ML12312A014

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Transmittal of Pressure and Temperature Limits Report Revision 02.00
ML12312A014
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 09/17/2012
From: Swift P M
Constellation Energy Nuclear Group, EDF Group, Nine Mile Point
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12312A014 (27)
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Text

CENGS.a joint venture of 0 Constellation

~fEnergy, 01 D NINE MILE POINT NUCLEAR STATION P.O. Box 63 Lycoming, NY 13093 September 17, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:

SUBJECT:

Document Control Desk Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Pressure and Temperature Limits Report Revision Enclosed is a copy of the Pressure and Temperature Limits Report, PTLR-1, Revision 02.00, for Nine Mile Point Unit 1 (NMP1). This report revision is being submitted pursuant to NMP1 Technical Specification 6.6.7.c.Should you have any questions regarding the information in this submittal, please contact John J. Dosa, Director Licensing, at (315) 349-5219.Very truly yours, Paul M. Swift Manager Engineering Services PMS/DEV

Enclosure:

Nine Mile Point Unit 1 Pressure and Temperature Limits Report, PTLR-1, Revision 02.00 cc: Regional Administrator, Region I, NRC Project Manager, NRC -Resident Inspector, NRC ENCLOSURE NINE MILE POINT UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT PTLR-1, REVISION 02.00 Nine Mile Point Nuclear Station, LLC September 17, 2012 NMP1 Pressure and Temperature Limits Report Constellation Energy-Nine Mile Point NucledrStatron NINE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 1 Pressure and.Temperature Limits Report (PTLR)PTLR-1, Revision 02.00 Prepared by: Reviewed by: Approved by: Approved by: Mech./Struc.

Design Engineering

ýý tt 1 Th-1)R* / ED-1 Mech./Struc.

Design Engineering Supervisor Mech./Struc., Design Engineering General Supervisor Design Engineering Date: A!L, /1-2 Date:.9/9!

1--Date: Date: 2..This Controlled Document provides reactor pressure vessel pressure and temperature limits for use in-conjunction with the Nine Mile Point Unit I Technical Specifications.

Document pages may only be changed through the re-issue of a revision to the entire document NMP1 Pressure and Temperature Limits Report Section 1.0 2.0 3.0 4.0 5.0 6.0 Table of Contents Title Purpose Applicability Methodology Operating Limits Discussion References NMP1 Pressure Test (Curve A)NMP1 Normal Operation (Heatup and Cooldown)

-Core Not Critical (Curve B)NMP1 Normal Operation (Heatup and Cooldown -Core Critical (Curve C)NMP1 Feedwater Nozzle Finite Element Model NMP1 Pressure Test (Curve A) -Beltline Region NMP1 Normal Operation

-Core Not Critical (Curve B), Beltline Region NMP1 Normal Operation

-Core Critical (Curve C)NMP1 ART Calculations for 36 EFPY Heat Transfer Coefficients for NMP1 Feedwater Nozzle Feedwater Nozzle Material Properties Page 1 1 2 3 4 7 Figure 1 Figure 2 Figure 3 Figure 4 Table 1 Table 2 Table 3 Table 4 Table 5 Table 6 10 11 12 13 14 16 18 20 21 22 Appendix A NMP1 Reactor Vessel Materials Surveillance Program 23 I PTLR-1 Revision 02.00 NMPI Pressure and Temperature Limits Report 1.0 PURPOSE The purpose of the Nine Mile Point Nuclear Station Unit 1 (NMP1) 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) head flange bolt-up temperature limits.This report has been prepared in accordance with the requirements of Technical Specification (TS) Section 6.6.7, "Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)," and the template provided in Licensing Topical Report SIR-05-044, Revision 0 (Reference 6.1).2.0 APPLICABILITY This report is applicable to the NMP1 RPV until the end of operating cycle 22. The following TS sections are affected by the information contained in this report: " Limiting Condition for Operation Section 3.2.1, "Reactor Vessel Heatup and Cooldown Rates."* Limiting Condition for Operation Section 3.2.2, "Minimum Reactor Vessel Temperature for Pressurization."* Surveillance Requirement Section 4.2.2, "Minimum Reactor Vessel Temperature for Pressurization." Page 1 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report 3.0 METHODOLOGY The limits in this report were derived as follows: (1) The methodology used to calculate the pressure and temperature limits is in accordance with Reference 6.1, which has been approved for BWR use by the NRC. The pressure and temperature limit calculations are documented in Reference 6.2.(2) The neutron fluence is calculated in accordance with NRC Regulatory Guide (RG) 1.190 (Reference 6.3) based on the wetted surface fluence that is documented in Reference 6.23. The methodology used to calculate the RPV neutron fluence has been approved by the NRC in Reference 6.5.(3) The adjusted reference temperature (ART) values for the limiting beltline materials are calculated in accordance with NRC Regulatory Guide 1.99, Revision 2 (Reference 6.6), as documented in Reference 6.7 as amended by Reference 6.24.(4) This revision of the pressure and temperature limits is to incorporate the following changes:* Rev. 0 -Initial issue of PTLR.* Rev. 01.00: o Removed 28 EFPY curves/tables which are no longer valid o Limited the use of the 36 EFPY curves/tables until the end of operating cycle (EOC) 22 o Removed 46 EFPY curves/tables which are not used during the current fluence period o Added a footnote 4 and clarification to fourth bullet in Section 4.0 to make the described operating limit consistent with the applicable PTLR Figure.o Previous Technical Specification Pressure-Temperature Limit Figures only had one curve per Figure. The PTLR Figures include several curves. A note was added to the bottom of each PTLR figure indicating plant operation shall remain to the right of all of the curves shown in each Figure.o Changed the legend for the temperature axis on each curve from "metal" temperature to "coolant" temperature to be consistent with the sample Figures 2-2 and 2-3 in Reference 6.1.o Added a footnote 1 to the last two columns of the Curve A and B Tables to make more evident that the data in the last two columns was; used to plot the respective curves with instrument uncertainty and static head corrections added.o Removed the 28 EFPY and 46 EFPY ART Calculation Tables corresponding to the removal of the 28 EFPY and 46 EFPY PT curves/tables.

