV9793 7K-6233A 40 81 50 91 10 40 40 N10 Core DP & Liquid Control Nozzle (MK17) 17-127-1 ZT3043 40 106 136 111 -20 40 40 Nil, N12, N16 Instrumentation Nozzle (M<12) Inconel 12-127-1 through 6 8564 N13, N14 High & Low Pressure Seal Leak (W139) 139-127-1 & -2 Not Available 40 40Q N15 Drain Nozzle (MK22) 22-127-1 213099 40 42 44 39 32 40 40 WELDS:

CylindricalShell Axial Welds Electroslag Welds ESW 23.1**

Girth Welds Shell 1 to Shell 2 WF 154 (SAW) 406L44, Lot 8720 20*

Notes: Minimum Charpy values are provided for all materials.

No Nil Ductility Transition (NDT) value is available on the CMTR; obtained from the purchase specification.

- Weld initial RTNDT values were obtained from previously-approved submittals.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table B-3: BFNP Unit 1 Initial RTNDT Values for RPV ADDurtenance and Boltin2 Materials Drop Test Temp Charpy Energy (Twr-60) Wegh RTNDT Component Heat (OF) (ft-lb) (OF) Weight (OF)

NDT (OF)

Miscellaneous Appurtenances:

Support Skit Segment (MK24) 24-139-1 through -4 C3888-5 10 38 40 41 4 40 40 Shroud Support (MK51, MK52. MK53) Alloy 600 Steam Dryer Support Bracket (MKI 31) Stainless Steel 131-127-1 through -4 00431 Core Spray Bracket (MK132) Stainless Steel 132-127-1 through-8 3342230 Dryer Hold Down Bracket (MK133) 133-127-1 through -4 EV-8446 40 38 42 37 36 40 40 Guide Rod Bracket (MK134) Stainless Steel 134-127-1 & -2 139506 Feedwater Sparger Brackets (MK 135) Stainless Steel 135-127-1 through -12 00431 Stabilizer Bracket (MK196) 10 60 59 56 -20 40 40 196-127-5 through -212 C6458-1 Surveillance Brackets (MIK199 & MK200) Stainless Steel 199-127-1 through -3 342633-2 200-127-1 through -3 342633-2 Lift Lugs (MK2 10) 210-122-1, -2, -3, & -6 AI210-3B 10 83 98 95 -20 40 40 CRD Penetrations (MKI 01 -MK128) Alloy 600 101 through 128 Refueling Containment Skirt (MK7 1) 71-127-1 through -4 B7478-4B 40*

Lateral Lowest Test Temp Charpy Energy Component Heat (°F) Expansion Service (ft-lb)

(mils) Temp (IF)

STUDS:

Closure (MK61) 6730502 10 34 52 68 N/A 70 NUTS:

Closure (MK62) 6730502 10 34 52 68 N/A 70 23514 10 49 53 63 29 10 6780382 10 45 42 46 N/A 70 6790156 N/A N/A N/A N/A N/A 70 BUSHINGS:

Closure (MK63) T3798 10 61 69 73 51 10 M2513 10 64 65 67 40 10 M2514 10 66 56 70 42 10 EV9474 10 67 64 62 N/A 70 AV3107 10 63 70 72 N/A 70 WASHERS:

Closure (MK64 and MK65) 6730502 10 34 52 68 N/A 70 6780278 N/A N/A N/A N/A N/A 70 Notes: Minimum Charpy values are provided for all materials.

No NDT value is available on the CMTR; obtained from the purchase specification.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table B-4: BFNP Unit 1 Adjusted Reference Temperatures for Up to 25 EFPY Lower-Intermediate Plates 2

Thickness in inches = 6.125 25 EFPY Peak I.D. fluence = 1.01 E+1 8n/cm 2

25 EFPY Peak 4 T fluence = 6.99E+17 n/cm Lower Plates & Lower to Lower-Intermediate Girth Weld 2

Thickness in inches = 6.125 25 EFPY Peak I.D. fluence = 8 14E+17 n/cm 2

25 EFPY Peak 1/4 T fluence = 5.64E+17 n/cm Axial Welds 2

Thickness in inches = 6.125 25 EFPY Peak I.D. fluence = 1.01E+I8 n/cm 2

25 EFPY Peak / T fluence = 6.99E+17 n/cm Water Level Instrumentation Nozzle 2

Thickness in inches = 6.125 25 EFPY Peak I.D. fluence = 3.04E+17 n/cm 25 EFPY Peak 1/4 T fluence = 2.11 E+1 7 n/cm 2 25 25 25 Initial 'A T EFPY EFPY EFPY Component omoetHeatlLot Heat or %Cu %Ni CF Au CF R°D RTteDT Fluence /T Gi Ga F a/4 OF T / T OF n/cm 2 ARTNDT Shift ART OF OF OF PLATES:

