ML090640302

PTLR-1, Revision 0, Nine Mile Point Unit 1 Pressure and Temperature Limits Report (Ptlr).

ML090640302
Person / Time
Site:	Nine Mile Point
Issue date:	02/13/2009
From:	Inch G Constellation Energy Group, Nine Mile Point
To:	Office of Nuclear Reactor Regulation
References
PTLR-1, Rev 0
Download: ML090640302 (44)

Text

ATTACHMENT 3 NINE MILE POINT UNIT 1 PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

Nine Mile Point Nuclear Station, LLC March 3, 2009

NINE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 1 Pressure and Temperature Limits Report (PTLR)

PTLR-1, Revision 0

I Prepared by: Date: 2./IY;/goo*

G. 8. Inch Mechanical Design Engineering Reviewed by: Date: -'// /**26.07 R. C Fri Mechanical Design Engineering Approved by: Date: ____

P. E. B Supervisor Mech./Struc. Design Engineering Approved by: Date: 2/"7/o' A. D. Sterio, 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 Pane 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 NMP1 Pressure Test (Curve A), 28 EFPY 8 Figure 2 NMP1 Normal Operation (Heatup and Cooldown) - Core Not Critical (Curve B), 9 28 EFPY Figure 3 NMP1 Normal Operation (Heatup and Cooldown) - Core Critical (Curve C), 10 28 EFPY Figure 4 NMP1 Pressure Test (Curve A), 36 EFPY 11 Figure 5 NMP1 Normal Operation (Heatup and Cooldown) - Core Not Critical (Curve B), 12 36 EFPY Figure 6 NMP1 Normal Operation (Heatup and Cooldown) - Core Critical (Curve C), 13 36 EFPY Figure 7 NMP1 Pressure Test (Curve A), 46 EFPY 14 Figure 8 NMP1 Normal Operation (Heatup and Cooldown) - Core Not Critical (Curve B), 15 46 EFPY Figure 9 NMP1 Normal Operation (Heatup and Cooldown) - Core Critical (Curve C), 16 46 EFPY Figure 10 NMP1 Feedwater Nozzle Finite Element Model 17 1

Table 1 NMP1 Pressure Test (Curve A) - Beltline Region, 28 EFPY 18 Table 2 NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region, 28 EFPY 20 Table 3 NMP1 Normal Operation - Core Critical (Curve C), 28 EFPY 22 Table 4 NMP1 Pressure Test (Curve A) - Beltline Region, 36 EFPY 24 Table 5 NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region, 36 EFPY 26 Table 6 NMP1 Normal Operation - Core Critical (Curve C), 36 EFPY 28 Table 7 NMP1 Pressure Test (Curve A) - Beltline Region, 46 EFPY 30 Table 8 NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region, 46 EFPY 32 Table 9 NMP1 Normal Operation - Core Critical (Curve C), 46 EFPY 34 Table 10 NMP1 ART Calculations for 28 EFPY 36 Table 11 NMP1 ART Calculations for 36 EFPY 37 Table 12 NMP1 ART Calculations for 46 EFPY 38 Table 13 Heat Transfer Coefficients for NMP1 Feedwater Nozzle 39 Table 14 Feedwater Nozzle Material Properties 40 Appendix A NMP1 Reactor Vessel Materials Surveillance Program 41 PTLR-1 Revision 0

NMP1 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 for 28, 36 and 46 Effective Full-Power Years (EFPY).

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."

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.

Page 1 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report (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 6.4. 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.

(4) This revision of the pressure and temperature limits is to incorporate the following changes:

0 Initial issue of PTLR.

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 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. The NMP1 P-T limit curves for 28 EFPY are provided in Figures 1 through 3, and a tabulation of the curves is included in Tables 1 through 3. The NMP1 P-T limit curves for 36 EFPY are provided in Figures 4 through 6, and a tabulation of the curves is included in Tables 4 through 6. The NMP1 P-T limit curves for 46 EFPY are provided in Figures 7 through 9, and a tabulation of the curves in included in Tables 7 through 9.

Page 2 of 41 PTLR-1 Revision 0

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 (Figures 1, 4 and 7: Curve A): _5250F/hour'.

• Normal Operating Heatup and Cooldown rate limit (Figures 2, 5 and 8: Curve B - non-nuclear heating, and Figures 3, 6 and 9: Curve C - nuclear heating): _5100°F/hour 2.

• RPV head installation temperature limit (Figures 1, 4 and 7: Curve A - Hydrostatic and Class 1 Leak Testing; Figures 2, 5 and 8: Curve B - non-nuclear heating): _ 70F 3 .

• RPV flange and adjacent shell temperature limit: _ 70°F.

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 1.190 (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 1 Interpreted as: The temperature change in any 1-hour period is less than or equal to 25°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.

Page 3 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report 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 10 17 and 1.05 x 1018 n/cm 2, respectively, for NMP1.

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 _<10 0 F/hr. 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"F/hr 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 ifthe pressure test heatup/cooldown rate limits cannot be maintained.

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 Tables 10, 11, and 12 for 28, 36 and 46 EFPY, respectively (Reference 6.7). 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 RTNDTvalues shown in Page 4 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Tables 10, 11, and 12 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 (oA = 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 NMP1 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 NMP1 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:

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 4500°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 Page 5 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report heatup/cooldown limits associated with the P-T curves for the upper vessel feedwater nozzle region.

• 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 13 (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 10) 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 14) to conservatively bound the 1000 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.

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.

Page 6 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report

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-1900, "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. MC1 758 and MC1 759)."

19. G.E. Drawing No. 237E434, "Loadings Reactor Vessel."

Page 7 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 1: NMP1 Pressure Test (Curve A), 28 EFPY 1,900 1,800 1,700 1,600 1,500 "5,400 a.

