ML12312A014

Transmittal of Pressure and Temperature Limits Report Revision 02.00

ML12312A014
Person / Time
Site:	Nine Mile Point
Issue date:	09/17/2012
From:	Swift P Constellation Energy Nuclear Group, EDF Group, Nine Mile Point
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12312A014 (27)

Text

P.O. Box 63 CENGS.

a joint venture of Lycoming, NY 13093 0 Constellation

~fEnergy, 01 D NINE MILE POINT NUCLEAR STATION September 17, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

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: Date: A!L, /1-2 Mech./Struc. Design Engineering Reviewed by: ýý tt 1Th-1)R* / ED-1 Date:.9/9! 1--

Mech./Struc. Design Engineering Approved by: Date:

Supervisor Mech./Struc., Design Engineering Approved by: Date: 2..

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 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 Table of Contents Section Title Page 1.0 Purpose 1 2.0 Applicability 1 3.0 Methodology 2 4.0 Operating Limits 3 5.0 Discussion 4 6.0 References 7 Figure 1 NMP1 Pressure Test (Curve A) 10 Figure 2 NMP1 Normal Operation (Heatup and Cooldown) - Core Not Critical (Curve B) 11 Figure 3 NMP1 Normal Operation (Heatup and Cooldown - Core Critical (Curve C) 12 Figure 4 NMP1 Feedwater Nozzle Finite Element Model 13 Table 1 NMP1 Pressure Test (Curve A) - Beltline Region 14 Table 2 NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region 16 Table 3 NMP1 Normal Operation - Core Critical (Curve C) 18 Table 4 NMP1 ART Calculations for 36 EFPY 20 Table 5 Heat Transfer Coefficients for NMP1 Feedwater Nozzle 21 Table 6 Feedwater Nozzle Material Properties 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): _ 100lFO4.

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 0F.

2 Interpreted as: The temperature change in any 1-hour period is less than or equal to 100°F.

3A 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 - ,Bottom Head D 700

0. 600 ...... Upper Vessel Bolt-up 500 Temp:

-Beltline Region 700 400 300 200 100 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 900

• 800 LU D 700 LU K 600 - -Bottom Head 500

...... Upper Vessel 400 Bolt-up Temp: - Beltline Region 300 700 200 100 0:

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 Minimum 200 Criticality:

100'F 100 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 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 = NMVP-i1 Component = Beitline Vessel thickness, t = 7.125 inches Vessel Radius, R = 106.5 inches ART = 161.6 °F =====> 36 EFPY Kit = 0 (no thermal effects)

Safety Factor = 1.5 Mm=

2.472 Temperature Adjustment = 4.0 °F (instrument uncertainty)

Pressure Adjustment = 27.7 4 psig (hydrostatic pressure head for a lull vessel at 70°F)

Pressure Adjustment = psig (instrument uncertainty)

(1)

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

NMP1 Pressure and Temperature Limits Report Table 1 (Continued)

(1)

(1) Adjusted Gauge Fluid Temperature Pressure for Temperature K1m Gauge for P-T Curve P-T Curve

(°F)

Ki, (ksi.Vin) Pressure (psig) 150 49.64 33.09 896 154 858 152 50.31 33.54 908 156 870 154 51.01 34.01 920 158 883 156 51.74 34.49 934 160 896 158 52.49 35.00 947 162 910 160 53.28 35.52 961 164 924 162 54.10 36.07 976 166 939 164 54.95 36.64 992 168 954 166 55.84 37.23 1008 170 970 168 56.77 37.84 1024 172 987 170 57.73 38.48 1042 174 1004 172 58.73 39.15 1060 176 1022 174 59.77 39.85 1079 178 1041 176 60.85 40.57 1098 180 1060 178 61.98 41.32 1118 182 1081 180 63.16 42.10 1140 184 1102 182 64.38 42.92 1162 186 1124 184 65.65 43.77 1185 188 1147 186 66.98 44.65 1209 190 1171 188 68.36 45.57 1233 192 1196 190 69.79 46.53 1259 194 1222 192 71.28 47.52 1286 196 1249 194 72.84 48.56 1314 198 1277 196 74.46 49.64 1343 200 1306 198 76.14 50.76 1374 202 1336 200 77.89 51.93 1405 204 1368 202 79.72 53.14 1438 206 1401 204 81.61 54.41 1473 208 1435 206 83.59 55.73 1508 210 1471 208 85.65 57.10 1545 212 1508 210 87.79 58.52 1584 214 1546 212 90.01 60.01 1624 216 1587 214 92.33 61.55 1666 218 1628 216 94.75 63.16 1710 220 1672 218 97.26 64.84 1755 222 1717 220 99.87 66.58 1802 224 1764 222 102.59 68.39 1851 226 1814 224 105.42 70.28 1902 228 1865 226 108.37 72.25 1955 230 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 = NM P-I Component = Beltline Vessel thickness, t = 7.125 inches Vessel Radius, R = 106.5 inches ART = 161.6 °F=====> 36 EFPY Kit = 12.91 Ksi.Vin Safety Factor = 2.