Lower Shell 6-127-1 A0999-1 0.14 0.60 100 -20 5.64E+17 31 0 16 31 62 42 6-127-2 B5864-1 0.15 0.44 101 -20 5.64E+17 32 0 16 32 63 43 6-127-4 A1009-1 0.14 0.50 96 -10 5.64E+17 30 0 15 30 60 50 Lower-Intermediate Shell 6-139-19 C2884-2 0.12 0.53 82 14 6.99E+17 28 0 14 28 57 71 6-139-20 C2868-2 0.09 0.48 58 30 6.99E+17 20 0 10 20 41 71 6-139-21 C2753-1 0.08 0.50 51 1 2 6.99E+17 18 0 9 18 36 38 WELDS:

Axial Welds Electroslag Weld (ESW) 0.24 0.37 141 23.1 6.99E+ 17 49 13 25 56 105 128 Lower to Lower-Intermediate Girth Weld WFI54 406L44 0.27 0.60 184 20 5.64E+ 17 57 10 28 59 117 137 31

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 25 25 25 Initial / T EFPY EFPY EFPY Component Heat/Lot Heat or %Cu %Ni CF CF Adjusted RTA RTNMT lec Fluence 1T T o F Margin 1/4T 'AT 2

OF n/cm ARTNDT Shift ART OF OF OF BEST ESTIMATE CHEMISTRIES:

None NOZZLES:

N 16 Water Level Instrumentation Forging Inconel I] (( )) 2.1 lE+17 ((

Weld Inconel INTEGRATED SURVEILLANCE PROGRAM:

Plate, 23"

6.99E+17 34 Weld" - _ 5.64E+17 Notes:

(I) ((

(2) The representative plate material is not the same heat number as the target plate; therefore the RG 1.99 R2 CF is used. This information is not applicable to development of the P-T curves and is provided for information only.

(3) 32

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table B-5: BFNP Unit 1 Adjusted Reference Temperatures for Up to 38 EFPY Lower-Intermediate Plates 2

Thickness in inches = 6.125 38 EFPY Peak I.D. fluence = I 58E+l 8 n/cm 2

38 EFPY Peak 1/4T fluence = 1.09E+18 n/cm Lower Plates & Lower to Lower-Intermediate Girth Weld 2

Thickness in inches = 6.125 38 EFPY Peak I.D. fluence = I 28E+18 n/cm 2

38 EFPY Peak 14 T fluence = 8.86E+17 n/cm Axial Welds 2

Thickness in inches = 6.125 38 EFPY Peak I.D. fluence = 1.58E+18 n/cm 2

38 EFPY Peak A T fluence = 1.09E+18 n/cm Water Level Instrumentation Nozzle 2

Thickness in inches = 6.125 38 EFPY Peak I.D. fluence = 4.77E+1 7 n/cm 2

38 EFPY Peak V,T fluence = 3.30E+17 n/cm 38 38 38 Initial '/4T EFPY EFPY EFPY Component omoetHeat/Lot Heat or %Cu %Ni CF A CFs RTNDT Fluence / T Gi Mr°F n %T A 1 T OF n/cm2 ARTNDT Shift ART OF OF OF PLATES:

Lower Shell 6-127-1 A0999-1 0.14 0.60 100 -20 8.86E+17 39 0 17 34 73 53 6-127-2 B5864-1 0.15 0.44 101 -20 8.86E+17 40 0 17 34 74 54 6-127-4 A1009-1 0.14 0.50 96 -10 8.86E+17 38 0 17 34 72 62 Lower-Intermediate Shell 6-139-19 C2884-2 0.12 0.53 82 14 1.09E+18 36 0 17 34 70 84 6-139-20 C2868-2 0.09 0.48 58 30 1.09E+18 25 0 13 25 50 80 6-139-21 C2753-1 0.08 0.50 51 2 1.09E+18 22 0 11 22 44 46 WELDS:

Axial Welds ESW 0.24 0.37 141 23.1 1.09E+ 18 61 13 28 62 123 146 Lower to Lower-Intermediate Girth Weld WFI54 406L44 0.27 0.60 184 20 8.86E+/-17 72 10 28 59 132 152 33

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public) 38 38 38 Adjusted Initial 1/4/4 T EFPY Margin EFPY EFPY Heat or ComponentHeat/Lot %Cu %Ni CF RTNDT Fluence 2 1/4T ol GA OF / T / T HF n/cm ARTNDT Shift ART OF OF OF BEST ESTIMATE CHEMISTRIES:

None NOZZLES:

N 16 Water Level Instrumentation Forging Inconel ... (( ] 3.03E+171] ((

Weld Inconel INTEGRATED SURVEILLANCE PROGRAM:

Plate"".11 1.09E+18 ((

Weld 3"4' 8.86E+17 Notes:

(1) ((

(2) The representative plate material is not the same heat number as the target plate; therefore the RG 1.99 R2 CF is used. This information is not applicable to development of the P-T curves and is provided for information only.

(3) [

))

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table B-6: BFNP Unit 1 RPV Beltline P-T Curve Input Values for 38 EFPY Adjusted RTNDT = Initial RTNDT + Shift A = 23.1 + 123 = 146.1OF (Based on ART values in Table B-5)

Vessel Height H = 875.13 inches Bottom of Active Fuel Height B = 216.3 inches Vessel Radius (to base metal) R = 125.7 inches Minimum Vessel Thickness (without clad) t = 6.125 inches Note: The ART for 25 EFPY is 1287F as shown in Table B-4.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Table B-7: BFNP Unit 1 Definition of RPV Beltline Regioni Elevation Component (inches from RPV "60")

Shell # 2 - Top of Active Fuel (TAF) 366.3 Shell # 1 - Bottom of Active Fuel (BAF) 216.3 Shell # 2 - Top of Extended Beltline Region (38 EFPY) 378.3 Shell # 1 - Bottom of Extended Beltline Region (38 EFPY) 206.4 Circumferential Weld Between Shell #1 and Shell #2 258.0 Circumferential Weld Between Shell #2 and Shell #3 391.5 Centerline of Recirculation Outlet Nozzle in Shell # 1 161.5 Top of Recirculation Outlet Nozzle N I in Shell # 1 188.0 Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0 Top of Recirculation Inlet Nozzle N2 in Shell # 1 193.3 Centerline of WLI Nozzle in Shell # 2 366.0 Bottom of WLI Nozzle in Shell # 2 364.6 Note:

(1) The beltline region is defined as any location where the peak neutron fluence is expected to exceed or equal 1.0e 17 n/cm 2 .

Based on the above, it is concluded that none of the BFNP Unit I reactor vessel plates, nozzles, or welds, other than those included in the ART table, are in the beltline region.

36

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Appendix C BFNP Unit 1 Reactor Pressure Vessel P-T Curve Checklist 37

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Table C-I provides a checklist that defines pertinent points of interest regarding the methods and information used in developing the BFNP Unit 1 PTLR. This table demonstrates that all important parameters have been addressed in accordance with the P-T curve LTR (Reference 6.2), and includes comments, resolutions, and clarifications as necessary.

Table C-i: BFNP Unit 1 Checklist Parameter Completed Comments/Resolutions/Clarifications Initial RTNDT Initial RTNDT has been determined for all The N 16 WLI nozzle is considered vessel materials including plates, flanges, within the beltline region. This forging forgings, studs, nuts, bolts, welds. was ((

Include explanation (including methods/sources) of any exceptions, are considered.

resolution of discrepant data (e.g., deviation from originally reported All other information remains values). unchanged from previous submittals.

Appendix B contains tables of all initial RTNDT values.

Has any non-plant-specific initial RTNDT Plate heat (( )) information information (e.g., ISP, comparison to other was obtained from the ISP database.

plant) been used? This material is ((

)) to the target vessel plate material and, in accordance with the ISP guidance; this data was ((

)) the limiting ART.

Weld heat (( )) information was obtained from the ISP database.