Page 2 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Rev. 02.00: o Included newly calculated ART values from Reference 6.24 to account for increased fluence values due to updated cycle calculations and GNF2 fuel introduction.

o Included newly developed PT Curves A, B, and C which were produced in Reference 6.25 using the new ART values.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 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 6.6.7.4.0 OPERATING LIMITS The pressure-temperature (P-T) limit curves included in this report represent steam dome pressure versus minimum vessel coolant temperature (as measured from recirculation loop suction) 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) core not critical operation (heatup and cooldown), referred to as Curve B; and (c) core critical operation (heatup and cooldown), referred to as Curve C.Complete P-T limit curves were developed for 28, 36 and 46 EFPY for NMP1, as documented in Reference 6.2. Only the NMP1 P-T limit curves for the current fluence period as documented in Reference 6.25 are included in this report. The applicable NMP1 P-T limit curves for this fluence period are included in Figures 1 through 3, and a tabulation of the curves is included in Tables 1 through 3.Page 3 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Other conditions applicable to the NMP1 RPV are:* Heatup and Cooldown rate limit during Hydrostatic and Class 1 Leak Testing (Figure 1: Curve A): _ 25°F/hourl.

  • Normal Operating Heatup and Cooldown rate limit (Figure 2: Curve B -non-nuclear heating, and Figure 3: Curve C -nuclear heating):

__ 100°F/hour

.* RPV head installation temperature (i.e., bolt-up) and core not critical limit (Figure 1: Curve A -Hydrostatic and Class 1 Leak Testing; Figure 2: Curve B -non-nuclear heating):

__ 70'F 3." RPV flange and adjacent shell temperature core critical limit (Figure 3: Curve C -nuclear heating):

_ 100lFO 4.5.0 DISCUSSION The adjusted reference temperature (ART) of the limiting beltline material is used to adjust beltline P-T curves to account for irradiation effects. Regulatory Guide 1.99, Revision 2 (Reference 6.6) provides the methods for determining the ART. The RG 1.99 methods for determining the limiting material and adjusting the P-T curves using ART are discussed in this section.The vessel beltline copper (Cu) and nickel (Ni) values were obtained from the evaluation of the NMP1 vessel plate and weld materials (Reference 6.7). The Cu and Ni values 'were used with Tables 1 and 2 of RG 1.99 to determine a chemistry factor (CF) per Paragraph 1.1 of RG 1.99 for welds and plates, respectively.