UJ,300 co P,200

• ,100-V,000 z-

• - 900

" 800 LU D) 700 LU W 600 Beltline Region 500

- -. Bottom Head 400

............ Upper Vessel 300 Bolt-up 200 Temp:

70°F 100 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)

Page 8 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 2: NMP1 Normal Operation (Heatup and Cooldown) -

Core Not Critical (Curve B), 28 EFPY 1,900 1,800 1,700 1,600 1,500 a,400 W,300 U)

,200 0

0,100 w

C,000 -

z I- 900-goo w 800 u) 700 u)

d. 600 Beltline Region 500 -

- -. Bottom Head 400 Bolt-up ............ Upper Vessel 300 Temp:

70°F 200 100 -

0-0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)

Page 9 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 3: NMP1 Normal Operation (Heatup and Cooldown) -

Core Critical (Curve C), 28 EFPY 1,900 1,800 1,700 1,600 1,500 1*,400 0.

[J,300 u4,,200 q,100 5,000 900

- 800 uJ U) 700 U) uJ 0., 600 500 400 300 Criticality:

IMinimum 100°F 200 100 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Page 10 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 4: NMP1 Pressure Test (Curve A), 36 EFPY 1,900 1,800 1,700 1,600 1,500

.ý,400 0.

J,300 U,

U,200 Q,100 I.-

U1,000 z

_900

-M 800 LU 700 U,

uJ Wv600 600 Beltline Region 500

- - -Bottom Head 400

............ Upper Vessel 300 Bolt-up Temp:

200 70OF 100 0i 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)

Page 11 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 5: NMP1 Normal Operation (Heatup and Cooldown) -

Core Not Critical (Curve B), 36 EFPY 1,900 1,800 1,700 1,600 1,500

,1,400 0.

E,300 Co I4,,200 C1,100 L~,oo

~,000 z

900

" 800 ILJ 700 LU W

0. 600 Beltline Region 500

- - - BottomHead 400 Bolt-up Temp: ............ Upper Vessel 300 70°F 200 100 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)

Page 12 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 6: NMP1 Normal Operation (Heatup and Cooldown) -

Core Critical (Curve C), 36 EFPY 1,900 1,800 1,700 1,600 1,500

.1,400 CL

[J,300 U,

L,,,200 p,100 5,000 z

900

" 800 LU.

U) 700 U,

n 600 500 400 300 Minimum 200 Criticality: .

100°F 100 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (-F)

Page 13 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 7: NMP1 Pressure Test (Curve A), 46 EFPY 1,900 1,800 1,700 1,600 1,500

.g,400 a3.

E,300 U)

U, Li,200 0,100 1,000 z

F- 900

" 800 LU U) 700 u)

W 600 Beltline Region 0.

500

- - Bottom Head 400 F

............ Upper Vessel 300 Bolt-up Temp:

70°F 200 100 0j 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (fF)

Page 14 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 8: NMP1 Normal Operation (Heatup and Cooldown) -

Core Not Critical (Curve B), 46 EFPY 1,900 1,800 1,700 1,600 1,500 0) a,400

_j o,300 U)

S,200 0

t,100 w

04,000 z

wU800 U) 700 UJ w

a. 600 Beltline Region 500

- -. Bottom Head 400

............ Upper Vessel 300 Bolt-up Temp:

200 70OF 100 0

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (TF)

Page 15 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 9: NMP1 Normal Operation (Heatup and Cooldown) -

Core Critical (Curve C), 46 EFPY 1,900 1,800 1,700 1,600 1,500

ýg,400 a.

J, 3 00 U) -

U)

L,,200 1,100 5,000 900

- 800 UJ U) 700 LU 600 500 400 300 200 100 0

I Minimum Criticality:

IO0°F 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 MINIMUM REACTOR VESSEL METAL TEMPERATURE (OF)

Page 16 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Figure 10: NMP1 Feedwater Nozzle Finite Element Model AN Feedwater Nozzle Finite Element Model Page 17 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 1: NMP1 Pressure Test (Curve A) - Beltline Region, 28 EFPY Plant = WWII.

Component = ýBeltline Vessel thickness, t = 7.125 inches Vessel Radius, R = 106.5 inches ART 151.4 °F =====> 28 EFPY Kit = 0 (no thermal effects)

Safety Factor = 1.5 M = 2.472 Temperature Adjustment: 4.0 *F (instrument uncertainty)

Pressure Adjustment - 27.7 psig (hydrostatic pressure head for a full vessel at 70°F)

Pressure Adjustment I1L 0.0 psig (instrument uncertainty)

Adjusted Gauge Fluid Temperature Pressure for Temperature K{m Gauge for P-T Curve P-T Curve (5F) KI, (ksi-Vin) (ksi-Vin) Pressure (psig) VF) (psig) 56 36.28 24.18 0 70 0 56 36.28 24.18 655 70 617 58 36.40 24.27 657 70 619 60 36.53 24.36 659 70 622 62 36.67 24.45 662 70 624 64 36.81 24.54 664 70 627 66 36.96 24.64 667 70 629 68 37.11 24.74 670 72 632 70 37.27 24.85 673 74 635 72 37.44 24.96 676 76 638 74 37.61 25.07 679 78 641 76 37.79 25.19 682 80 644 78 37.98 25.32 685 82 648 80 38.17 25.45 689 84 651 82 38.37 25.58 692 86 655 84 38.59 25.72 696 88 659 86 38.81 25.87 700 90 663 88 39.03 26.02 704 92 667 90 39.27 26.18 709 94 671 92 39.52 26.35 713 96 675 94 39.78 26.52 718 98 680 96 40.05 26.70 723 100 685 98 40.33 26.88 728 102 690 100 40.62 27.08 733 104 695 102 40.92 27.28 738 106 701 104 41.23 27.49 744 108 706 106 41.56 27.71 750 110 712 108 41.90 27.94 756 112 718 110 42.26 28.17 763 114 725 112 42.63 28.42 769 116 732 114 43.01 28.68 776 118 738 116 43.41 28.94 783 120 746 118 43.83 29.22 791 122 753 120 44.26 29.51 799 124 761 122 44.72 29.81 807 126 769 124 45.19 30.12 815 128 778 126 45.68 30.45 824 130 787 128 46.18 30.79 833 132 796 130 46.71 31.14 843 134 805 132 47.27 31.51 853 136 815 134 47.84 31.89 863 138 826 136 48.44 32.29 874 140 836 138 49.06 32.71 885 142 848 140 49.71 33.14 897 144 859 Page 18 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 1 (Continued)