This material is (( ))

to the target vessel weld material and, in accordance with ISP guidance, this data was (( )) the limiting ART.

If deviation from the P-T curve LTR No deviations from the P-T curve LTR process occurred, sufficient supporting process were applied.

information has been included (e.g., Charpy V-Notch data used to determine an Initial RTNDT).

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

....

a.r ...........

- .. . . omlete*d* Cohmme s Ieslon l ns

~ 4 4 All previously published Initial RTNDT M RVID was reviewed for the beltline values from sources such as the Generic materials; all initial RTNDT values agree; Letter (GL) 88-0 1, Reactor Vessel Integrity no further review was performed.

Database (RVID), UFSAR, etc., have been reviewed.

Adjusted Reference Temperature Sigma I (ao, standard deviation for Initial Z Sigma I is equal to 0°F for all materials RTNDT) is 0°F unless the RTNDT was except the weld heats. The ESW obtained from a source other than CMTRs. material uses (aIof 13'F and the If c, is not equal to 0°F, reference/basis has Submerged Arc Weld (SAW) girth weld been provided, material uses a y, of 10'F, consistent with previous NRC submittals.

Sigma a (GA, standard deviation for ARTNDT) is determined per RG 1.99, Revision 2 Chemistry has been determined for all The N 16 WLI nozzle is ((

vessel beltline materials including plates, forgings (if applicable), and welds.

)) is Include explanation (including considered.

methods/sources) of any exceptions, resolution of discrepant data ISP data is obtained from BWRVIP-135, (e.g., deviation from originally reported Revision 2.

values).

No deviations from previously reported values.

Non-plant-specific chemistry information Z Plate heat (( )) has been (e.g., ISP, comparison to other plant) used evaluated using best estimate chemistry has been adequately defined and described. from the ISP.

For any deviation from the P-T curve LTR Z While not a deviation, it is noted that the process, sufficient information has been limiting ART for the beltline materials is included. that for a weld heat. As this material

)) to provide bounding P-T curves for the beltline region.

No deviations from the P-T curve LTR process.

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

All previously published chemistry values RVID was reviewed; all chemistry from sources such as the GL88-01, RVID, values agree; no further review was UFSAR, etc., have been reviewed. performed.

The fluence used for determination of ART and any extended beltline region was obtained using an NRC-approved methodology.

The fluence calculation provides an axial .

distribution to allow determination of the vessel elevations that experience fluence of 1.Oel 7 n/cm 2 both above and below active fuel.

The fluence calculation provides an axial distribution to allow determination of the fluence for intermediate locations such as the beltline girth weld (if applicable) or for any nozzles within the beltline region.

All materials within the elevation range where the vessel experiences a fluence

>1.0e17 n/cm 2 have been included in the ART calculation. All initial RTNDT and chemistry information is available or explained.

Discontinuities The discontinuity comparison has been There are no deviations.

performed as described in Section 4.3.2.1 of the P-T curve LTR. Any deviations have been explained.

Discontinuities requiring additional [ All discontinuities are bounded by either components (such as nozzles) to be the Upper Vessel, Bottom Head, or considered part of the beltline have been Beltline curve; those bounded by the adequately described. It is clear which Upper Vessel and/or Bottom Head are in curve is used to bound each discontinuity, accordance with Tables 4-4a and 4-5a of the LTR.

Appendix G of the P-T curve LTR The thickness discontinuity evaluation describes the process for considering a demonstrates that no additional thickness discontinuity, both beltline and adjustment is required; the curves bound non-beltline. If there is a discontinuity in the discontinuity stresses.

the vessel that requires such an evaluation, the evaluation was performed. The affected curve was adjusted to bound the discontinuity, if required. _

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

ýQX GO,i .t~ý a mb Appendix H of the P-T curve LTR defines the basis for the CRD Penetration curve discontinuity and the appropriate transient application. The plant-specific evaluation bounds the requirements of Appendix H.

Appendix J of the P-T curve LTR defines the basis for the WLI Nozzle curve discontinuity and the appropriate transient application. The plant-specific evaluation bounds the requirements of Appendix J.