The peak RPV inside diameter (ID) fluence values of 1.12 x 1018 n/cm 2 at 28 EFPY and 1.61 x 1018 n/cm 2 at 46 EFPY used in the P-T curve evaluation were obtained from Reference 6.4.Neutron fluence values were calculated using methods that conform to the guidelines of RG 1 Interpreted as: The temperature change in any 1-hour period is less than or equal to 25 0 F.2 Interpreted as: The temperature change in any 1-hour period is less than or equal to 100°F.3 A higher minimum bolt-up temperature of 70°F was applied to these curves, as compared to the 60'F value determined in Reference 6.2, in order to be consistent with the minimum bolt-up temperature value used in previous studies.With water level within the normal range for power operation, the minimum criticality temperature of 100'F is determined from the RTNDT of the closure flange region + 60'F.Page 4 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report 1.190 (Reference 6.3). At 36 EFPY, the peak fluence value of 1.34 x 1018 n/cm 2 was obtained by performing a linear interpolation between the fluence values at 28 and 46 EFPY. These fluence values apply to the limiting beltline lower shell plate (Heat No. P2112 for NMP1). The fluence values for the lower shell plates are based upon an attenuation factor of 0.652 for a postulated 1/4T flaw. As a result, the 1/4T fluences for 28, 36 and 46 EFPY for the limiting lower shell plate are 7.29 x 1017, 8.71 x 1017 and 1.05 x 1018 n/cm 2 , respectively, for NMP1. The peak RPV ID fluence values described above were revised in Reference 6.23 after Revision 1 of this PTLR was submitted to the NRC. Although the revised peak RPV ID fluence values increased, the validity period for the 36 EFPY curves remains until the end of operating cycle 22 (< 36 EFPY) as documented in Reference 6.25.The P-T limit curves for the core not critical and core critical 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 is in the outer wall during heatup. However, as a conservative simplification, the thermal gradient stresses at the 1/4T location are assumed to be tensile for both heatup and cooldown.

This results in the approach of applying the maximum tensile stresses at the 1/4T location.

This approach is conservative because irradiation effects cause the allowable toughness at the 1/4T location to be less than that at the 3/4T location for a given metal temperature.

This approach causes no operational difficulties, since the boiling water reactor is at steam saturation conditions during normal operation, which is well above the P-T curve limits.For the core not critical curve (Curve B) and the core critical curve (Curve C), the P-T curves are applicable for a coolant heatup and cooldown temperature rate of _ 100°Flhr.

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 _< 25°Flhr must be maintained.

The P-T limits and corresponding limits of either Curve A or B may be applied, if necessary, while achieving or recovering from test conditions.

Thus, although Curve A applies during pressure testing, the limits of Curve B may be conservatively used during pressure testing if the pressure test heatup/cooldown rate limits cannot be maintained.

Page 5 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report The initial nil-ductility transition reference temperature (RTNDT), the chemistry (weight-percent copper and nickel), and ART at the 1/4T location for all RPV beltline materials significantly affected by fluence (i.e., fluence > 1017 n/cm 2 for E > 1 MeV) are shown in Table 4 for 36 EFPY, based on Reference 6.24. The initial RTNDT values were determined and reported to the NRC in the NMP1 responses to NRC Generic Letter (GL) 92-01, Revision 1 (Reference 6.8) and GL 92-01, Revision 1, Supplement 1 (Reference 6.9). The NRC acknowledged these GL responses in letters dated March 30, 1994, August 26, 1996, and June 25, 1999 (References 6.10, 6.11, and 6.12, respectively).

The initial RTNDT values shown in Table 4 have previously been used in establishing the current TS P-T limit curves (license amendment approved by the NRC in Reference 6.5) and in evaluations contained in the License Renewal Application (approved by the NRC in Reference 6.13).Per Reference 6.7 and in accordance with Appendix A of Reference 6.1, the NMP1 representative weld and plate surveillance materials data from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) were reviewed.

The representative heats of plate materials (P2112 and P2130) in the ISP are the same as the lower shell plate material in the vessel beltline region of NMPI. For plate heat P2112, since the scatter in the fitted results exceeds 1-sigma (17*F), the full 2-sigma margin term has been utilized in calculating the ART value for this plate in the vessel. For plate heat P2130, since the surveillance data was found to be credible, the margin term (GA = 17°F) is divided by two for the plate material when calculating the ART. Therefore, the CFs from the NRC's Reactor Vessel Integrity Database (Reference 6.14) and Reference 6.6 were used in the determination of ART for all NMP1 materials except for plate heat P2130.The only computer code used in the determination of the NMPI P-T curves was the ANSYS/Mechanical Release 6.1 (with Service Packs 2 and 3) finite element computer program (Reference 6.15) for the feedwater nozzle (non-beltline) stresses.

This analysis was performed to determine through-wall thermal and pressure stress distributions for the NMPI feedwater nozzles due to a step-change thermal transient (Reference 6.16). The ANSYS program was controlled under the vendor's 10 CFR 50 Appendix B Quality Assurance Program for nuclear quality-related work. Benchmarking consistent with NRC Generic Letter 83-11, Supplement 1 (Reference 6.17), was performed as a part of the computer program verification by comparing the solutions produced by the computer code to hand calculations for several problems.