Adjusted Gauge Fluid Temperature Pressure for Temperature K. Gauge for P-T Curve P-T Curve

(°F) C(ksi-Vin) (ksi-Vin) Pressure (psig) (*F) (psig) 142 50.38 33.59 909 146 871 144 51.08 34.05 922 148 884 146 51.81 34.54 935 150 897 148 52.57 35.05 949 152 911 150 53.36 35.57 963 154 925 152 54.18 36.12 978 156 940 154 55.04 36.69 993 158 956 156 55.93 37.29 1009 160 972 158 56.86 37.91 1026 162 988 160 57.83 38.55 1043 164 1006 162 58.83 39.22 1062 166 1024 164 59.88 39.92 1080 168 1043 166 60.96 40.64 1100 170 1062 168 62.10 41.40 1121 172 1083 170 63.28 42.18 1142 174 1104 172 64.50 43.00 1164 176 1126 174 65.78 43.85 1187 178 1149 176 67.11 44.74 1211 180 1173 178 68.50 45.66 1236 182 1198 180 69.94 46.62 1262 184 1224 182 71.44 47.62 1289 186 1251 184 73.00 48.66 1317 188 1280 186 74.62 49.75 1346 190 1309 188 76.31 50.87 1377 192 1339 190 78.07 52.05 1409 194 1371 192 79.90 53.27 1442 196 1404 194 81.81 54.54 1476 198 1438 196 83.79 55.86 1512 200 1474 198 85.86 57.24 1549 202 1512 200 88.00 58.67 1588 204 1550 202 90.24 60.16 1628 206 1591 204 92.57 61.71 1670 208 1633 206 94.99 63.33 1714 210 1676 208 97.51 65.01 1760 212 1722 210 100.14 66.76 1807 214 1769 212 102.87 68.58 1856 216 1819 214 105.71 70.48 1908 218 1870 216 108.67 72.45 1961 220 1923 Page 19 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 2: NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region, 28 EFPY Plant =F, NMP1 Component = Beltline Vessel thickness, t = 7.125 inches Vessel Radius, R = 106.5 inches ART = 151.4 °F =====> 28 EFPY Kit =

12.91 ksi??in Safety Factor = 2.0 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 Adjusted Gauge Fluid Temperature Pressure for Temperature Kim Gauge for P-T Curve P-T Curve

(*F) K3. (ksi-Vin) (ksi-Vin) Pressure (psig) ('F) (psig) 48 35.82 11.45 310 70 0 48 35.82 11.45 310 70 230 50 35.93 11.51 311 70 232 52 36.04 11.56 313 70 233 54 36.16 11.62 315 70 235 56 36.28 11.68 316 70 236 58 36.40 11.74 318 70 238 60 36.53 11.81 320 72 240 62 36.67 11.88 321 74 242 64 36.81 11.95 323 76 244 66 36.96 12.02 325 78 246 68 37.11 12.10 327 80 248 70 37.27 12.18 330 82 250 72 37.44 12.26 332 84 252 74 37.61 12.35 334 86 254 76 37.79 12.44 337 88 257 78 37.98 12.53 339 90 259 80 38.17 12.63 342 92 262 82 38.37 12.73 345 94 265 84 38.59 12.84 347 96 268 86 38.81 12.95 350 98 271 88 39.03 13.06 353 100 274 90 39.27 13.18 357 102 277 92 39.52 13.30 360 104 280 94 39.78 13.43 364 106 284 96 40.05 13.57 367 108 287 98 40.33 13.71 371 110 291 100 40.62 13.85 375 112 295 102 40.92 14.00 379 114 299 104 41.23 14.16 383 116 303 106 41.56 14.32 388 118 308 108 41.90 14.50 392 120 312 110 42.26 14.67 397 122 317 112 42.63 14.86 402 124 322 114 43.01 15.05 407 126 327 116 43.41 15.25 413 128 333 118 43.83 15.46 418 130 339 120 44.26 15.68 424 132 344 122 44.72 15.90 430 134 351 124 45.19 16.14 437 136 357 126 45.68 16.38 443 138 364 128 46.18 16.64 450 140 370 130 46.71 16.90 457 142 378 132 47.27 17.18 465 144 385 134 47.84 17.46 473 146 393 136 48.44 17.76 481 148 401 138 49.06 18.07 489 150 409 140 49.71 18.40 498 152 418 Page 20 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 2 (Continued)

Adjusted Gauge Fluid Temperature Pressure for Temperature Kim Gauge for P-T Curve P-T Curve

(°F) Kic (ksi-Vin) (ksi-Vin) Pressure (psig) (°F) (psig) 142 50.38 18.73 507 154 427 144 51.08 19.08 517 156 437 146 51.81 19.45 526 158 447 148 52.57 19.83 537 160 457 150 53.36 20.22 547 162 468 152 54.18 20.64 559 164 479 154 55.04 21.06 570 166 490 156 55.93 21.51 582 168 502 158 56.86 21.97 595 170 515 160 57.83 22.46 608 172 528 162 58.83 22.96 621 174 542 164 59.88 23.48 636 176 556 166 60.96 24.03 650 178 570 168 62.10 24.59 666 180 586 170 63.28 25.18 682 182 602 172 64.50 25.80 698 184 618 174 65.78 26.43 715 186 636 176 67.11 27.10 733 188 654 178 68.50 27.79 752 190 672 180 69.94 28.51 772 192 692 182 71.44 29.26 792 194 712 184 73.00 30.04 813 196 733 186 74.62 30.85 835 198 755 188 76.31 31.70 858 200 778 190 78.07 32.58 882 202 802 192 79.90 33.49 907 204 827 194 81.81 34.45 932 206 852 196 83.79 35.44 959 208 879 198 85.86 36.47 987 210 907 200 88.00 37.55 1016 212 936 202 90.24 38.66 1046 214 967 204 92.57 39.83 1078 216 998 206 94.99 41.04 1111 218 1031 208 97.51 42.30 1145 220 1065 210 100.14 43.61 1180 222 1101 212 102.87 44.98 1217 224 1138 214 105.71 46.40 1256 226 1176 216 108.67 47.88 1296 228 1216 218 111.75 49.42 1338 230 1258 220 114.96 51.02 1381 232 1301 222 118.30 52.69 1426 234 1346 224 121.77 54.43 1473 236 1393 226 125.38 56.23 1522 238 1442 228 129.14 58.12 1573 240 1493 230 133.06 60.07 1626 242 1546 232 137.14 62.11 1681 244 1601 234 141.38 64.23 1739 246 1659 236 145.79 66.44 1798 248 1718 238 150.39 68.74 1860 250 1781 240 155.17 71.13 1925 252 1845 242 160.15 73.62 1993 254 1913 Page 21 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Table 3: NMP1 Normal Operation - Core Critical (Curve C), 28 EFPY Plant = NMP1 Curve A Leak Test Temperature = 169.2 'F Curve A Leak Test Pressure = 1,055 psig Unit Pressure = 1,875 psig (hydrostatic pressure)