41

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Appendix D Sample P-T Curve Calculations 42

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Beltline Water Level Instrumentation Nozzle Pressure Test (Curve A)

K, for the discontinuity is determined considering the K1 obtained from Table 7 of Appendix J (for hydrotest). For 1070 psig, this K1 is (( )) as follows:

KI ]J T-RTNDT is calculated in the following manner:

T-RTNDT ))

The ART is added to T-RTNDT to obtain the required T:

T I]

This temperature is not obvious from the P-T curve as it is bounded by the ((

Core Not Critical (Curve B)

Ki for the discontinuity is determined considering the K, obtained from Table 5 of Appendix J.

I]

The transient used for the WLI nozzle, defined in Appendix J, is used in determination of K1 .

The total K1 is therefore:

KI =

T-RTNDT is calculated in the following manner:

T-RTNDT = ((

The ART is added to T-RTNDT to obtain the required T:

T = [

This temperature is not obvious from the P-T curve as it is bounded by the ((

))

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NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Correction Factor The total stress for the WLI exceeds the yield stress; therefore, the correction factor, R, is calculated to consider the nonlinear effects in the plastic region according the following equation based on the assumptions and recommendation of Welding Research Council (WRC) Bulletin 175 as shown in Equation 4-7 of Reference 6.2.

3 R [ays - 'pm -+((Qltotai - (Yys)/ 0)]/(Gtotal - Gpm)

Applied to the WLI:

R -

))

44

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Beltline Calculations Excludin2 Water Level Instrumentation Nozzle Pressure Test (Curve A) at 1070 psig for 38 EFPY The limiting beltline material is the bounding !component for Curve A; therefore, a sample calculation for this material, not including the WLI nozzle is provided for 1070 psig.

The limiting ART applied to the beltline PT curves is (( )) for the ((

)), which is also in the (( )). However, the ((

)) as defined in ASME Appendix G.

When comparing the resultant required temperature to that for the axial ESW, it is seen that the axial weld will provide a more limiting curve. Therefore, the ART of 1467F is used in developing the beltline P-T curve.

Pressure is calculated to include hydrostatic pressure for a full vessel:

P 1070 psig + (H - B)*0.0361 psi/inch (H=vessel height; B=elevation of bottom of active fuel)

= 1070 + (875.13 - 216.3)

0.0361

= 1093.8 psig Pressure Stress:

o = PR/t (P=pressure; R=vessel radius; t=vessel thickness)

= 1.094

125.7 6.125

= 22.45 ksi Mm = 0.926'/t

= 0.9264i6.125

= 2.29 The stress intensity factor, Klt, is calculated as described in Section 4.3.2.2.4 of the LTR, except that "G" is 15SF/hr instead of 1.00 0F/hr.

Mt = 0.2914, from ASME Appendix G, Figure G-2214-1 AT = GC 2 /213 G = coolant heatup/cooldown rate of 15°F/hr C= minimum vessel thickness including clad = 6.125"+0.1875"=6.313"=0.526 ft P = thermal diffusivity at 550°F = 0.354 ft2 /hr

= (15*(0.526)2) / (2*0.354)

= 5.86OF 45

NEDO-33445 Revision 0 Non-Proprietary Information-Class I (Public)

Kit = Mt

AT

= 0.2914

5.86

- 1.71 Kim G

Mm

= 22.45

2.29

= 51.4 T-RTNDT = ln[(1.5*Kim + Kit - 33.2)/20.734]/0.02

= ln[(1.5*51.4 + 1.71 - 33.2)/20.734]/0.02

= 39.4 0 F T is calculated by adding the ART:

T = 39.4+146

= 185.4 0 F for P = 1070 psig at 38 EFPY This temperature represents the limiting point on Curve A and is cited as 185.6°F in Table 2.

Core Not Critical (Curve B) at 1070 psig for 38 EFPY The WLI nozzle is not the bounding component at any point in the pressure range; therefore, a sample calculation for the limiting beltline material, which bounds the WLI nozzle, is provided for 1070 psig.

As discussed above and in Section 5.0 and Table B-5, the limiting ART applied to the beltline Curve B is 146°F for the axial ESW.

The AT term is calculated as shown above for the Pressure Test case, but the temperature rate change is 100°F/hr instead of 15°F/hr. Therefore, AT equals 39°F.