Mm= 2.472 Temperature Adjustment = 12.2 *F (instrument uncertainty)

Pressure Adjustment = 27.7~ psig (hydrostatic pressure head for a full vessel at 70'F)

Pressure Adjustment = 52.2 psig (instrument uncertainty)

Heat Up and Cool Down Rate = 100 °F/Hr (1)

(1) Adjusted Gauge Fluid Temperature Pressure for Temperature Elm Gauge for P-T Curve P-T Curve

('F) KI, (ksi-Vin) Pressure (psig) (*F) (psig) 48 35.34 11.21 0 70 0 48 35.34 11.21 303 70 224 50 35.43 11.26 305 70 225 52 35.52 11.30 306 70 226 54 35.61 11.35 307 70 227 56 35.71 11.40 308 70 229 58 35.81 11.45 310 70 230 60 35.92 11.50 311 72 231 62 36.03 11.56 313 74 233 64 36.14 11.62 314 76 234 66 36.26 11.68 316 78 236 68 36.39 11.74 318 80 238 70 36.52 11.80 319 82 240 72 36.65 11.87 321 84 241 74 36.80 11.94 323 86 243 76 36.94 12.01 325 88 245 78 37.10 12.09 327 90 247 80 37.25 12.17 329 92 250 82 37.42 12.25 332 94 252 84 37.59 12.34 334 96 254 86 37.77 12.43 336 98 257 88 37.96 12.52 339 100 259 90 38.15 12.62 342 102 262 92 38.35 12.72 344 104 264 94 38.56 12.83 347 106 267 96 38.78 12.93 350 108 270 98 39.01 13.05 353 110 273 100 39.25 13.17 356 112 276 102 39.50 13.29 360 114 280 104 39.75 13.42 363 116 283 106 40.02 13.55 367 118 287 108 40.30 13.69 371 120 291 110 40.59 13.84 375 122 295 112 40.89 13.99 379 124 299 114 41.20 14.14 383 126 303 116 41.53 14.31 387 128 307 118 41.87 14.48 392 130 312 120 42.22 14.65 397 132 317 122 42.59 14.84 402 134 322 124 42.97 15.03 407 136 327 126 43.37 15.23 412 138 332 128 43.79 15.44 418 140 338 130 44.22 15.65 424 142 344 132 44.67 15.88 430 144 350 134 45.14 16.11 436 146 356 Page 16 of 23 PTLR-1 Revision 02.00

NMP1 Pressure and Temperature Limits Report Table 2 (Continued)

(1)

(1) Adjusted Gauge Fluid Temperature Pressure for Temperature Klm Gauge for P-T Curve P-T Curve

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

Flange RTNOT= 'F Adjusted P-T Curve Adjusted P-T Temperature Curve

(°F) Pressure (psig) 100 0 100 113 102 117 104 122 106 127 108 131 110 136 112 141 114 147 116 153 118 159 120 165 122 172 124 179 126 186 128 194 130 202 132 210 134 219 136 228 138 238 140 248 142 259 144 264 146 267 148 270 150 273 152 276 154 280 156 283 158 287 160 291 162 295 164 299 166 303 168 307 170 312 172 317 174 322 176 327 178 332 180 338 182 344 184 350 186 356 188 363 190 370 192 375 194 375 196 375 198 375 200 375 200 408 202 417 Page 18 of 23 PTLR-1 Revision 02.00

