ML13311A054

Pressure and Temperature Limits Report (PTLR) PTLR-2, Revision 0 (Draft B)

ML13311A054
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Site:	Nine Mile Point
Issue date:	11/04/2013
From:	Inch G Constellation Energy Nuclear Group, Nine Mile Point
To:	Office of Nuclear Reactor Regulation
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ATTACHMENT 2 NINE MILE POINT UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) -

REVISION 0 (DRAFT B)

Nine Mile Point Nuclear Station, LLC November 4, 2013

CENGSM a joint venture of OEnerWy Constellation neg"'eDF 10DF NINE MILE POINT NUCLEAR STATION Nine Mile Point Nuclear Station Nine Mile Point Unit 2 Pressure and Temperature Limits Report (PTLR)

PTLR-2, Revision 0 (Draft B)

Prepared by: Date:

G. B. Inch Mechanical Design Engineering Reviewed by: Date:

S. K. Dhar Mechanical Design Engineering Approved by: Date:

P. E. Bartolini, Supervisor Mechanical-Structural Design Engineering Approved by: Date:

M. N. Khan, General Supervisor Design Engineering This Controlled Document provides reactor pressure vessel pressure and temperature limits for use in conjunction with the Nine Mile Point Unit 2 Technical Specifications. Document pages may only be changed through the re-issue of a revision to the entire document.

NMP2 Pressure and Temperature Limits Report Table of Contents Section Page 1.0 Purpose 1 2.0 Applicability 1 3.0 Methodology 1 4.0 Operating Limits 2 5.0 Discussion 3 6.0 References 6 Figure 1 Bottom Head and Composite P-T Curves for Pressure 7 Test [Curve A] for up to 32 EFPY Figure 2 Bottom Head and Composite P-T Curves for Core Not 8 Critical [Curve B] for up to 32 EFPY Figure 3 Composite P-T Curves for Core Critical [Curve C] for up 9 to 32 EFPY Table 1 Data Table for Composite P-T Curve for 32 EFPY 10 Appendix A Reactor Vessel Material Surveillance Program 15 Appendix B Supporting Information 16 Appendix C Checklist 25 i PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report 1.0 Purpose The purpose of the Nine Mile Point Nuclear Station Unit 2 (NMP2) 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 1 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 of Technical Specification (TS) 5.6.7, "Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)."

2.0 Applicability This report is applicable to the NMP2 RPV for up to the 32 Effective Full Power Years (EFPY).

The following TS are affected by the information contained in this report:

TS 3.4.11 RCS Pressure and Temperature (P/T) Limits; 3.0 Methodology The limits in this report were derived from the NRC-approved methods listed in TS 5.6.7, using the specific revisions listed below:

1. The appendix B Adjusted Reference Temperature (ART) is defined based on conservative extrapolation for up to 32 EFPY. The Neutron fluence used for the ART was verified conservative per the NMP2 plant specific Reg. Guide 1.190 methods documented in Reference 6.2, approved in reference 6.3. and 6.10.

2. The pressure and temperature limits were calculated per GEH P-T Curve Licensing Topical Report, NEDC-33178P-A, Revision 1, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Page 1 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Curves," Report for BWR Owners' Group, Sunol, California, (GEH Proprietary),

June 2009, approved in Reference 6.5.

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

Changes to the curves, limits, or parameters within this PTLR, based upon new irradiation fluence data of the Reactor Pressure Vessel (RPV), or other plant design assumptions in the Updated Final Safety Analysis Report (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, in accordance with TS Section 5.6.7.

Changes to the curves, limits, or parameters within this PTLR, based upon new surveillance capsule data of the RPV, cannot be made without prior NRC approval.

Such analysis and revisions shall be submitted to the NRC for review prior to incorporation into the PTLR. Since NMP2 surveillance capsule program is the ISP program, new surveillance data through the Integrated Surveillance Program (ISP) does not represent new data that requires NRC review prior to incorporation into the PTLR.

4.0 Operating Limits The pressure-temperature (P-T) curves included 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.

Complete P-T curves were developed for the estimated fluence based on 32 EFPY assuming 3988 MWth rating. A tabulation of the P-T curves is also included in Table 1.

The previous evaluation for Pressure-Temperature limits for up to 22 EFPY is contained in Reference 6.6.

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.

Heatup and Cooldown rate limit during Hydrostatic and Class 1 Leak Testing (Figure 1):

Curve A): < 20 OF/hour.

Page 2 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Normal Operating Heatup and Cooldown rate limit (Figures 2 and 3): Curve B - Non-Nuclear Heating and Curve C - Nuclear Heating): < 100 °F/hour.

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

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

RPV flange and adjacent shell temperature limit: _> 70 OF.

5.0 Discussion No new computer codes have been used in the development of Pressure-Temperature curves.

The method for determining the initial RTNDT for all vessel materials is that defined in Section 4.1.2 of NEDC-33178P-A, Revision 1, approved for use in Reference 6.5. Initial RTNDT values for all vessel materials considered are presented in tables in this PTLR.

Surveillance capsule material data to represent the NMP2 vessel is available from the Integrated Surveillance Program (ISP). Since NMP2 is not a host plant in the ISP program, the ISP program representative materials are evaluated to confirm applicability of RG 1.99 position 1.1. The ISP data review is shown in Appendix B. The NMP2 representative plate is not the same as the target plate material and is therefore provided for information only and is not considered in development of the PT curves.

The NMP2 representative weld is not the same as the target weld material. However, as the same heat is used in beltline axial welds, the ISP weld material is considered in the development of the PT curves. This material is not the limiting material with respect to the PT curves; the NMP2 plant-specific plate heat C3147-1, has the limiting ART.

For NMP2, there are three thickness discontinuities in the vessel. One discontinuity is between the bottom head torus and dollar plate. One discontinuity is between the bottom head torus and Shell #1. One discontinuity is between the transition in the upper Shell (Shell #3 to Shell #4). The thickness discontinuities do not cause a change in the RTNDT.

The adjusted reference temperature (ART) of the limiting beltline material is used to adjust the beltline P-T curves to account for irradiation effects. Regulatory Guide 1.99, Revision 2 (RG 1.99) provides the methods for determining the ART. The RG 1.99 Page 3 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report methods for determining the limiting material and adjusting the P-T curves using ART are discussed in this section.