P - 1070 psig + (H - B)*0.0361 psi/inch (H=vessel height; B=elevation of bottom of active fuel)

= 1070 + (875.13 -216.3)

0.0361

- 1093.8 psig Pressure Stress:

o = PR/t (P=pressure; R=vessel radius; t=vessel thickness)

= 1.094

125.7 / 6.125

= 22.45 ksi Kim = G*Mm

= 22.45

2.29

= 51.41 46

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Kit = Mt

AT (for the 100 0 F/hr case)

= 0.2914

39

= 11.36 T-RTNDT = ln[(2.0*K1 n + Kit - 33.2)/20.734]/0.02

= ln[(2.0*51.41 + 11.36 - 33.2)/20.734]/0.02

= 68.12OF T is calculated by adding the ART:

T = 68.1+146

= 214.1 0 F for P = 1070 psig at 38 EFPY This temperature represents the limiting point on Curve B and is cited in Table 2 as 214.3'F.

47

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Feedwater Nozzle Calculations An evaluation was performed for the FW nozzle as described in Section 4.3.2.1.3 of the LTR.

The first part of the evaluation is as described earlier, where it is assured that the limiting component that is represented by the upper vessel nozzle curve is bounded by the ((

)). A second evaluation was performed using the BFNP Unit 1-specific FW nozzle dimensions; this evaluation is shown below to demonstrate that the (( )) curve is applicable to BFNP Unit 1:

Vessel radius to base metal, R, Vessel thickness, t, Vessel pressure, Pv Pressure stress = PR/t =

Dead Weight + Thermal Restricted Free End stress Total Stress = (( 3] ))

The factor F (a/rn) from Figure A5-I of "PVRC Recommendations on Toughness Requirements for Ferritic Materials," WRC Bulletin 175, August 1972 (WRC-175) is determined where:

a -A (tn2 + tv2 ) '/2 tn= thickness of nozzle t, thickness of vessel rn= apparent radius of nozzle = ri + 0. 2 9 *rc ri= actual inner radius of nozzle rc= nozzle radius (nozzle comer radius) ))

Therefore, a/rn = (( )). The value F (a/rn), taken from Figure A5-I of WRC-175 for an (( )). Including the safety factor of 1.5, the stress intensity factor, K1 , is 1.5 7 (7ra) 1/2

F(a/rn):

BFNP Unit 1 Plant-Specific Nominal K, = 1.5 * (( 1]

A detailed upper vessel example calculation for core not critical conditions is provided in Section 4.3.2.1.4 of the LTR. Section 4.3.2.1.3 of the LTR presents the ((

)) for the FW nozzle evaluation upon which the baseline non-shifted upper vessel P-T curve is based. It can be seen that the nominal K, from this BFNP Unit 1 evaluation is E[ )). Therefore, it has been shown that the nominal K1 for the BFNP Unit 1-specific FW nozzle is less than the (( )) KI, demonstrating applicability of the FW nozzle curve for BFNP Unit 1.

48

ENCLOSURE 4 Enclosed are the affidavits supporting the request to withhold proprietary information (included in Enclosure 2) from the public.

GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Peter M. Yandow, state as follows:

(1) I am the Vice President, Nuclear Plant Projects/Services Licensing, Regulatory Affairs, of GE-Hitachi Nuclear Energy Americas LLC ("GEH"), and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in GEH proprietary report, NEDC-33445P, "Tennessee Valley Authority Browns Ferry Nuclear Plant Unit I Pressure and Temperature Limits Report (PTLR) Up to 25 and 38 Effective Full-Power Years," dated December 2013. The GEH proprietary information in NEDC-33445P is identified by a dotted underline inside double square brackets. ((This. sentence is an example...3 .)) In each case, the superscript notation 13ý refers to Paragraph (3) of this affidavit, which provides the basis for the proprietary determination.

(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 U.S.C. Sec. 552(b)(4), and the Trade Secrets Act, 18 U.S.C.

Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F.2d 871 (D.C. Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F.2d 1280 (D.C. Cir. 1983).

(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over other companies;

b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;

c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, resulting in potential products to GEH;

d. Information that discloses trade secret or potentially patentable subject matter for which it may be desirable to obtain patent protection.

(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GEH, Page 1 of 3

GE-Hitachi Nuclear Energy Americas LLC and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in the following paragraphs (6) and (7).

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited to a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary or confidentiality agreements.