The following inputs were used in the finite element analysis: Page 6 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report* With respect to operating conditions, stress distributions were developed for a thermal shock of 450'F, which represents the maximum thermal shock for the feedwater nozzle during normal operating conditions.

The stress results for a 450 *F shock are appropriate for use in developing the non-beltline P-T curves based on the limiting feedwater nozzle, as a shock of 450*F is representative of the Turbine Roll transient that occurs in the feedwater nozzle as part of the 100*F/hr startup transient.

Therefore, these stresses represent the bounding stresses in the feedwater nozzle associated with 100 *F/hr heatup/cooldown limits associated with the P-T curves for the upper vessel feedwater nozzle region.o Heat transfer coefficients were calculated from the governing design basis stress report for the NMP1 feedwater nozzle and from a model of the heat transfer coefficient as a function of flow rate, as shown in Table 5 (Reference 6.16). The heat transfer coefficients were evaluated at flow rates that bound the actual operating conditions in the feedwater nozzles at NMP1.* A two-dimensional, axisymmetric finite element model of the feedwater nozzle was constructed (Figure 4) using the same modeling techniques that were employed to evaluate the feedwater nozzle in the governing design basis report. In order to properly model the feedwater nozzle, the analysis was performed as a penetration in a sphere and not in a cylinder.

To make up for this difference in geometry, a conversion factor of 3.2 times the cylinder radius was used to model the sphere (Reference 6.16). Material properties were evaluated at 325°F (Table 6) to conservatively bound the 100°F condition where the maximum stress occurred.

6.0 REFERENCES

1. Structural Integrity Associates Report No. SIR-05-044-A, Revision 0, "Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," April 2007.2. Structural Integrity Associates Calculation No. 0800297.301, Revision 1, "Revised Pressure-Temperature Curves," January 2009.3. NRC Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," March 2001.4. "Neutron Transport Analysis for Nine Mile Point Unit 1," Report Number MPM-405778, MPM Technologies, May 2006.Page 7 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report 5. NRC Letter to NMPNS dated October 27, 2003, "Nine Mile Point Nuclear Station, Unit No. 1, Issuance of Amendment Re: Pressure-Temperature Limit Curves (TAC No.MB6687)." 6. NRC Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," May 1988.7. Structural Integrity Associates Calculation No. 0800297.300, Revision 1, "Evaluation of Adjusted Reference Temperature Shifts," August 2008.8. NRC Generic Letter 92-01, Revision 1, "Reactor Vessel Structural Integrity," March 6, 1992.9. NRC Generic Letter 92-01, Revision 1, Supplement 1, "Reactor Vessel Structural Integrity," May 19, 1995.10. NRC Letter to Niagara Mohawk Power Corporation (NMPC) dated March 30, 1994,"Generic Letter (GL) 92-01, Revision 1, 'Reactor Vessel Structural Integrity,'

Nine Mile Point Nuclear Station Unit No. 1 (NMP-1) (TAC No. M83486)." 11. NRC Letter to NMPC dated August 26, 1996, "Closeout for Niagara Mohawk Power Corporation (NMPC) Response to Generic Letter 92-01, Revision 1, Supplement 1 for the Nine Mile Point Nuclear Station, Unit Nos. 1 & 2 (TAC Nos. M92700 and M927001)." 12. NRC Letter to NMPC dated June 25, 1999, "Response to Request for Additional Information Regarding Generic Letter 92-01, Revision 1, Supplement 1, 'Reactor Vessel Structural Integrity,'