The vessel beltline copper and nickel values (except for the N6 and N12 nozzles) were obtained from Reference 6.6 PT curve limits report. Chemistries for the surveillance materials evaluated in Appendix B of this report were obtained from the ISP. The LPCI (N6) Nozzle and the Water Level Instrumentation (N12) Nozzle are now included in the extended beltline region. For the N6 nozzle forging, CMTR's were located which contained Cu (0.07%) and Ni (0.86%) values. For the N6 nozzle welds, CMTRs were located that contained Cu and Ni values as shown in the ART table.

For the Water Level Instrumentation (N12) Nozzle, the CMTR's do not contain the Cu and Ni content. Since plant-specific information regarding the Cu and Ni content for this material is not available, the evaluation was performed based on a bounding estimate for forgings fabricated from SA508 Class 1 material. This was defined based on a search of available BWR vessel purchase records for SA508 Class 1 materials. Representative values for Cu and Ni content were developed using Mean + 1 sigma.

The P-T curves for the non-beltline region were conservatively developed for a Boiling-Water Reactor Product Line 6 (BWR/6) with nominal inside diameter of 251 inches. The analysis is considered appropriate for NMP2, since the plant specific geometric values are bounded by the generic analysis for a large BWRJ6. The generic value was adapted to the conditions at NMP2 using plant-specific RTNDT values for the reactor pressure vessel. The value of R/t11 2 for NMP2 = 126.6875 / (7.19)1/2 = 47.3 inch11 2 .

The peak RPV ID fluence used in the P-T curve evaluation for 32 EFPY is calculated using methods that comply with the guidelines of RG 1.190, (References 6.2, 6.3 and 6.4). Appendix B lists the peak fluence levels used for the PT curves.

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 1/4T 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, Kir, at 1/4T to be less than that at 3/4T for a given metal temperature. This approach causes no Page 4 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report operational difficulties, since the BWR is at steam saturation conditions during normal operation, well above the heatup/cooldown curve limits.

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 _<1OO0 F/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 _<20°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.

For NMP2, the plate heat C3147-1 is the limiting material for the beltline region. Peak fluence values used in the development of the Pressure-Temperature curves are identified in Appendix B. The limiting ART for the beltline LPCI N6 and Water Level Instrumentation N12 nozzle forgings and welds are also considered in the development of the beltline PT curves.

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 NEDC-33178P-A, Revision 1, approved for use in Reference 6.5, for the non-beltline and beltline regions, respectively, are applied.

Page 5 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report 6.0 References 6.1 GEH Report NEDC-33414P, Revision 1, "Pressure-Temperature Curves for Constellation Generation Group Nine Mile Point Nuclear Station Unit 2", October 2012 6.2 Benchmarking of Nine Mile Point Unit 1 and Unit 2 Neutron Transport Calculations, MPM-402781 Revision 1, September 2003.

6.3 NRC Letter to NMPNS dated October 27, 2003, "Nine Mile Point Nuclear Station, Unit No. 1 - Issuance of Amendment Re: Pressure-Temperature Limit Curves and Tables (TAC No. MB6687)."

6.4 Fluence Extrapolation in Support of NMP2 P-T Curve Update, MPM-913991, September, 2013 6.5 Letter from T. R. Bount, USNRC to D. 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 6.6 Pressure-Temperature Operating Curves for Nine Mile Point Unit 2, MPM-502840, dated July 2003.

6.7 "BWRVIP-135, Revision 2: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations", 1020231, EPRI, Palo Alto, CA, October 2009 (EPRI Proprietary Information) 6.8 Letter from P. S. Tam (NRC) to J. A. Spina (NMPNS), dated November 8, 2004, "Nine Mile Point Nuclear Station Unit Nos. 1 and 2 - Issuance of Amendments Re:

Implementation of the Reactor Pressure Vessel Integrated Surveillance Program (TAC Nos. MC1758 and MC1759)"

6.9 Nine Mile Point Unit 2 3-Degree Surveillance Capsule Report, MPM-1200676, December, 2000.

6.10 NRC Letter to NMPNS dated November 8, 2004 - Issuance of Amendments RE:

Implementation of the Reactor Pressure Vessel Integrated Surveillance Program (TAC Nos. MC1 758 and MC1759)

Page 6 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Figure 1 - Bottom Head and Composite P-T Curves for Pressure Test [Curve A] for up to 32 EFPY 1400 1300 INITIAL RTndt VALUES ARE 0°F FOR BELTLINE, 1200 5°F FOR UPPER VESSEL, AND 1100 10°F FOR BOTTOM HEAD

,a 1000 Z~

BELTLINE CURVES 900 ADJUSTED AS SHOWN:

0 EFPY SHIFT (°F) 32 51 800 U) 0)

700 0 HEATUP/COOLDOWN I- RATE OF COOLANT w 600 < 2 0 °F/HR Z

500 w

400 LU 300 200 100 0

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

Page 7 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Figure 2 - Bottom Head and Composite P-T Curves for Core Not Critical [Curve B]

for up to 32 EFPY 1400 1300 1200 1100 0,

.1000

• 900 0~

I-w 800 U)

U)

W 700 0

I--

HEATUPICOOLDOWN RATE OF COOLANT "W 600 z < 100°F/HR I-a 500

c( 400 3

oU) 300 200 -UPPER VESSEL AND BELTLINE LIMITS 100 0

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

Page 8 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Figure 3 - Composite P-T Curves for Core Critical [Curve C] for up to 32 EFPY 1400 INITIAL RTndt VALUES 1300 ARE 0°F FOR BELTLINE, 5°F FOR UPPER VESSEL, 1200 AND 24.6°F FOR BOTTOM HEAD 1100 1000 BELTLINE CURVE ADJUSTED AS SHOWN:

0cn EFPY SHIFT (-F) 900 32 51 "I-U.1 800 w

HEATUP/COOLDOWN 0_.1 RATE OF COOLANT I-J C-)

Z 700 < 100°F/HR L.