Flange RTNDT = 40.0 PF Adjusted P-T Adjusted P-T Curve Curve Temperature Pressure (psig)

(°F) 100 0 100 113 102 119 104 122 106 126 108 131 110 136 112 141 114 147 116 153 118 159 120 165 122 172 124 179 126 186 128 194 130 202 132 210 134 219 136 228 138 238 140 248 142 259 144 270 146 281 148 287 150 291 152 295 154 299 156 303 158 308 160 312 162 317 164 322 166 327 168 333 170 339 172 344 174 351 176 357 178 364 180 370 182 375 184 375 186 375 188 375 190 375 Page 22 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Table 3 (Continued)

Adjusted P-T curveAdjusted PoT Curve P ure Temperature

(°F) Pressure (psig) 192 375 194 375 196 375 198 375 200 375 200 457 202 468 204 479 206 490 208 502 210 515 212 528 214 542 216 556 218 570 220 586 222 602 224 618 226 636 228 654 230 672 232 692 234 712 236 733 238 755 240 778 242 802 244 827 246 852 248 879 250 907 252 936 254 967 256 998 258 1031 260 1065 262 1101 264 1138 266 1176 268 1216 270 1258 272 1301 274 1346 276 1393 278 1442 280 1493 282 1546 284 1601 286 1659 288 1718 290 1781 292 1845 294 1913 Page 23 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 4: NMPI Pressure Test (Curve A) - Beltline Region, 36 EFPY Plant -*j MPI,'

Component ,Beltline :

Vessel thickness, t 7' 1.125 - inches Vessel Radius, R = 106.5 inches ART 159.0 'F =====> 36 EFPY (no thermal effects)

Safety Factor 1 5 Temperature Adjustment 4 0 *F (instrument uncertainty)

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

Pressure Adjustment "10;0 psig (instrument uncertainty)

Adjusted Gauge Fluid Temperature Pressure for Temperature KIm Gauge for P-T Curve P-T Curve (5F6 3, (ksi-4in) (ksi-Vin) Pressure (psig) (F) (psig) 56 35.84 23.90 0 70 0 56 35.84 23.90 647 70 609 58 35.95 23.97 649 70 611 60 36.06 24.04 651 70 613 62 36.18 24.12 653 70 615 64 36.30 24.20 655 70 617 66 36.43 24.29 657 70 620 68 36.56 24.37 660 72 622 70 36.70 24.46 662 74 625 72 36.84 24.56 665 76 627 74 36.99 24.66 667 78 630 76 37.14 24.76 670 80 633 78 37.30 24.87 673 82 635 80 37.47 24.98 676 84 638 82 37.64 25.10 679 86 642 84 37.83 25.22 683 88 645 86 38.02 25.34 686 90 648 88 38.21 25.47 690 92 652 90 38.42 25.61 693 94 656 92 38.63 25.75 697 96 659 94 38.85 25.90 701 98 663 96 39.08 26.05 705 100 668 98 39.32 26.21 710 102 672 100 39.57 26.38 714 104 676 102 39.83 26.55 719 106 681 104 40.10 26.73 724 108 686 106 40.38 26.92 729 110 691 108 40.68 27.12 734 112 696 110 40.98 27.32 739 114 702 112 41.30 27.53 745 116 708 114 41.63 27.75 751 118 714 116 41.97 27.98 757 120 720 118 42.33 28.22 764 122 726 120 42.70 28.47 771 124 733 122 43.09 28.73 778 126 740 124 43.50 29.00 785 128 747 126 43.92 29.28 792 130 755 128 44.35 29.57 800 132 763 130 44.81 29.87 809 134 771 132 45.28 30.19 817 136 779 134 45.78 30.52 826 138 788 136 46.29 30.86 835 140 798 138 46.82 31.22 845 142 807 140 47.38 31.59 855 144 817 Page 24 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Table 4 (Continued)

Adjusted Gauge Fluid Temperature Pressure for Temperature Klm Gauge for P-T Curve P-T Curve

(°F) (°F)