(8) The information identified in paragraph (2), above, is classified as proprietary because it contains the detailed GEH methodology for pressure-temperature curve analysis for the GEH Boiling Water Reactor (BWR). These methods, techniques, and data along with their application to the design, modification, and analyses associated with the pressure-temperature curves were achieved at a significant cost to GEH.

The development of the evaluation processes along with the interpretation and application of the analytical results is derived from the extensive experience databases that constitute a major GEH asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

The research, development, engineering, analytical and NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial. GEH's competitive advantage will be lost if its Page 2 of 3

GE-Hitachi Nuclear Energy Americas LLC competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.

The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief.

Executed on this 6 th day of December 2013.

Peter M. Yandow Vice President, Nuclear Plant Projects/Services Licensing, Regulatory Affairs GE-Hitachi Nuclear Energy Americas LLC 3901 Castle Hayne Rd.

Wilmington, NC 28401 Peter.Yandow@ge.com Page 3 of 3

E l ELECTRIC POWER RESEARCH INSTITUTE 2013-2 15 BWR Vessel & Internals Project (BWRVIP)

December 9, 2013 Brian Eber Technical Services Lead Project Manager GE Hitachi Nuclear Energy 3901 Castle Hayne Road ATC2 Second Floor, Cube 4337 Wilmington, NC 28401 USA

Subject:

Transmittal of EPRI Proprietary Affidavit to the NRC The purpose of this letter is to transmit a proprietary affidavit for transmittal of the following document to the NRC:

"GE Hitachi Nuclear Energy, NEDC-33445P, Revision 0, December 2013, Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Pressure and Temperature Limits Report (PTLR) up to 25 and 38 Effective Full Power Years" If you have any questions on this subject, please contact Andrew McGehee by telephone at 704-502-6440 or by email at amcgeheeaepri.com.

Sincerely, Andrew McGehee EPRI, BWRVIP Program Manager c: Vic Schiavone, TVA Together ... Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillview Avenue, Polo Alto, CA 94304-1395 USA

650.855.2000

Customer Service 800.313.3774

www.epri.com

1 I ELECTRIC POWER RESEARCH INSTITUTE Christine King Director, Director, Nuclear Fuels &Chemistry Nuclear Power Sector December 6, 2014 Document Control Desk Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Request for Withholding of the Following Proprietary Information Included in:

GE Hitachi Nuclear Energy, NEDC-33445P, Revision 0, December 2013, Tennessee Valley Authority Browns Ferry Nuclear Plant Unit I Pressure and Temperature Limits Report (PTLR) up to 25 and 38 Effective Full Power Years To Whom It May Concern:

This is a request under 10 C.F.R. §2.390(a)(4) that the U.S. Nuclear Regulatory Commission ("NRC")

withhold from public disclosure the information identified in the enclosed Affidavit consisting of the proprietary information owned by Electric Power Research Institute, Inc. ("EPRr') identified in the attached report. Proprietary and non-proprietary versions of the Report and the Affidavit insupport of this request are enclosed.

EPRI desires to disclose the Proprietary Information inconfidence to assist the NRC review of the enclosed submittal by Tennessee Valley Authority for Browns Ferry Nuclear Plant Unit 1 PTLR. The Proprietary Information is not to be divulged to anyone outside of the NRC nor shall any copies be made of the Proprietary Information provided herein. EPRI welcomes any discussions and/or questions relating to the information enclosed.

Ifyou have any questions about the legal aspects of this request for withholding, please do not hesitate to contact me at (650) 855-2164. Questions on the content of the Report should be directed to Andy McGehee of EPRI at (704) 502-6440.

Sincerely, Attachment(s)

Together . . . Shaping the Future of Electricity PALO ALTO OFFICE 3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA

650.855.2000

Customer Service 800.313.3774

www.epri.com

E 3I 1ELECTRIC POWER RESEARCH INSTITUTE AFFIDAVIT RE: Request for Withholding of the Following Proprietary Information Included in:

GE Hitachi Nuclear Energy, NEDC-33445P, Revision 0, December 2013, Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Pressure and Temperature Limits Report (PTLR) up to 25 and 38 Effective Full Power Years I,Christine King, being duly sworn, depose and state as follows:

I am the Director, Nuclear Fuels &Chemistry at Electric Power Research Institute, Inc. whose principal office is located at 3420 Hillview Avenue, Palo Alto, California ("EPRI") and I have been specifically delegated responsibility for the above-listed report that contains EPRI Proprietary Information that is sought under this Affidavit to be withheld ("Proprietary Information"). I am authorized to apply to the U.S. Nuclear Regulatory Commission ("NRC") for the withholding of the Proprietary Information on behalf of EPRI.