600 I-w C,, 500 uJ, nw 0Z 400 300 200

-BELTLINE AND NON-100 BELTLINE LIMITS Minimum Criticality Temperature 70'F 0

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

Page 9 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Table 1 - NMP2 Tabulation of Composite P-T Curves for 32 EFPY -

Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A for Figures 1, 2 & 3 BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE HEAD BELTLINE LIMITING PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C

(°F)

(PSIG) (°F) ('F) (*F) (*F) 0 68.0 70.0 68.0 70.0 70.0 10 68.0 70.0 68.0 70.0 70.0 20 68.0 70.0 68.0 70.0 70.0 30 68.0 70.0 68.0 70.0 70.0 40 68.0 70.0 68.0 70.0 70.0 5o 68.0 70.0 68.0 70.0 70.0 60 68.0 70.0 68.0 70.0 70.0 70 68.0 70.0 68.0 70.0 70.0 80 68.0 70.0 68.0 70.0 70.0 90 68.0 70.0 68.0 70.0 70.0 100 68.0 70.0 68.0 70.0 70.0 110 68.0 70.0 68.0 70.0 71.9 120 68.0 70.0 68.0 70.0 75.7 130 68.0 70.0 68.0 70.0 79.2 140 68.0 70.0 68.0 70.0 82.4 1SO 68.0 70.0 68.0 70.0 85.2 160 68.0 70.0 68.0 70.0 87.9 170 68.0 70.0 68.0 70.0 90.5 180 68.0 70.0 68.0 70.0 92.9 190 68.0 70.0 68.0 70.0 95.2 200 68.0 70.0 68.0 70.0 97.3 210 68.0 70.0 68.0 70.0 99.3 220 68.0 70.0 68.0 70.0 101.3 230 68.0 70.0 68.0 70.0 103.1 240 68.0 70.0 68.0 70.0 104.9 25O 68.0 70.0 68.0 70.0 106.6 260 68.0 70.0 68.0 70.0 108.2 270 68.0 70.0 68.0 70.0 109.8 280 68.0 70.0 68.0 71.3 111.3 290 68.0 70.0 68.0 72.8 112.8 Page 10 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Table 1 - NMP2 Tabulation of Composite P-T Curves for 32 EFPY -

Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A for Figures 1, 2 & 3 BO'TOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE HEAD BELTILINE LIMITING PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (°F) (*F) (°F) (°F) (°F) 300 68.0 70.0 68.0 74.2 114.2 310 68.0 70.0 68.0 75.5 115.5 312.5 68.0 70.0 68.0 75.9 115.9 312.5 68.0 100.0 68.0 130.0 170.0 320 68.0 100.0 68.0 130.0 170.0 330 68.0 100.0 68.0 130.0 170.0 340 68.0 100.0 68.0 130.0 170.0 350 68.0 100.0 68.0 130.0 170.0 360 68.0 100.0 68.0 130.0 170.0 370 68.0 100.0 68.0 130.0 170.0 380 68.0 100.0 68.0 130.0 170.0 390 68.0 100.0 68.0 130.0 170.0 400 68.0 100.0 68.0 130.0 170.0 410 68.0 100.0 68.0 130.0 170.0 420 68.0 100.0 68.0 130.0 170.0 430 68.0 100.0 68.0 130.0 170.0 440 68.0 100.0 68.0 130.0 170.0 450 68.0 100.0 68.0 130.0 170.0 460 68.0 100.0 68.0 130.0 170.0 470 68.0 100.0 68.0 130.0 170.0 480 68.0 100.0 68.0 130.0 170.0 490 68.0 100.0 68.0 130.0 170.0 500 68.0 100.0 68.0 130.0 170.0 510 68.0 100.0 68.0 130.0 170.0 520 68.0 100.0 68.0 130.0 170.0 530 68.0 100.0 68.0 130.0 170.0 540 68.0 100.0 68.0 130.0 170.0 550 68.0 100.0 68.0 130.0 170.0 560 68.0 100.0 68.0 130.0 170.0.

570 68.0 100.0 68.0 130.0 170.0 Page 11 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Table 1 - NMP2 Tabulation of Composite P-T Curves for 32 EFPY -

Required Metal Temperature with Required Coolant Temperature Rate at 100 *F/hr for Curves B & C and 20 °F/hr for Curve A for Figures 1, 2 & 3 BOTTOM UPPER RPV & BOlTOM UPPER RPV &

HEAD BELTLINE HEAD BELTLINE LIMITING PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) ('F) (*F) (°F) ('F) ('F) 580 68.0 100.0 68.0 130.0 170.0 590 68.0 100.0 68.0 130.0 170.0 600 68.0 100.0 68.0 130.0 170.0 610 68.0 100.0 68.0 130.0 170.0 620 68.0 100.0 68.0 130.0 170.0 630 68.0 100.0 68.0 130.0 170.0 640 68.0 100.0 68.0 130.0 170.0 650 68.0 100.0 68.0 130.0 170.0 660 68.0 100.0 68.0 130.0 170.0 670 68.0 100.0 68.0 130.0 170.0 680 68.0 100.0 68.7 130.0 170.0 690 68.0 100.0 69.9 130.0 170.0 700 68.0 100.0 71.0 130.0 170.0 710 68.0 100.0 72.2 130.0 170.0 720 68.0 100.0 73.3 130.0 170.0 730 68.0 100.0 74.4 130.0 170.0 740 68.0 100.0 75.5 130.0 170.0 750 68.0 100.0 76.6 130.0 170.0 760 68.0 100.0 77.6 130.0 170.0 770 68.0 100.0 78.6 130.0 170.0 780 68.0 100.0 79.6 130.0 170.0 790 68.0 100.0 80.6 130.0 170.0 800 68.0 100.0 81.5 130.0 170.0 810 68.0 100.0 82.5 130.0 170.0 820 68.0 100.0 83.4 130.0 170.0 830 68.0 100.0 84.3 130.0 170.0 840 68.0 100.0 85.2 130.0 170.0 850 68.0 100.0 86.0 130.0 170.0 860 68.0 100.0 86.9 130.0 170.0 870 68.0 100.0 87.7 130.0 170.0 Page 12 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Table 1 - NMP2 Tabulation of Composite P-T Curves for 32 EFPY -

Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A for Figures 1, 2 & 3 BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE HEAD BELTILINE LIMITING PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (7F) (°F) (*F) (°F) (°F) 880 68.0 100.0 88.6 130.0 170.0 890 68.0 100.0 89.4 130.0 170.0 900 68.0 100.0 90.2 130.0 170.0 910 68.0 100.0 91.0 130.0 170.0 920 68.0 100.0 91.7 130.0 170.0 930 68.0 100.0 92.5 130.0 170.0 940 68.0 100.0 93.3 130.0 170.0 950 68.0 100.0 94.0 130.0 170.0 960 68.0 100.0 94.7 130.0 170.0 970 68.0 100.0 95.5 130.0 170.0 980 68.0 100.0 96.2 130.0 170.0 990 68.0 100.0 96.9 130.0 170.0 1000 68.0 100.0 97.6 130.0 170.0 1010 68.0 100.0 98.2 130.0 170.0 1020 68.0 100.0 98.9 130.0 170.0 1030 68.0 100.0 99.6 130.0 170.0 1035 68.0 100.0 99.9 130.0 170.0 1040 68.0 100.0 100.2 130.0 170.0 1050 68.0 100.0 100.9 130.0 170.0 1055 68.0 100.0 101.2 130.0 170.0 1060 68.0 100.0 101.5 130.0 170.0 1070 68.0 100.0 102.1 130.0 170.0 1080 68.0 100.0 102.8 130.0 170.0 1090 68.6 100.0 103.4 130.0 170.0 1100 69.2 100.0 104.0 130.0 170.0 1105 69.6 100.0 104.3 130.0 170.0 1110 69.9 100.0 104.6 130.0 170.0 1120 70.6 100.0 105.2 130.0 170.0 1130 71.2 100.0 105.8 130.0 170.0 1140 71.9 100.0 106.3 130.0 170.0 Page 13 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Table 1 - NMP2 Tabulation of Composite P-T Curves for 32 EFPY -

Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A for Figures 1, 2 & 3 BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE HEAD BELTLINE LIMITING PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (*F) (*F) (*F) ('F) (*F) 1150 72.5 100.0 106.9 130.0 170.0 1160 73.1 100.0 107.5 130.0 170.0 1170 73.8 100.0 108.0 130.0 170.0 1180 74.4 100.0 108.6 130.0 170.0 1190 75.0 100.0 109.1 130.0 170.0 1200 75.6 100.4 109.7 130.0 170.0 1210 76.2 101.0 110.2 130.0 170.0 1220 76.8 101.7 110.8 130.0 170.0 1230 77.3 102.3 111.3 130.0 170.0 1240 77.9 102.9 111.8 130.0 170.0 1250 78.5 103.5 112.3 130.0 170.0 1260 79.0 104.1 112.8 130.3 170.3 1270 79.6 104.7 113.3 130.6 170.6 1280 80.1 105.2 113.8 130.8 170.8 1290 80.7 105.8 114.3 131.1 171.1 1300 81.2 106.4 114.8 131.4 171.4 1310 81.7 106.9 115.3 131.8 171.8 1320 82.3 107.5 115.8 132.2 172.2 1330 82.8 108.0 116.2 132.7 172.7 1340 83.3 108.6 116.7 133.1 173.1 1350 83.8 109.1 117.2 133.5 173.5 1360 84.3 109.7 117.6 134.0 174.0 1370 84.8 110.2 118.1 134.4 174.4 1380 85.3 110.7 118.5 134.8 174.8 1390 85.8 111.2 119.0 135.2 175.2 1400 86.3 111.7 119.4 135.7 175.7 Page 14 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix A Reactor Vessel Material Surveillance Program In accordance with 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, the first surveillance capsule was removed from the NMP2 reactor vessel after Cycle 7, in March 2000, and tested. The surveillance capsule contained flux wires for neutron fluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel materials within the core beltline region.

The methods and results are presented in Reference 6.9, as required by 10 CFR 50, Appendices G and H.

As described in the NMP2 Updated Safety Analysis Report (USAR) Section 5.3.1.6, Material Surveillance, the BWRVIP Integrated Surveillance Program (ISP) will determine the removal schedule for the remaining two (2) NMP2 surveillance capsules. Per the BWRVIP ISP, NMP2 is not a host plant; all remaining surveillance capsules are classified as "Standby." The NMP2 material surveillance program is administered in accordance with the BWRVIP ISP. The ISP combines the 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 Supplemental Surveillance Program (SSP).

NMP2 maintains a Reg. Guide 1.190 fluence monitoring program and reviews the actual fluence on a routine basis, as discussed in USAR Section 4.1.4.5 and Appendix C, Section C.2.1.2.

Page 15 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information Figure of NMP2 Reactor Pressure Vessel TOP HEAD TOP HEAD FLANGE SHELL FLANGE

- SHELL #4

- SHELL #3 LPCI NOZZLE SHELL #2 TOP OF ACTIVE FUEL (TAF)366.31'"

iter Level trumentation Nozzle BOTTOM OF SHELL #1 ACTIVE FUEL (BAF)21 6.31'"

Page 16 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Initial RTNDT Values for RPV Materials Plate and Flange Materials Drop Test Component Heat or Heat I Flux I Lot Temp Charpy Energy'" (TO-r-60) Weight RTNDT

(*F) (ft-lb) (*F) NDT ('F)

(*F)

Top Head & Flange Shell Flange Mark 27-1 48D 1072-1-1 /48B1121-1-1 40 67 131 110 10 -20 10 Top Head Flange Mark 32-1 49B 168-1-1 /49D 161-1-1 30 94 98 77 0 -30 0 Top Head Dollar Mark 36-2 A0678-1 40 53 62 53 -20 -20 -20 Top Head Torus Plates Marks 36-1-1 36-1-2, 36-1-3 C2325-2 60 55 55 52 0 -20 0 Marks 36-1-4. 36-1-5, 36-1-6 C2480-2 30 62 50 66 -30 -40 -30 Shell Courses Upper Shell Plates Mark 24-1-1 C3193-1 60 59 56 58 0 -10 0 Mark 24-1-2 C3192-2 70 61 54 63 10 -10 10 Mark 24-1-3 C3192-1 70 58 51 72 10 -10 10 Upper Intermediate Plates Mark 23-1-1 C3121-1 70 52 50 50 10 -20 10 Mark 23-1-2 C3138-1 50 56 56 50 -10 -50 -10 Mark 23-1-3 B6991-1 20 70 64 56 -40 -40 -40 Lower-Intermediate Plates Mark 22-1-1 C3065-1 50 70 50 50 -10 -30 -10 Mark 22-1-2 C3121-2 60 50 53 50 0 -30 0 Mark 22-1-3 C3147-1 60 50 50 52 0 -20 0 Lower Shell Plates Mark 21-1-1 C3147-2 60 52 50 50 0 -20 0 Mark 21-1-2 C3066-2 40 55 52 51 -20 -30 -20 Mark 21-1-3 C3065-2 70 51 53 51 10 -10 10 Bottom Head Bottom Head Dollar Mark 13-1 B6803-2 50 55 58 52 -10 -10 -10 Mark 13-2 C2944-2 40 62 58 60 -20 -20 -20 Mark 13-3 B6803-1 70 68 56 54 10 -30 10 Bottom Head Torus Plates Marks 13-4, 13-5, 13-6 C3073-1 60 51 54 53 0 -20 0 Marks 13-7, 13-8, 13-9 C3073-2 70 51 57 55 10 -10 10 Skirt Knuckle Mark 9-1-1, 9-1-2, 9-1-3, 9-1-4 C3957-3 30 55 54 60 -30 -20 -20 (1) Minimum Charpy values are used in these calculations.