Kc (ksi-Vin) (ksi-Vin) Pressure (psig) (psig) 142 47.96 31.97 865 146 828 144 48.56 32.37 876 148 839 146 49.19 32.79 888 150 850 148 49.84 33.23 899 152 862 150 50.52 33.68 912 154 874 152 51.23 34.15 924 156 887 154 51.96 34.64 938 158 900 156 52.73 35.15 951 160 914 158 53.52 35.68 966 162 928 160 54.35 36.24 981 164 943 162 55.22 36.81 996 166 959 164 56.11 37.41 1013 168 975 166 57.05 38.03 1029 170 992 168 58.02 38.68 1047 172 1009 170 59.04 39.36 1065 174 1028 172 60.09 40.06 1084 176 1047 174 61.19 40.79 1104 178 1066 176 62.33 41.55 1125 180 1087 178 63.52 42.35 1146 182 1108 180 64.76 43.17 1168 184 1131 182 66.04 44.03 1192 186 1154 184 67.38 44.92 1216 188 1178 186 68.78 45.85 1241 190 1203 188 70.23 46.82 1267 192 1230 190 71.74 47.83 1295 194 1257 192 73.32 48.88 1323 196 1285 194 74.95 49.97 1352 198 1315 196 76.66 51.10 1383 200 1346 198 78.43 52.29 1415 202 1378 200 80.28 53.52 1449 204 1411 202 82.20 54.80 1483 206 1446 204 84.20 56.13 1519 208 1482 206 86.28 57.52 1557 210 1519 208 88.44 58.96 1596 212 i558 210 90.70 60.47 1637 214 1599 212 93.05 62.03 1679 216 1641 214 95.49 63.66 1723 218 1685 216 98.03 65.35 1769 220 1731 218 100.68 67.12 1817 222 1779 220 103.43 68.95 1866 224 1829 222 106.30 70.86 1918 226 1880 224 109.28 72.85 1972 228 1934 Page 25 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 5: NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region, 36 EFPY Plant =

Component = Beltllne K Vessel thickness, t = 7.125 inches Vessel Radius, R = 106.5 inches ART = 159.0 °F =====> 36 EFPY Kit = 12.91 ksi??in Safety Factor = 2.0 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 Adjusted Gauge Fluid Temperature Pressure for Kim Temperature Gauge for P-T Curve P-T Curve (F) KI, (ksi-Vin) (ksi-Vin) Pressure (psig) (*F) (psig) 48 35.45 11.27 305 70 0 48 11.27 70 3S.45 305 225 50 35.54 11.31 306 70 226 52 35.64 11.36 308 70 228 54 35.74 11.41 309 70 229 56 35.84 11.46 310 70 230 58 35.95 11.52 312 70 232 60 36.06 11.57 313 72 233 62 36.18 11.63 315 74 235 64 36.30 11.69 317 76 237 66 36.43 11.76 318 78 238 68 36.56 11.82 320 80 240 70 36.70 11.89 322 82 242 72 36.84 11.96 324 84 244 74 36.99 12.04 326 86 246 76 37.14 12.11 328 88 248 78 37.30 12.19 330 90 250 80 37.47 12.28 332 92 2S2 82 37.64 12.37 335 94 255 84 37.83 12.46 337 96 257 86 38.02 12.55 340 98 260 88 38.21 12.65 342 100 263 90 38.42 12.75 345 102 265 92 38.63 12.86 348 104 268 94 38.85 12.97 351 106 271 96 39.08 13.08 354 108 274 98 39.32 13.20 357 110 278 100 39.57 13.33 361 112 281 102 39.83 13.46 364 114 284 104 40.10 13.59 368 116 288 106 40.38 13.73 372 118 292 108 40.68 13.88 376 120 296 110 40.98 14.03 380 122 300 112 41.30 14.19 384 124 304 114 41.63 14.36 389 126 309 116 41.97 14.53 393 128 313 118 42.33 14.71 398 130 318 120 42.70 14.90 403 132 323 122 43.09 15.09 408 134 329 124 43.50 15.29 414 136 334 126 43.92 15.50 420 138 340 128 44.35 15.72 425 140 346 130 44.81 15.95 432 142 352 132 45.28 16.18 438 144 358 134 45.78 16.43 445 146 365 136 46.29 16.69 452 148 372 138 46.82 16.95 459 150 379 140 47.38 17.23 466 152 387 Page 26 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 5 (Continued)

Adjusted Gauge Fluid Temperature Pressure for Temperature Klm Gauge for P-T Curve P-T Curve

('F)

KIc (ksi- Vin) (ksi-Vin) Pressure (psig) ('F) (psig) 142 47.96 17.52 474 154 394 144 48.56 17.82 482 156 403 146 49.19 18.14 491 158 411 148 49.84 18.46 500 160 420 150 50.52 18.80 509 162 429 152 51.23 19.16 518 164 439 154 51.96 19.52 528 166 449 156 52.73 19.91 539 168 459 158 53.52 20.30 550 170 470 160 54.35 20.72 561 172 481 162 55.22 21.15 572 174 493 164 56.11 21.60 585 176 505 166 57.05 22.07 597 178 517 168 58.02 22.55 610 180 531 170 59.04 23.06 624 182 544 172 60.09 23.59 638 184 559 174 61.19 24.14 653 186 573 176 62.33 24.71 669 188 589 178 63.52 25.30 685 190 605 180 64.76 25.92 702 192 622 182 66.04 26.57 719 194 639 184 67.38 27.24 737 196 657 186 68.78 27.93 756 198 676 188 70.23 28.66 776 200 696 190 71.74 29.41 796 202 716 192 73.32 30.20 817 204 738 194 74.95 31.02 840 206 760 196 76.66 31.87 863 208 783 198 78.43 32.76 887 210 807 200 80.28 33.68 912 212 832 202 82.20 34.64 938 214 858 204 84.20 35.64 965 216 885 206 86.28 36.68 993 218 913 208 88.44 37.77 1022 220 942 210 90.70 38.89 1053 222 973 212 93.05 40.07 1084 224 1005 214 95.49 41.29 1118 226 1038 216 98.03 42.56 1152 228 1072 218 100.68 43.88 1188 230 1108 220 103.43 45.26 1225 232 1145 222 106.30 46.69 1264 234 1184 224 109.28 48.18 1304 236 1224 226 112.38 49.74 1346 238 1266 228 115.62 51.35 1390 240 1310 230 118.98 53.03 1435 242 1356 232 122.48 54.78 1483 244 1403 234 126.12 56.60 1532 246 1452 236 129.92 58.50 1583 248 1504 238 133.86 60.47 1637 250 1557 240 137.97 62.53 1692 252 1613 242 142.25 64.67 1750 254 1670 244 146.70 66.89 1811 256 1731 246 .151.33 69.21 1873 258 1793 248 156.15 71.62 1938 260 1859 250 161.17 74.13 2006 262 1926 Page 27 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 6: NMP1 Normal Operation - Core Critical (Curve C), 36 EFPY Plant = NMP1 Curve A Leak Test Temperature = 176.8 -F Curve A Leak Test Pressure = 1,055 psig Unit Pressure = 1,875 psig (hydrostatic pressure)