Nine Mile Point Nuclear Station, Unit Nos. 1 & 2 (TAC Nos. MA1200 and MA1201)." 13. NUREG-1 900, "Safety Evaluation Report Related to the License Renewal of Nine Mile Point Nuclear Station, Units 1 and 2," September 2006.14. U. S. Nuclear Regulatory Commission, "Reactor Vessel Integrity Database Version 2.0.1," September 7, 2000.15. ANSYS/Mechanical Release 6.1 (w/Service Packs 2 and 3), ANSYS, Inc., April 2002.16. Structural Integrity Associates Calculation No. NMP-09Q-302, Revision 0, "Feedwater Nozzle Green's Functions for Nine Mile Point Unit 1." 17. NRC Generic Letter 83-11, Supplement 1, "Licensee Qualification for Performing Safety Analyses," June 24, 1999.18. NRC Letter to 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)." 19. G.E. Drawing No. 237E434, "Loadings Reactor Vessel." Page 8 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report 20. "Neutron Transport Analysis for Nine Mile Point Unit 1," Report Number MPM-1209877, MPM Tecnologies, December 2009.21. Engineering Change Notice, ECN No. N1-09-022 0800297.300-01.00 Rev. 000.22. Calculation Change Notice, CCN No. N1-09-022 0800297.301-01.00 Rev. 000 23. "Neutron Transport Analysis for Nine Mile Point Unit 1," Report Number MPM-611914, MPM Tecnologies, December 2011.24. Engineering Change Notice, ECN No. ECP-10-000337-CN-006 0800297.300-01.00 Rev. 000.25. Calculation Change Notice, CCN No. ECP-10-000337-CN-007 0800297.301-01.00 Rev. 000 Page 9 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Figure 1: NMP1 Pressure Test (Curve A)Curve is Valid Until End of Operating Cycle 22 1900 1800 1700 1600 1500 1400 1300 0.3 1200 U.'z 900 800 LU D 700 0. 600 500 400 300 200 100-,Bottom Head...... Upper Vessel-Beltline Region Bolt-up Temp: 700 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL COOLANT TEMPERATURE

(-F)(MAINTAIN PLANT OPERATION TO THE RIGHT OF ALL CURVES)Page 10 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Figure 2: NMP1 Normal Operation (Heatup and Cooldown)

-Core Not Critial (Curve B)Curve is Valid Until End of Operating Cycle 22 1900 1800 1700 1600 1500 1400._1300 1200> 1100 0 1000 LU z 900800 LU D 700 LU K 600 500 400 300 200 100 0:--Bottom Head...... Upper Vessel-Beltline Region Bolt-up Temp: 700 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL COOLANT TEMPERATURE

(-F)(MAINTAIN PLANT OPERATION TO THE RIGHT OF ALL CURVES)Page 11 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Figure 3: NMP1 Normal Operation (Heatup and Cooldown)-

Core Critical (Curve C)Curve is Valid Until End of Operating Cycle 22 1900 1800 1700 1600 1500 1400 1300 1200 LU> 1100 0 1000 LU z 900 800 LU 700 600 500 400 300 200 100 Minimum Criticality:

100'F 40 60 20 0 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL COOLANT TEMPERATURE

('F)MAINTAIN PLANT OPERATION TO THE RIGHT OF THE CURVE Page 12 of 23 PTLR-1 Revision 02.00 NMPI Pressure and Temperature Limits Report Figure 4: NMPI Feedwater Nozzle Finite Element Model Feedwater Nozzle Finite Element Model Page 13 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 1: NMP1 Pressure Test (Curve A) -Beitline Region, EOC 22 Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =Kit =Safety Factor =Mm=Temperature Adjustment

=Pressure Adjustment

=Pressure Adjustment

=NMVP-i1 Beitline 7.125 106.5 161.6 0 1.5 2.472 4.0 27.7 4 inches inches°F =====>(no thermal effects)36 EFPY°F (instrument uncertainty) psig (hydrostatic pressure head for a lull vessel at 70°F)psig (instrument uncertainty)

Gauge Fluid Temperature (5F)56 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 Kk 35.71 35.71 35.81 35.92 36.03 36.14 36.26 36.39 36.52 36.65 36.80 36.94 37.10 37.25 37.42 37.59 37.77 37.96 38.15 38.35 38.56 38.78 39.01 39.25 39.50 39.75 40.02 40.30 40.59 40.89 41.20 41.53 41.87 42.22 42.59 42.97 43.37 43.79 44.22 44.67 45.14 45.63 46.13 46.66 47.21 47.78 48.38 49.00 KIm (ksi.Vin)23.81 23.81 23.87 23.95 24.02 24.10 24.18 24.26 24.35 24.44 24.53 24.63 24.73 24.84 24.95 25.06 25.18 25.31 25.43 25.57 25.71 25.86 26.01 26.17 26.33 26.50 26.68 26.87 27.06 27.26 27.47 27.69 27.91 28.15 28.39 28.65 28.92 29.19 29.48 29.78 30.09 30.42 30.76 31.11 31.47 31.85 32.25 32.66 Gauge Pressure 0 644 646 648 650 652 654 657 659 661 664 667 669 672 675 678 682 685 688 692 696 700 704 708 713 717 722 727 732 738 743 749 756 762 769 775 783 790 798 806 814 823 832 842 852 862 873 884 (1)Temperature for P-T Curve (7F)70 70 70 70 70 70 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 (1)Adjusted Pressure for P-T Curve (psig)0 607 608 610 612 614 617 619 621 624 626 629 632 635 638 641 644 647 651 654 658 662 666 671 675 680 684 689 695 700 706 712 718 724 731 738 745 752 760 768 777 786 795 804 814 824 835 846 Page 14 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 1 (Continued)