Page 17 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Initial RTNDT Values for RPV Materials, Continued Nozzle Materials Test Drop Component Heat or Heat / Flux/.Lot Temp Charpy Energy[U (T 50 T-60) Weight RTNDT (CF) (ft-lb) (*F) NDT (°F)

(*F)

N1 Recirculation Outlet Nozzle Mark 49-1-1 Q2QL1W/63A-1 40 102 109 91 -20 -20 -20 Mark 49-1-2 Q2QLlW/63A-2 40 95 106 82 -20 -20 -20 N2 Recirculation Inlet Nozzle Mark 52-1-1 Q2QL2W I 62A-1 30 93 97 94 -30 -20 -20 Mark 52-1-2 Q2Q67W / 62A-2 40 95 103 105 -20 -20 -20 Mark 52-1-3 Q2Q67W / 62A-3 40 82 81 101 -20 -20 -20 Mark 52-1-4 02Q67W / 62A-4 40 67 64 77 -20 -20 -20 Mark 52-1-5 Q2Q67W / 62A-5 40 62 67 109 -20 -20 -20 Mark 52-1-6 Q2QL2W / 62A-6 40 102 102 109 -20 -20 -20 Mark 52-1-7 Q2QL2W / 62A-7 40 79 83 87 -20 -20 -20 Mark 52-1-8 Q2Q65W / 62A-8 40 105 120 128 -20 -20 -20 Mark 52-1-9 Q2Q65W / 62A-9 40 105 103 124 -20 -20 -20 Mark 52-1-10 Q2QL2W / 62A-10 40 94 90 66 -20 -20 -20 N3 Steam Outlet Nozzle Mark 56-1-1 Q2Q68W / 1828-1 40 78 99 52 -20 -20 -20 Mark 56-1-2 Q2Q68W / 182B-2 40 76 87 75 -20 -20 -20 Mark 56-1-3 Q2Q68W / 182B-3 40 69 107 97 -20 -20 -20 Mark 56-1-4 Q2Q68W / 182B-4 40 121 120 116 -20 -20 -20 N4 Feedwater Nozzle Mark 59-1-1 Q2QL2W / 315A-1 40 103 103 87 -20 -20 -20 Mark 59-1-2 Q2QL2W / 315A-2 30 77 96 100 -30 -20 -20 Mark 59-1-3 Q2QL2W / 315A-3 30 77 56 54 -30 -20 -20 Mark 59-1-4 Q2QL2W / 315A-4 30 114 101 92 -30 -20 -20 Mark 59-1-5 Q2QL2W / 315A-5 40 95 72 116 -20 -20 -20 Mark 59-1-6 Q2QL2W / 315A-6 40 101 79 73 -20 -20 -20 N5 Core Spray Nozzle (Low Pressure)

Mark 63-1-1 Q2QL3W / 867B-1 20 82 81 66 -40 -20 -20 N6 RHR-LPCI Nozzle Mark 67-1-1 Q2QL3W / 854A-1 40 53 101 84 -20 -20 -20 Mark 67-1-2 Q2Q0L3W / 854A-2 40 64 74 70 -20 -20 -20 Mark 67-1-3 Q2QL3W / 854A-3 40 65 70 60 -20 -20 -20 N7 Top Head Spray Nozzle Mark 71-1-1 Q2Q60QT / 569F-1 30 98 114 131 -30 -20 -20 Mark 72-1 Weld Neck Flange 720230 / 10618D / 3445-1 20 90 122 179 -40 -40 -40 Mark 73-2-1 Blind Flange C4889-3 30 54 70 78 -30 -30 -30 N8 Top Head Vent Nozzle Mark 74-1 211290 / L3156 40 50 54 51 -20 -20 -20 Mark 75-1 Weld Neck Flange 720230 / 10618D / 3445-1 20 90 122 179 -40 -40 -40 Mark 76-1A Blind Flange D1295-3 20 52 58 72 -40 -40 -40 N9 Jet Pump Instrumentation Nozzle Mark 77-1-1 Q2QL4W / R64A-1 40 66 62 54 -20 -20 -20 Mark 77-1-2 Q2QL4W / R64A-2 40 57 62 56 -20 -20 -20 N10 CRD Hydraulic System Return Mark 80-1 Q2QL4W / 868B 40 67 63 65 -20 -20 -20 Page 18 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Initial RTNDT Values for RPV Materials, Continued Nozzle Materials Drop Test 1 Heat or Heat I Flux I Lot Temp Charpy Energy[ ' (T5oT-60) Weight RTNDT Component (ft-lb) (°F) NOT (°F)

(OF)

_(F)

Nll Core AP & Liquid Control Mark 84-1 NX5001 / 1765 (Alloy 600) (Note 2)

Mark 89-1 Weld Coupling 67993/1550 (Stainless) (Note 2)

Mark 85-1-1 54318 / 1095 (Alloy 600) (Note 2)

N12 Instrument Nozzle Mark 88-1-1 thru 88-1-4 717456 / L9295 / FE-1 40 64 58 57 -20 -20 -20 N13 Instrument Nozzle Mark 88-1-5 thru 88-1-6 717456 / L9295 / FE-1 40 64 58 57 -20 -20 -20 N14 Instrument Nozzle Mark 91-1-1 thru 91-1-4 717456 / L9295 / FE-1 40 64 58 57 -20 -20 -20 N15 Drain Nozzle Mark 93-1 B19W (213099)/ R853A 40 85 86 93 -20 -20 -20 N16 Core Spray (High Pressure)

Mark 63-1-2 Q2QL3W / 867B-2 40 89 89 71 -20 -20 -20 N17 Seal Leak Detector Nozzle Mark 104-1 NX4745 / 461 (Alloy 600) (Note 2)

Mark 30-1 615146/3444 (Note 3)

Mark 142-1 615146/3444 (Note 3)