Flange RTNDT =1 40.0 -F Adjusted Curve poT Adjusted P-T Curve Temperature Pressure (psig)

(°F) 100 0 100 113 102 119 104 122 106 126 108 131 110 136 112 141 114 147 116 153 118 159 120 165 122 172 124 179 126 186 128 194 130 202 132 210 134 219 136 228 138 238 140 248 142 259 144 268 146 271 148 274 150 278 152 281 154 284 156 288 158 292 160 296 162 300 164 304 166 309 168 313 170 318 172 323 174 329 176 334 178 340 180 346 182 352 184 358 186 365 188 372 190 375 Page 28 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 6 (Continued)

Adjusted P-T Adjusted P-T Curve Curve Temperature Pressure (psig)

(°F) 192 375 194 375 196 375 198 375 200 375 200 420 202 429 204 439 206 449 208 459 210 470 212 481 214 493 216 505 218 517 220 531 222 544 224 559 226 573 228 589 230 605 232 622 234 639 236 657 238 676 240 696 242 716 244 738 246 760 248 783 250 807 252 832 254 858 256 885 258 913 260 942 262 973 264 1005 266 1038 268 1072 270 1108 272 1145 274 1184 276 1224 278 1266 280 1310 282 1356 284 1403 286 1452 288 1504 290 1557 292 1613 294 1670 296 1731 298 1793 300 1859 302 1926 Page 29 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 7: NMPI Pressure Test (Curve A) - Beltline Region, 46 EFPY Plant WNMP1 r Component 1eline Vessel thickness, t 7:125 inches Vessel Radius, R: .106.5 inches ART 167-4 'F =====> 46 EFPY Kit 1;0 (no thermal effects)

Safety Factor 1.5 Mm 2.472 Temperature Adjustment = 4.0 'F (instrument uncertainty)

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

Pressure Adjustment 10.0 psig (instrument uncertainty)

Adjusted Gauge Fluid Temperature Pressure for Temperature Khm Gauge for P-T Curve P-T Curve 56 (ksi-3in) (ksi-Vin) Pressure (psig) (*F) (psig) 56 35.43 23.62 0 70 0 35.43 23.62 639 70 602 58 35.53 23.68 641 70 603 60 35.62 23.75 643 70 605 62 35.72 23.81 645 70 607 64 35.82 23.88 646 70 609 66 35.93 23.95 648 70 611 68 36.04 24.03 650 72 613 70 36.16 24.10 652 74 615 72 36.28 24.18 655 76 617 74 36.40 24.27 657 78 619 76 36.53 24.36 659 80 622 78 36.67 24.45 662 82 624 80 36.81 24.54 664 84 627 82 36.96 24.64 667 86 629 84 37.11 24.74 670 88 632 86 37.27 24.85 673 90 635 88 37.44 24.96 676 92 638 90 37.61 25.07 679 94 641 92 37.79 25.19 682 96 644 94 37.98 25.32 685 98 648 96 38.17 25.45 689 100 651 98 38.37 25.58 692 102 655 100 38.59 25.72 696 104 659 102 38.81 25.87 700 106 663 104 39.03 26.02 704 108 667 106 39.27 26.18 709 110 671 108 39.52 26.35 713 112 675 110 39.78 26.52 718 114 680 112 40.05 26.70 723 116 685 114 40.33 26.88 728 118 690 116 40.62 27.08 733 120 695 118 40.92 27.28 738 122 701 120 41.23 27.49 744 124 706 122 41.56 27.71 750 126 712 124 41.90 27.94 756 128 718 126 42.26 28.17 763 130 725 128 42.63 28.42 769 132 732 130 43.01 28.68 776 134 738 132 43.41 28.94 783 136 746 134 43.83 29.22 791 138 753 136 44.26 29.51 799 140 761 138 44.72 29.81 807 142 769 140 45.19 30.12 815 144 778 Page 30 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 7 (Continued)

Adjusted Gauge Fluid Temperature Pressure for Temperature KIm Gauge for P-T Curve P-T Curve

(*F) Kc (ksi-Vin) (ksi-Vin) Pressure (psig) ('F) (psig) 142 45.68 30.45 824 146 787 144 46.18 30.79 833 148 796 146 46.71 31.14 843 150 805 148 47.27 31.51 853 152 815 150 47.84 31.89 863 154 826 152 48.44 32.29 874 156 836 154 49.06 32.71 885 158 848 156 49.71 33.14 897 160 859 158 50.38 33.59 909 162 871 160 51.08 34.05 922 164 884 162 51.81 34.54 935 166 897 164 52.57 35.05 949 168 911 166 53.36 35.57 963 170 925 168 54.18 36.12 978 172 940 170 55.04 36.69 993 174 956 172 55.93 37.29 1009 176 972 174 56.86 37.91 1026 178 988 176 57.83 38.55 1043 180 1006 178 58.83 39.22 1062 182 1024 180 59.88 39.92 1080 184 1043 182 60.96 40.64 1100 186 1062 184 62.10 41.40 1121 188 1083 186 63.28 42.18 1142 190 1104 188 64.50 43.00 1164 192 1126 190 65.78 43.85 1187 194 1149 192 67.11 44.74 1211 196 1173 194 68.50 45.66 1236 198 1198 196 69.94 46.62 1262 200 1224 198 71.44 47.62 1289 202 1251 200 73.00 48.66 1317 204 1280 202 74.62 49.75 1346 206 1309 204 76.31 50.87 1377 208 1339 206 78.07 52.05 1409 210 1371 208 79.90 53.27 1442 212 1404 210 81.81 54.54 1476 214 1438 212 83.79 55.86 1512 216 1474 214 85.86 57.24 1549 218 1512 216 88.00 58.67 1588 220 1550 218 90.24 60.16 1628 222 1591 220 92.57 61.71 1670 224 1633 222 94.99 63.33 1714 226 1676 224 97.51 65.01 1760 228 1722 226 100.14 66.76 1807 230 1769 228 102.87 68.58 1856 232 1819 230 105.71 70.48 1908 234 1870 232 108.67 72.45 1961 236 1923 Page 31 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Table 8: NMP1 Normal Operation - Core Not Critical (Curve B), Beltline Region, 46 EFPY Plant = ! -<N-MP1 -*