Gauge Fluid Temperature 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 Ki, 49.64 50.31 51.01 51.74 52.49 53.28 54.10 54.95 55.84 56.77 57.73 58.73 59.77 60.85 61.98 63.16 64.38 65.65 66.98 68.36 69.79 71.28 72.84 74.46 76.14 77.89 79.72 81.61 83.59 85.65 87.79 90.01 92.33 94.75 97.26 99.87 102.59 105.42 108.37 K1m (ksi.Vin)33.09 33.54 34.01 34.49 35.00 35.52 36.07 36.64 37.23 37.84 38.48 39.15 39.85 40.57 41.32 42.10 42.92 43.77 44.65 45.57 46.53 47.52 48.56 49.64 50.76 51.93 53.14 54.41 55.73 57.10 58.52 60.01 61.55 63.16 64.84 66.58 68.39 70.28 72.25 Gauge Pressure 896 908 920 934 947 961 976 992 1008 1024 1042 1060 1079 1098 1118 1140 1162 1185 1209 1233 1259 1286 1314 1343 1374 1405 1438 1473 1508 1545 1584 1624 1666 1710 1755 1802 1851 1902 1955 (1)Temperature for P-T Curve (°F)154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 (1)Adjusted Pressure for P-T Curve (psig)858 870 883 896 910 924 939 954 970 987 1004 1022 1041 1060 1081 1102 1124 1147 1171 1196 1222 1249 1277 1306 1336 1368 1401 1435 1471 1508 1546 1587 1628 1672 1717 1764 1814 1865 1918 (1) DATA IN THESE COLUMNS WERE USED TO PLOT P-T CURVES AND INCLUDE INSTRUMENT UNCERTAINTIES/STATIC HEAD CORRECTION.

Page 15 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 2: NMP1 Normal Operation

-Core Not Critical (Curve B), Beltline Region, EOC 22 Plant =Component

=Vessel thickness, t =Vessel Radius, R =ART =Kit =Safety Factor =Mm=Temperature Adjustment

=Pressure Adjustment

=Pressure Adjustment

=Heat Up and Cool Down Rate =NM P-I Beltline 7.125 106.5 161.6 12.91 2.2.472 12.2 27.7~52.2 100 inches inches°F =====>Ksi.Vin 36 EFPY*F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70'F)psig (instrument uncertainty)

°F/Hr Gauge Fluid Temperature

('F)48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 KI, 35.34 35.34 35.43 35.52 35.61 35.71 35.81 35.92 36.03 36.14 36.26 36.39 36.52 36.65 36.80 36.94 37.10 37.25 37.42 37.59 37.77 37.96 38.15 38.35 38.56 38.78 39.01 39.25 39.50 39.75 40.02 40.30 40.59 40.89 41.20 41.53 41.87 42.22 42.59 42.97 43.37 43.79 44.22 44.67 45.14 Elm (ksi-Vin)11.21 11.21 11.26 11.30 11.35 11.40 11.45 11.50 11.56 11.62 11.68 11.74 11.80 11.87 11.94 12.01 12.09 12.17 12.25 12.34 12.43 12.52 12.62 12.72 12.83 12.93 13.05 13.17 13.29 13.42 13.55 13.69 13.84 13.99 14.14 14.31 14.48 14.65 14.84 15.03 15.23 15.44 15.65 15.88 16.11 Gauge Pressure (psig)0 303 305 306 307 308 310 311 313 314 316 318 319 321 323 325 327 329 332 334 336 339 342 344 347 350 353 356 360 363 367 371 375 379 383 387 392 397 402 407 412 418 424 430 436 (1)Temperature for P-T Curve (*F)70 70 70 70 70 70 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 (1)Adjusted Pressure for P-T Curve (psig)0 224 225 226 227 229 230 231 233 234 236 238 240 241 243 245 247 250 252 254 257 259 262 264 267 270 273 276 280 283 287 291 295 299 303 307 312 317 322 327 332 338 344 350 356 Page 16 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 2 (Continued)