N18 Top Head Spare Nozzle Mark 71-1-2 Q2Q60QT / 569F-2 30 51 66 93 -30 -20 -20 Mark 99-1 Weld Neck Flange 720230/ 10618D / 3445-1 20 90 122 179 -40 -40 -40 Mark 73-2-2 Blind Flange B7492-2 40 62 50 55 -40 -40 -40 CRD Stub Tube Mark 14 NX4994 I M1753 (Alloy 600) (Note 2)

Mark 14 NX5190 / M1769 (Alloy 600) (Note 2)

Mark 14 NX6104 / M4728 (Alloy 600) (Note 2)

Mark 14 NX7249G (Alloy 600) (Note 2)

Mark 14 1NX5151 / M1758 (Alloy 600) (Note 2)

Mark 14 2NX5291/M1789 (Alloy 600) (Note 2)

Mark 14 4NX5190 / M1770 (Alloy 600) (Note 2)

Mark 14 NX5159 (Alloy 600) (Note 2)

Mark 14 NX4902 (Alloy 600) (Note 2)

Nozzle Welds N6 LPCI Nozzle 629865/A421A27AD -10 69 70 88 -70 -90 -70 N6 LPCI Nozzle 04T931/A423B27AG 0 65 69 72 -60 -90 -60 N6 LPCI Nozzle 402P3162/H426B27AE -10 60 54 68 -70 -70 -70 N6 LPCI Nozzle 5P6771/Unde 124/0342 (Single) 30 78 53 68 -30 -30 -30 N6 LPCI Nozzle 5P6771/Linde 124/0342 (Tandem) 40 77 81 83 -20 -20 -20 N6 LPCI Nozzle 492L4871/A421B27AF 10 56 58 61 -50 -80 -50 N6 LPCI Nozzle 05T776/L314A27AH -10 69 72 81 -70 -70 -70 (1) Minimum Charpy values are used in these calculations.

(2) Alloy 600 and Stainless Steel components do not require fracture toughness evaluation; see Appendix A of Reference 6.1 for additional information.

(3) Small diameter piping does not require fracture toughness evaluation; see Appendix A of Reference 6.1 for additional information.

Page 19 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Initial RTNDT Values for RPV Materials, Continued Appurtenance Materials Drop Test Component Heat or Heat I Flux I Lot Terp Charpy Energy'" (Tsor60) Weight RTNDT (CF) (ft-lb) ('F) NDT (*F)

(*F)

Support Skirt Mark 10-1-1 C2762-1F 30 60 62 59 -30 -50 -30 Mark 10-1-2 A0797-3 20 54 62 51 -40 -10 -10 Support Skirt Extension Mark 10-2-1 thru 10-2-6 R0530-1 70 112 110 90 10 10 10 Shroud Support Marks 20-1-1 thru 20-1-4 (Horizontal Support to BH) 3NX6945-1 I PC-9435 (Alloy 600) (Note 2)

Marks 20-1-1 thru 20-1-4 (Horizontal Support to BH) 2NX7083-1 I PC-9729 (Alloy 600) (Note 2)

Marks 20-2-1, 20-2-2 (Horizontal Support to BH) 2NX694&-1 / PC-9437 (Alloy 600) (Note 2)

Marks 20-4-1 thru 20-4-6 (Vertical Supports from CP) 1NX6897-1 I PC-9401 (Alloy 600) (Note 2)

Marks 20-4-7 thru 20-4-14 (Vertical Supports from CP) 1 NX6897-7 / PC-9402 (Alloy 600) (Note 2)

Marks 17-1-1 thru 17-1-14 (Vertical Supports to BH) 636478-4X (Alloy 600) (Note 2)

Stabilizer Bracket Mark 101-1 A1322-2B 50 67 50 51 -10 -20 -10 Refueling Bellows Bar Mark 29-1-1 thru 29-1-6 A2457-7 60 50 50 52 0 -20 0 Mark 45-1-1 thru 45-1-6 R0503-1 60 53 46 60 0 0 0 Guide Rod Bracket Mark 106-1-1 & 106-1-2 120867/ 333 (Stainless) (Note 2)

Steam Dryer Support Bracket Mark 108-1-1 thru 108-1-4 120867 /333 (Stainless) (Note 2)

Core Spray Bracket Mark 116-1-1 thru 116-1-8 120867 /333 (Stainless) (Note 2)

Feedwater Sparger Bracket Mark 112-1-1 thru 112-1-12 633345 /333 (Stainless) (Note 2)

Top Head Lifting Lug Mark 43-1-5 thru 43-1-8 C3916-2B 60 58 53 59 0 -40 0 Thermocouple Pads and Clamps Mark 47-1 and 47-2 C3427-13A 30 50 53 50 -30 -30 -30 Dryer Hold Down Bracket Marks 110-1-1 thin 110-1-4 C2325-2 60 55 55 52 0 -20 0 Marks 110-1-1 thru 110-1-4 C2480-2 20 50 53 50 -40 -40 -40 (1) Minimum Charpy values are used in these calculations.

(2) Alloy 600 and Stainless Steel components do not require fracture toughness evaluation; see Appendix A of reference 6.1 for additional information. CP = Core Plate; BH = Bottom Head Page 20 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Initial RTNDT Values for RPV Materials, Continued Bolting Materials Test C harpy Energy Mi Lat LST Component Heat Temp (ft-Ib) Exp (*F)

(°F) (mils)