Component = BeltIlne Vessel thickness, t = 7.125. inches Vessel Radius, R = 10615 inches ART = 167.4 'F =====> 46 EFPY o12:91/

Kit = ksi??in Safety Factor =

Mm= 4.2.72 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 Adjusted Gauge Fluid Temperature Pressure for Temperature Kim Gauge for P-T Curve P-T Curve

(°F) Kkc (ksi-Vin) (ksi-Vin) Pressure (psig) ('F) (psig) 48 35.10 11.09 300 70 0 48 35.10 11.09 220 300 70 50 35.18 11.13 301 70 221 52 35.26 11.17 302 70 223 54 35.35 11.22 304 70 224 56 35.43 11.26 305 70 225 58 35.53 11.31 306 70 226 60 35.62 11.35 307 72 227 62 35.72 11.40 309 74 229 64 35.82 11.45 310 76 230 66 35.93 11.51 311 78 232 68 36.04 11.56 313 80 233 70 36.16 11.62 315 82 235 72 36.28 11.68 316 84 236 74 36.40 11.74 318 86 238 76 36.53 11.81 320 88 240 78 36.67 11.88 321 90 242 80 36.81 11.95 323 92 244 82 36.96 12.02 325 94 246 84 37.11 12.10 327 96 248 86 37.27 12.18 330 98 250 88 37.44 12.26 332 100 2S2 90 37.61 12.35 334 102 254 92 37.79 12.44 337 104 257 94 37.98 12.53 339 106 2S9 96 38.17 12.63 342 108 262 98 38.37 12.73 345 110 265 100 38.59 12.84 347 112 268 102 38.81 12.95 350 114 271 104 39.03 13.06 353 116 274 106 39.27 13.18 357 118 277 108 39.52 13.30 360 120 280 110 39.78 13.43 364 122 284 112 40.05 13.57 367 124 287 114 40.33 13.71 371 126 291 116 40.62 13.85 375 128 295 118 40.92 14.00 379 130 299 120 41.23 14.16 383 132 303 122 41.56 14.32 388 134 308 124 41.90 14.50 392 136 312 126 42.26 14.67 397 138 317 128 42.63 14.86 402 140 322 130 43.01 15.05 407 142 327 132 43.41 15.25 413 144 333 134 43.83 15.46 418 146 339 136 44.26 15.68 424 148 344 138 44.72 15.90 430 150 3S1 140 45.19 16.14 437 152 357 Page 32 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 8 (Continued)

Adjusted Gauge Fluid Temperature Pressure for Temperature Km Gauge for P-T Curve P-T Curve

('F) K,, (ksi-Vin) (ksi-Vin) Pressure (psig) (F) (psig) 142 45.68 16.38 443 154 364 144 46.18 16.64 450 156 370 146 46.71 16.90 457 158 378 148 47.27 17.18 465 160 385 150 47.84 17.46 473 162 393 152 48.44 17.76 481 164 401 154 49.06 18.07 489 166 409 156 49.71 18.40 498 168 418 158 50.38 18.73 507 170 427 160 51.08 19.08 517 172 437 162 51.81 19.45 526 174 447 164 52.57 19.83 537 176 457 166 53.36 20.22 547 178 468 168 54.18 20.64 559 180 479 170 55.04 21.06 570 182 490 172 55.93 21.51 582 184 502 174 56.86 21.97 595 186 515 176 57.83 22.46 608 188 528 178 58.83 22.96 621 190 542 180 59.88 23.48 636 192 556 182 60.96 24.03 650 194 570 184 62.10 24.59 666 196 586 186 63.28 25.18 682 198 602 188 64.50 25.80 698 200 618 190 65.78 26.43 715 202 636 192 67.11 27.10 733 204 654 194 68.50 27.79 752 206 672 196 69.94 28.51 772 208 692 198 71.44 29.26 792 210 712 200 73.00 30.04 813 212 733 202 74.62 30.85 835 214 755 204 76.31 31.70 858 216 778 206 78.07 32.58 882 218 802 208 79.90 33.49 907 220 827 210 81.81 34.45 932 222 852 212 83.79 35.44 959 224 879 214 85.86 36.47 987 226 907 216 88.00 37.55 1016 228 936 218 90.24 38.66 1046 230 967 220 92.57 39.83 1078 232 998 222 94.99 41.04 1111 234 1031 224 97.51 42.30 1145 236 1065 226 100.14 43.61 1180 238 1101 228 102.87 44.98 1217 240 1138 230 105.71 46.40 1256 242 1176 232 108.67 47.88 1296 244 1216 234 111.75 49.42 1338 246 1258 236 114.96 51.02 1381 248 1301 238 118.30 52.69 1426 250 1346 240 121.77 54.43 1473 252 1393 242 125.38 56.23 1522 254 1442 244 129.14 58.12 1573 256 1493 246 133.06 60.07 1626 258 1546 248 137.14 62.11 1681 260 1601 250 141.38 64.23 1739 262 1659 252 145.79 66.44 1798 264 1718 254 150.39 68.74 1860 266 1781 256 155.17 71.13 1925 268 1845 258 160.15 73.62 1993 270 1913 Page 33 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 9: NMPI Normal Operation - Core Critical (Curve C), 46 EFPY Plant NMP1.