EPRI Information is identified by a solid underline inside double square brackets. ((This sentence is an example. ]{E} Tables containing EPRI proprietary information are identified with double square brackets before and after the object. In each case the superscript notation {E} refers to this affidavit as the bases for the proprietary determination.

EPRI requests that the Proprietary Information be withheld from the public on the following bases:

Withholding Based Upon Privileged And Confidential Trade Secrets Or Commercial Or Financial Information (see e.,g. 10 C.F.R. §2.390(a)(4):

a. The Proprietary Information is owned by EPRI and has been held in confidence by EPRI. All entities accepting copies of the Proprietary Information do so subject to written agreements imposing an obligation upon the recipient to maintain the confidentiality of the Proprietary Information. The Proprietary Information isdisclosed only to parties who agree, inwriting, to preserve the confidentiality thereof.

b. EPRI considers the Proprietary Information contained therein to consitiute trade secrets of EPRI. As such, EPRI holds the Information in confidence and disclosure thereof is strictly limited to individuals and entities who have agreed, inwriting, to maintain the confidentiality of the Information.

c. The information sought to be withheld is considered to be proprietary for the following reasons. EPRI made a substantial economic investment to develop the Proprietary Information and, by prohibiting public disclosure, EPRI derives an economic benefit in the form of licensing royalties and other additional fees from the confidential nature of the Proprietary Information. Ifthe Proprietary Information were publicly available to consultants and/or other businesses providing services inthe electric and/or nuclear power industry, they would be able to use the Proprietary Information for their own commercial benefit and profit and without expending the substantial economic resources required of EPRI to develop the Proprietary Information.

d. EPRI's classification of the Proprietary Information as trade secrets is justified by the Uniform Trade Secrets Act which California adopted in 1984 and a version of which has been adopted by over

40 states. The California Uniform Trade Secrets Act, California Civil Code §§3426 - 3426.11, defines a "trade secret" as follows:

"Trade Secret" means information, including a formula, pattern, compilation, program device, method, technique, or process, that:

(1)Derives independent economic value, actual or potential, from not being generally known to the pubic or to other persons who can obtain economic value from its disclosure or use; and (2) is the subject of efforts that are reasonable under the circumstances to maintain its secrecy."

e. The Proprietary Information contained therein are not generally known or available to the public. EPRI developed the Information only after making a determination that the Proprietary Information was not available from public sources. EPRI made a substantial investment of both money and employee hours in the development of the Proprietary Information. EPRI was required to devote these resources and effort to derive the Proprietary Information. As a result of such effort and cost, both in terms of dollars spent and dedicated employee time, the Proprietary Information is highly valuable to EPRI.

f. A public disclosure of the Proprietary Information would be highly likely to cause substantial harm to EPRI's competitive position and the ability of EPRI to [icense the Proprietary Information both domestically and internationally. The Proprietary Information can only be acquired and/or duplicated by others using an equivalent investment of time and effort.

I have read the foregoing and the matters stated herein are true and correct to the best of my knowledge, information and belief. I make this affidavit under penalty of perjury under the laws of the United States of America and under the laws of the State of California.

Executed at 3420 Hillview Avenue, Palo Alto, California being the premises and place of business of Electric Power Research Institute, Inc.

Date: (2 Uý I

CJrhrtina Winn VIIII LI I/ I lli (State of California)

(County of Santa Clara)

Subscd ed and sworp 4 (or affirmed) before me on this 64bay of 6 V &., . 20.A3 by proved to me on the basis of satisfactory evidence to be the person(s) whgoo;tpeared f.fore m.) /

Signature i. 76I',0*/*

/ - (Seal) .,'* '.:

My Commiession Expires ý> day_ .. f. _ 2__, . =:: ii. =,

it BERTE A.DAHL Cou.PUB.-CFU"'A

1926383

.NOTAR SANTA CLARACO.

1MY CONl. EDp. 20, 2015j MAR.

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