Gauge Fluid Temperature

(°F)36 138 140 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 Kic 45.63 46.13 46.66 47.21 47.78 48.38 49.00 49.64 50.31 51.01 51.74 52.49 53.28 54.10 54.95 55.84 56.77 57.73 58.73 59.77 60.85 61.98 63.16 64.38 65.65 66.98 68.36 69.79 71.28 72.84 74.46 76.14 77.89 79.72 81.61 83.59 85.65 87.79 90.01 92.33 94.75 97.26 99.87 102.59 105.42 108.37 111.44 114.63 117.96 121.41 125.01 128.76 132.66 136.72 140.95 145.34 149.92 154.68 159.64 Klm (ksi.Vin)16.36 16.61 16.87 17.15 17.43 17.73 18.04 18.36 18.70 19.05 19.41 19.79 20.18 20.59 21.02 21.46 21.93 22.41 22.91 23.43 23.97 24.53 25.12 25.73 26.37 27.03 27.72 28.44 29.18 29.96 30.77 31.61 32.49 33.40 34.35 35.34 36.37 37.44 38.55 39.71 40.92 42.17 43.48 44.84 46.26 47.73 49.26 50.86 52.52 54.25 56.05 57.92 59.87 61.90 64.02 66.21 68.50 70.88 73.36 Gauge Pressure (psig)443 450 457 464 472 480 488 497 506 516 525 536 546 557 569 581 593 606 620 634 649 664 680 697 714 732 750 770 790 811 833 856 879 904 930 956 984 1013 1043 1075 1107 1141 1177 1214 1252 1292 1333 1377 1422 1468 1517 1568 1621 1676 1733 1792 1854 1919 1986 (1)Temperature for P-T Curve (°F)148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 264 (1)Adjusted Pressure for P-T Curve (psig)363 370 377 384 392 400 408 417 426 436 446 456 466 477 489 501 514 527 540 554 569 584 600 617 634 652 670 690 710 731 753 776 799 824 850 877 904 933 964 995 1028 1062 1097 1134 1172 1212 1253 1297 1342 1388 1437 1488 1541 1596 1653 1712 1774 1839 1906 (1) DATA IN THESE COLUMNS WERE USED TO PLOT P-T CURVES AND INCLUDE INSTRUMENT UNCERTAINTIESISTATIC HEAD CORRECTION.

Page 17 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 3: NMP1 Normal Operation

-Core Critical (Curve C), EOC 22 Plant =Curve A Leak Test Curve A leak Test Unit Pressure Flange RTNOT =Adjusted P-T Curve Temperature

(°F)100 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 200 202 psig psig (hydrostatic pressure)'F Adjusted P-T Curve Pressure (psig)0 113 117 122 127 131 136 141 147 153 159 165 172 179 186 194 202 210 219 228 238 248 259 264 267 270 273 276 280 283 287 291 295 299 303 307 312 317 322 327 332 338 344 350 356 363 370 375 375 375 375 375 408 417 Page 18 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 3 (Continued)