NMP1 Pressure and Temperature Limits Report Table 3 (Continued)

Adjusted P-T Curve Adjusted P-T Temperature Curve Pressure (psig) 204 426 206 436 208 446 210 456 212 466 214 477 216 489 218 501 220 514 222 527 224 540 226 554 228 569 230 584 232 600 234 617 236 634 238 652 240 670 242 690 244 710 246 731 248 753 250 776 252 799 254 824 256 850 258 877 260 904 262 933 264 964 266 995 268 1028 270 1062 272 1097 274 1134 276 1172 278 1212 280 1253 282 1297 284 1342 286 1388 288 1437 290 1488 292 1541 294 1596 296 1653 298 1712 300 1774 302 1839 304 1906 Page 19 of 23 PTLR-1 Revision 02.00

NMP1 Pressure and Temperature Limits Report Table 4: NMP1 ART Calculations for 36 EFPY Initial Flux Lot RTNDT ARTN Code No.71 ('F)

Description Heat NO. No. DT Cu (I V(F)

I I Upper Shell Plate G-307-3 P2074 28 0.2 0.48 134.6 64.3 0 17 126.3 Upper Shell Plate G-307-4 P2076 40 0.27 0.53 173.85 83.0 0 17 157.0 4-(U Upper Shell Plate G-307-10 P2091 20 0.22 0.51 148.85 71.1 0 17 125.1 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 N

Description DT

('F)

Upper Shel Axial Welds Lower Shell Axial Welds Circumferential Weld Seam 2-564A/C 2-564D/F 3-564 1

86054B 86054B 1248

~

4E5F 4E5F 4M2F

-50

-50

-50 Fluence Data 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 42.2 28.0 30.1 Location G3Attenation Wall thickness 12uenc ID at 1/4 T2 Fluence Factor, FF UpperFull 1/4T 11/4 (n/CMA2 = 0.624x e.E (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 100% Flow Case Heat Transfer Heat Transfer Temperature Coefficient Temperature Coefficient Region (°F) (Btu/hr-ft2-°F) Region (°F) (Btu/hr-ft2-°F) 1 550.0 205.1 1 100.0 2108.8 2 550.0 205.1 2 325.0 673.9 3 550.0 205.1 3 325.0 191.8 4 550.0 205.1 4 550.0 1000.0 Page 21 of 23 PTLR-1 Revision 02.00

NMPMPressure and Temperature Limits Report Table 6: Feedwater Nozzle Material Properties Material Properties All Steels: Poisson's Ratio 0.3 Densitj 0.283 Reactor Vessel Plate (SA 302 Gr.B) [5, Material Group D]

T a E Thermal Conductivity, K Thermal Diffusiv#y Specific Heat, Cp F win~AF psi BTU/hrwft'F ft1/hr BTUAb OF 300 7.74E -06 2,80E+07 2437 0.42 0.12 350 7,88E-06 24.7 0.409 0.123 400 8.01E -06 2.74E+07 24.6 0,398 0.126 325 7..81E .06 2.79E+07 24.7 0.4145 0.1215 Nozzle Forging (SA 336 with Code Case 1236-1) [5, Material Group A]

T a E Thermal Conductivity, K Thermal Diffusivily Specific Heat, Cp F inln"F psi BTU/hrft*F ft 2/hr BTUhOb F 300 7,30E-06 2.85E+07 23.9 0.406 0.120 350 7.49E--00 23.7 0.396 0.122 400 7,66E-06 2.79E+07 23.6 0.385 0.125 325 7.395E-06 '2.84E+07 23.8 0.401 0.121 Safe End (CS-i SA-105 Gr. II) [5, Material Group 8]

T a E Thermai Conductivity, K Thermal Diffusivity Specific Heat, Cp F inf nzF psi BTU/hr~ft'F ft'/hr BTUIbt*F 300 7I8E-06 2.81E407 28.4 0.481 0.1207 350 7.47E-06 28.0 0.464 0-1234 400 2,75E+07 325 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