STUDS Closure Mark 38-1-1 thu 38-1-13 11949 10 54 56 56 32 10 Mark 38-1-14 thu 38-1-26 11054 10 46 47 46 26 10 Mark 38-1-27 thu 38-1-44 11949 10 54 56 56 32 10 Mark 38-1-45 thu 38-1-56 84176 10 49 49 48 26 10 Mark 38-1-57 thu 38-1-76 11949 10 54 56 56 32 10 N7 & N18 Nozzles Mark 73-4 82116 10 63 64 63 25 10 N8 Nozzle Mark 76-3 82116 10 63 64 63 25 10 NUTS Closure NMark 39-5-1 thu 39-5-48 43320 10 48 50 48 29 10 Mark 39-5-49 thu 39-5-54 83706 10 50 51 54 26 10 Mark 39-5-55 thu 39-5-76 84751 10 48 48 47 25 10 N7 & N18 Nozzles Mark 73-5 14886 10 69 72 76 30 10 N8 Nozzle Mark 76-4 14886 10 69 72 76 30 10 CLOSURE BUSHINGS Mark 152-1-1 thru 152-1-76 52504 10 48 48 50 28 10 CLOSURE WASHERS Mark 39-6-1 thru 39-6-76 83706 10 50 51 54 26 10 Page 21 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 Adjusted Reference Temperatures for 32 EFPY Lower Shell. Shell 1 to Sholl 2 Girth Weld and Lower Shell Axial Welds Note 10 Thickoessin inches = 6.1875 54 EFPY Peak I D fluence 1.58E+18 n4cm' 32 EFPY Peak I D. uence = 9.36E, 17 Ncm' 32 EFPY Peak 114 T fluence = 6.46E+17 nlcm' Lower-ontermediate Shell and Axial Welds Note 10 Thickoess in inche- 6.1875 54 EFPY Peak I.D. nuence 1 62E018 10cl' 32 EFPY Peak I D fcuence = 9.60E+17 rwcm2 32 EFPY Peak 114T fuence = 6.62E÷17 Nw'M2 N6 Nozzle Note 10 Thicknessin inches 6 1875 54 EFPY Peak I.D. tluence= 5.34E+17 Now2 32 EFPY Peak I D. fluence = 3.16E+17 NVcm2 32 EFPY Peak 114 T fluence = 2.18E+17 n/cmz N12 Nozzle Note 10 Thickness in nches= 61875 54 EFPY Peak I.D fIuence = 3.65E+17 r4cm' 32 EFPY Peak I.D. Suence 2.16E+17 rscm'2 32 EFPY Peak 114 T fluence = 1 49E017 slcm Adjusted Inital 114 T 32 EFPY 32 EFPY 32 EFPY COMPONENT HEAT %Cu %Ni CF CF RTxaT Fluence a RTaeT Ot Oe Margin Shift ART F sdcl' "F (Note 8) PF PF "F PLATES:

Lowe rentermediate Shell C306,5-1 006 063 37 -10 6.62E+17 126 0 6 126 251 15 C3121-2 009 0.65 58 0 662E+17 19.7 0 10 197 394 39 C3147-1 011 063 74.5 0 662E÷17 25.3 0 13 253 50.6 51 Lower Shell C3065-2 006 0.63 37 10 6.46E+17 124 0 6 124 24.8 35 C3066-2 0.07 0.64 44 -20 6 46E+17 14.7 0 7 14.7 29.5 9 C3147-2 0.11 063 745 0 6.46E017 25.0 0 12 25.0 49.9 50 WELDS: (1)

Ciumofenteneal 4P7216(Sy0751 0.045 0.80 61 -50 6 46E+17 20.4 0 10 204 409 -9 4P7216(T50751 0035 0.82 475 -80 6 46E617 159 0 8 15.9 31.8 .48 4P7465(Sy0751 0.02 0.82 27 -60 6.46E017 90. 0 5 9.0 18.1 -41 4P7465(Ty0751 0.02 0.00 27 -60 6 46E017 9.0 0 5 90 181 41 Axial LowerShell 5P621401Sy0331 0.02 082 27 -50 6.46E÷17 90 0 5 9.0 18.1 -31 Lowe Shell 5P6214B(T)l0331 0.014 0.70 22.8 40 6.46E+17 7.6 0 4 76 153 -25 Lcnr-feoennediate Shel 5PS657(S)Y0931 0.07 0.71 95 -60 662E+17 32.3 0 16 323 645 5 Lnoer-lnternediate Shell 5P5657(Ty0931 004 089 54 -60 6 62E+17 183 0 9 103 36.7 -23 NOZZLES:

-orgings N6 LPCI (2) Q2Q1L3W 0.07 o60. 44 -20 2.18E+17 6.0 0 4 8.0 10.0 -i N12 Water LevelIlstwmeroation (2.3) 717456 0.272 0214 136 0 1.49E+17 194 0 10 19.4 38.9 39 Weida (1)

N6 LPCI(2) 629865/A421A27AD 005 1.10 69 -70 218E+17 123 0 6 123 24.7 -45 N6LPCI 2) 04T9311A423927AG 003 1.06 41 -60 2 18Ec17 7.4 0 4 7.4 149 45 N6 LPCI (2) 402P3162JH426827AE 003 083 41 -70 2.10E+17 7.4 9 4 7.4 149 -55 N6 LPCI (2) 5P6771(SY0342 0.03 088 41 -30 2 18E+17 7.4 0 4 7.4 149 -15 6 LPCI (2) 5P6771(Ty0342 0.04 0.95 54 -20 2 18E+17 9.8 0 5 9.8 196 0 N6 LPCI (2) 492L487l/A421027AF 0.03 098 41 -50 2.18E+17 7.4 0 4 7.4 149 -35 N6 LPCI (2) 05T7761L314A27AH 0.06 0.92 82 -70 2.18E+17 149 0 7 14.9 29.8 -40 N12 Water Levi Instnamertation (9) Inonnel INTEGRATEDSURVEILLANCE PROGRAM (4):

Plate (5) C2761-2 0.10 054 65 10 6.66E+17 20.1 0 11 221 441 54 Weld (6,7) 5P6214B 0.027 0.94 36.8 53.7 A40 0662E317 182 0 9 182 36.5 Noles:

(1) This evoluation includes both Single (S) and Tandem IT) wire materials.

(2) Chemistries and InitialRT-D for the nozzle forg0ngs were obtained from BWR fleet CMTRdata. Copper content was based upon 14 data points and nickel was based upon 35 data points.

(3) The N12 nozzle is claesified as a partial penetration in Shell Ring #2.

(4) Repfesentatike materials as defined by the Integrated Surceillance Program (ISP).

(5) The ISP plate material is not the same heat number as the target plate as defined in the ISP Therefore. the CF from RG1.99. Position 1.1 is wed to determine the ART. This information is not required per BWRVIP-135 to dictate the ART owedfor the NMP2 PT curves. and is proided for information only. Plate C3147-1 remains the limiting behline material for the purposeof developIng the PT curves (6) The ISP weld material is not the same heat numher ase terget weld (SP5657) as defined in the ISP. H er. the ISP weld material is the same heat as another beftine weld Therefore. the slroedllan'e data is considered and the CF is adjusted as defined inRG1.99 Postion 2.1.

(7) The Adjusted CF was conneestisely calculated using the hinting parametersfor this heat because there are two (2) sets of data Wovidedby the ISP (from Perry and SSP materials that originated hromGrand Gull).

CF+,,,,, = (27r20)

• 39 75 = 53.7"F (9) PorwoJ submimtal included a conser itrorw = 14.5'F. BWROG NRC-approved methodology has been applied. allowing reduction such that a, = 0-F (9) Non-feirtie matedils do not require ealuation for fracture toughness.