Adjusted P-T Curve Temperature 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 264 266 268 270 272 274 276 278 280 282 284 286 288 290 292 294 296 298 300 302 304 Adjusted P-T Curve Pressure (psig)426 436 446 456 466 477 489 501 514 527 540 554 569 584 600 617 634 652 670 690 710 731 753 776 799 824 850 877 904 933 964 995 1028 1062 1097 1134 1172 1212 1253 1297 1342 1388 1437 1488 1541 1596 1653 1712 1774 1839 1906 Page 19 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 4: NMP1 ART Calculations for 36 EFPY Description Code No.71 Heat NO.Flux Lot No.Initial RTNDT ('F)Cu (I ARTN DT V(F)126.3 157.0 125.1 I I Upper Shell Plate Upper Shell Plate Upper Shell Plate G-307-3 G-307-4 G-307-10 P2074 P2076 P2091 28 40 20 0.2 0.27 0.22 0.48 0.53 0.51 134.6 173.85 148.85 64.3 83.0 71.1 0 0 0 17 17 17 4-(U 0.Lower Shell Plate q-8-1 P2112 -36 0.236 0.503 ! , 228.35 91.6 0 17 161.6 Lower Shell Plate 72.9 Description N Upper Shel Axial Welds Lower Shell Axial Welds Circumferential Weld Seam 2-564A/C 2-564D/F 3-564 86054B 86054B 1248 4E5F 4E5F 4M2F-50-50-50 V 0.214 0.214 0.214 0.046 0.046 0.076 97.59 97.59 99.9 46.1 39.0 40.1 0 0 0 23.1 19.5 20.0 DT ('F)42.2 28.0 30.1-. 1 ~ Fluence Data Location Wall thickness ID G3Attenation 12uenc at 1/4 T2 Fluence Factor, FF UpperFull 1/4T (n/CMA2 11/4 = e.E 0.624x (nEcmA2) 04f(O.28-O.log f)Upper Shell Plate G-307-3 7.125 1.781 2.05E+18 0.652 1.34E+18 0.478 Upper Shell Plate G-307-4 7.125 1.781 2.05E+18 0.652 1.34E+18 0.478 Upper Shell Plate G-307-10 7.125 1.781 2.05E+18 0.652 1.34E+18 0.478 Lower Shell Plate G-8-1 7.125 1.781 1.42E+18 0.652 9.23E+17 0.401-Lower Shell Plate G-8-3/4 7.125 {1.781 1.42E+18 0.652 9.23 E+17 0.401 Upper Shell Axial Welds 2-564A/C 7.125 1.781 I2.OOE+18 0.652 1.31E+18 0.472 Z Lower Shell Axial Welds 2-564D/F 7.125 1.781 1.41E+18 0.652 9.17E+17 0.400 Circumferential Weld Seam 3-564 7.125 1.781 1.42E+18 0.652 9.23E+17 0.401 Page 20 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report Table 5: Heat Transfer Coefficients for NMP1 Feedwater Nozzle 0% Flow Case Heat Transfer Temperature Coefficient Region (°F) (Btu/hr-ft 2-°F)1 550.0 205.1 2 550.0 205.1 3 550.0 205.1 4 550.0 205.1 100% Flow Case Heat Transfer Temperature Coefficient Region (°F) (Btu/hr-ft 2-°F)1 100.0 2108.8 2 325.0 673.9 3 325.0 191.8 4 550.0 1000.0 Page 21 of 23 PTLR-1 Revision 02.00 NMPM Pressure and Temperature Limits Report Table 6: Feedwater Nozzle Material Properties Material Properties All Steels: Poisso Densitj T F 300 350 400 325 T F 300 350 400 325 T F 300 350 400 325 a win~7.74E 7,88E 8.01E 7..81E n's Ratio 0.3 0.283 Reactor Vessel Plate (SA 302 Gr.B) [5, Material Group D]E Thermal Conductivity, K Thermal Diffusiv#y Specific Heat, Cp AF psi BTU/hrwft'F ft 1/hr BTUAb OF-06 2,80E+07 2437 0.42 0.12-06 24.7 0.409 0.123-06 2.74E+07 24.6 0,398 0.126.06 2.79E+07 24.7 0.4145 0.1215 Nozzle Forging (SA 336 with Code Case 1236-1) [5, Material Group A]a E Thermal Conductivity, K Thermal Diffusivily Specific Heat, Cp inln"F psi BTU/hrft*F ft 2/hr BTUhOb F 7,30E-06 2.85E+07 23.9 0.406 0.120 7.49E--00 23.7 0.396 0.122 7,66E-06 2.79E+07 23.6 0.385 0.125 7.395E-06

'2.84E+07 23.8 0.401 0.121 Safe End (CS-i SA-105 Gr. II) [5, Material Group 8]a E Thermai Conductivity, K Thermal Diffusivity Specific Heat, Cp inf nzF psi BTU/hr~ft'F ft'/hr BTUIb t*F 7I8E-06 2.81E407 28.4 0.481 0.1207 7.47E-06 28.0 0.464 0-1234 2,75E+07 7.325E-06 r 2.80E+07 28.2 0.4725 0.1221 Page 22 of 23 PTLR-1 Revision 02.00 NMP1 Pressure and Temperature Limits Report APPENDIX A NMP1 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM NMP1 has replaced the original materials surveillance program with the BWRVIP Integrated Surveillance Program (ISP). This program meets the requirements of 10 CFR 50, Appendix H, for integrated surveillance programs, and has been approved by the NRC (see NMP1 License Amendment No. 184, Reference 6.18). The representative plate material from the ISP is not the same heat number as the target plate in the NMP1 vessel. Also, the representative weld material is not the same heat number as the target weld in the NMP1 vessel. However, there is one matching plate heat number (heat number P2130-2) in the Supplemental Surveillance Program (SSP). Irradiated data is available from SSP capsules A, B, D, G, E, and I (Reference 6.7). Under the ISP, there is one weld heat that is scheduled to be tested in 2017.Representative surveillance capsule materials for the NMP1 weld are contained in the Hatch Unit 2 surveillance capsule program. Under the Supplemental Surveillance Program (SSP), there are no additional representative capsule materials to be tested.Page 23 of 23 PTLR-1 Revision 02.00

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