(10) Fluenceconseirtioly extrapolated for ARTdetermination RG 1.190 Flcenee projections proided in reference 6.4 Page 22 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B NMP2 RPV Beltline P-T Curve Input Values Adjusted RTNDT = Initial RTNDT + Shift A = 0 + 51 = 51°F (Based on ART Table)

Vessel Height H = 869.75 inches Bottom of Active Fuel Height B = 216.3 inches Vessel Radius (to base metal) R = 126.7 inches Minimum Vessel Thickness (without clad) t = 6.1875 inches Page 23 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix B 1

NMP2 Definition of RPV Beltline Regionl ]

Elevation Component (inches from RPV "0")

Shell # 2 - Top of Active Fuel (TAF) 366.3" Shell # 1 - Bottom of Active Fuel (BAF) 216.3" Centerline of Recirculation Outlet Nozzle in Shell # 1 172.5" Top of Recirculation Outlet Nozzle N1 in Shell # 1 197.9" Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0" Top of Recirculation Inlet Nozzle N2 in Shell # 1 198.7" Centerline of LPCI Nozzle N6 in Shell #2 372.5" Bottom of LPCI Nozzle N6 in Shell #2 337.1" Centerline of Water Level Instrumentation Nozzle N12 in Shell # 2 366.0" Bottom of Water Level Instrumentation Nozzle N12 in Shell #2 364.4"

[1] The beltline region is defined as any location where the peak neutron fluence is expected to exceed or equal 1.0e17 n/cm 2 .

[2] The dimensions identified above are specified as the distance (elevation) above vessel "0" The review of the axial fluence edicated that the RPV fluence projected to 54 EFPY drops to less than 1.0e17 n/cm2 at 12" e low the BAF and a~tŽ--' above TAF. The beltline region considered in the develop n the P-T curves has b' conservatively adjusted to include the region from 204.6" to 378.4" above reactor vessel "0".

Based on the above, it is concluded that none of the NMP2 reactor vessel plates, nozzles, or welds, other than those included in the Adjusted Reference Temperature Table, are in the beltline region.

Page 24 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Appendix C NMP2 Reactor Pressure Vessel P-T Curve Checklist S... Parameter Completed Comments/Resolutions/Clarifications Initial RTNDT Initial RTNDT has been determined The beltline LPCI N6 and Water Level for NMP2 for all vessel materials Instrumentation N12 nozzle forgings including plates, flanges, forgings, and welds have been considered in the studs, nuts, bolts, welds. development of the beltline PT curves.

Include explanation (including methods/sources) of any exceptions, resolution of discrepant data (e.g., deviation from originally reported values).

Appendix B contains tables of all Initial RTNDT values for NMP2 Has any non-NMP2 initial RTNDT The review performed indicated that the information (e.g., ISP, comparison NMP2 plant-specific weld material ART to other plant) been used? values bound those determined for the ISP representative weld material.

If deviation from the LTR process occurred, sufficient supporting No deviations from the LTR process information has been included (e.g.,

Charpy V-Notch data used to determine an Initial RTNDT).

All previously published Initial RTNDT RVID was reviewed. All initial RTNDT values from sources such as the values agree. No further review was GL88-01, RVID, FSAR, etc., have required.

been reviewed.

Adjusted Reference Temperature (ART)

Sigma I (standard deviation for NMP2 has previously calculated the Initial RTNDT) is 00 F unless the ART using a conservative u* of 14.5 0 F RTNDT was obtained from a source for all materials. However, since the other than CMTRs. If ai is not equal GE/BWROG method of estimating to 0, reference/basis has been RTNDT per NEDC-32399-P operates on provided, the lowest Charpy energy value and provides a conservative adjustment to the 50 ft-lb level, the value of ai is taken to be 0°F for the vessel materials in the evaluation.

Sigma A (standard deviation for ARTNDT) is determined per RG 1.99, Rev. 2 Page 25 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Parameter Completed Comments/Resolutions/Clarifications Chemistry has been determined for Z The vessel chemistries are consistent all vessel beltline materials including with previously reported information.

plates, forgings (if applicable), and welds for NMP2. The LPCI (N6) Nozzle and the Water Include explanation (including Level Instrumentation (N12) Nozzle are methods/sources) of any now included in the extended beltline exceptions, resolution of discrepant region. For the N6 nozzle forging and data (e.g., deviation from originally welds, CMITR's were located which reported values), contained Cu and Ni values as shown in the ART table.

Non-NMP2 chemistry information Z An adjusted CF was required for ISP (e.g., ISP, comparison to other Heat 5P6214B, and was determined plant) used has been adequately per Paragraph 2.1 of RG 1.99.

defined and described.

For any deviation from the LTR Z No deviations from the LTR process process, sufficient information has been included.

All previously published chemistry [

values from sources such as the GL88-01, RVID, FSAR, etc., have been reviewed.

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

The fluence calculation provides an Z axial distribution to allow determination of the vessel elevations that experience fluence of 1.0E17 n/cm 2 both above and below active fuel.

The fluence calculation provides an Z 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 Page 26 of 27 PTLR-2 Revision 0

NMP2 Pressure and Temperature Limits Report Parameter-:- Completed Comments/ResolutionslClarifications explained.

Discontinuities The discontinuity comparison has [

been performed as described in No deviations Section 4.3.2.1 of the LTR. Any deviations have been explained.

Discontinuities requiring additional [

components (such as nozzles) to be considered part of the beltline have been adequately described. It is clear which curve is used to bound each discontinuity.

Appendix G of the LTR describes [

the process for considering a The thickness discontinuity evaluation thickness discontinuity, both beltline demonstrated that no additional and non-beltline. If there is a adjustment is required; the curves discontinuity in the NMP2 vessel bound the discontinuity stresses.

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

Appendix H of the LTR defines the Z An evaluation was performed to assure basis for the CRD Penetration curve that the CRD discontinuity bounds the discontinuity and the appropriate other discontinuities that are protected transient application. The NMP2 by the CRD curve with respect to evaluation bounds the requirements pressure stresses. For heatup/

of Appendix H. cooldown conditions, the CRD penetration provides bounding limits.

Appendix J of the LTR defines the [

basis for the Water Level Instrumentation Nozzle curve discontinuity and the appropriate transient application. The NMP2 evaluation bounds the requirements of Appendix J.

Page 27 of 27 PTLR-2 Revision 0