Curve A Leak Test Temperature = 185.2 'F Curve A Leak Test Pressure = .1,055 psig Unit Pressure = 1,875 psig (hydrostatic pressure)

Flange RTNDT= 40.0 -

Adjusted P-T Adjusted P-T Curve

.Curve Temperature Pressure (psig)

(°F) 100 0 100 113 102 119 104 122 106 126 108 131 110 136 112 141 114 147 116 153 118 159 120 165 122 172 124 179 126 186 128 194 130 202 132 210 134 219 136 228 138 238 140 248 142 254 144 257 146 259 148 262 150 265 152 268 154 271 156 274 158 277 160 280 162 284 164 287 166 291 168 295 170 299 172 303 174 308 176 312 178 317 180 322 182 327 184 333 186 339 188 344 190 351 192 357 194 364 196 370 198 375 200 375 Page 34 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Table 9 (Continued)

Adjusted P-T Curve Adjusted P-T Curve Temperature Pressure (psig)

(*F) 200 385 202 393 204 401 206 409 208 418 210 427 212 437 214 447 216 457 218 468 220 479 222 490 224 502 226 515 228 528 230 542 232 556 234 570 236 586 238 602 240 618 242 636 244 654 246 672 248 692 250 712 252 733 254 755 256 778 258 802 260 827 262 852 264 879 266 907 268 936 270 967 272 998 274 1031 276 1065 278 1101 280 1138 282 1176 284 1216 286 1258 288 1301 290 1346 292 1393 294 1442 296 1493 298 1546 300 1601 302 1659 304 1718 306 1781 308 1845 310 1913 Page 35 of 41 PTLR-1 Revision 0

NMPI Pressure and Temperature Limits Report Table 10: NMP1 ART Calculations for 28 EFPY Upper Shell Plate G-307-3 P2074 28 0.2 0.48 134.6 57.7 0 17 119.7 Upper Shell Plate G-307-4 P2076 40 0.27 0.53 173.85 74.6 0 17 148.6 a)

.6~

'U Upper Shell Plate G-307-10 P2091 20 0.22 0.51 148.85 63.8 0 17 117.8 K

Lower Shell Plate G-8-1 P2112 36 0.236 0.503 228.35 81.4 0 17 151.4 Lower Shell Plate. G-8-3/4 P2130A -3 0.176 0.586 146.8 52.3 0 8.5 66.3

-I P P 4 4 4 $

In Upper Shell Axial Welds 2-564A/C 86054B 4E5F -50 0.214 0.046 97.59 41.4 0 20.7 32.8 0

Lower Shell Axial Welds 2-564D/F 86054B 4E5F -50 0.214 0.046 97.59 34.6 0 17.3 19.3 Circumferential Weld Seam 3-564 1248 4M2F -50 0.214 0.076 99.9 35.6 0 17.8 21.2 Fluence at-1/4 T, f Fluence Factor, FF 2

(n/cm ) f(O.28-O101og f) -

Upper Shell Plate G-307-3 7.125 1.781 1.63E+18 0.652 1.06E+18 0.429 In Upper Shell Plate G-307-4 7.125 1.781 1.63E+18 0.652 1.06E+18 0.429 a'

.6~

'U Upper Shell Plate G-307-10 7.125 1.781 1.63E+18 0.652 1.06E+18 0.429 K

Lower Shell Plate G-8-1 7.125 1.781 1.12E+18 0.652 7.29E+17 0.357 Lower Shell Plate 1 G-8-3/4

- 1 7.125 1.781 1.12E+18 1 0.652 I 7.29E+17 I 0.357 Upper Shell Axial Welds 2-564A/C 7.125 1.781 1.59E+18 0.652 1.04E+18 0.424 Lower Shell Axial Welds 2-564D/F 7.125 1.781 1.11E+18 0.652 7.22E+17 0.355 Circumferential Weld Seam 3-564 7.125 1.781 1.12E+18 0.652 7.29E+17 0.357 Page 36 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 11: NMPI ART Calculations for 36 EFPY Adjustments for 1/4T r**:"*

" .. , .... " * " -" Flux Lot. 'Initial Flux.Lot Chemistry Description, Code-No. Heat No. RTNDT Chemistry Factor-(F) ARTNOT Margin Terms ARTNDT No.

0

_ ' ".... Cu (wt%) Ni (wt%) _ _(°F) o, (*F) A (F) (*F)

Upper Shell Plate G-307-3 P2074 - 28 0.2 0.48 134.6 63.5 0 17 125.5 Upper Shell Plate G-307-4 P2076 - 40 0.27 0.53 173.85 82.0 0 17 156.0 Upper Shell Plate G-307-10 P2091 - 20 0.22 0.51 148.85 70.2 0 17 124.2 0.

Lower Shell Plate G-8-1 P2112 - 36 0.236 0.503 228.35 89.0 0 17 159.0 Lower Shell Plate G-8-3/4 P2130A - -3 0.176 0.586 146.8 57.2 0 8.5 71.2 Upper Shell Axial Welds 2-564A/C 86054B 4ESF -50 0.214 0.046 97.59 45.5 0 22.8 41.1 Lower Shell Axial Welds 2-564D/F 86054B 4ESF -50 0.214 0.046 97.59 37.9 0 19.0 25.8 Circumferential Weld Seam 3-564 1248 4M2F -50 0.214 0.076 99.9 38.9 0 19.5 27.9

_______________... .___ Fluence Data Fluence at Location Wall Thickness (in) ID Attenuation Fluence at 1/4 T, f Fluence Factor, FF 2 2

:__ _ _ _Full 1/4 T (n/cm ) 1/4T = e-0.24x (n/cm ) f(O.28-0.10log f)

Upper Shell Plate G-307-3 7.125 1.781 2.OOE+18 0.652 1.30E+18 0.472 Upper Shell Plate G-307-4 7.125 1.781 2.OOE+18 0.652 1.30E+18 0.472 Upper Shell Plate G-307-10 7.125 1.781 2.OOE+18 0.652 1.30E+18 0.472 Lower Shell Plate G-8-1 7.125 1.781 1.34E+18 0.652 8.71E+17 0.390 Lower Shell Plate G-8-3/4 7.125 1.781 1.34E+18 0.652 8.71E+17 0.390 Upper Shell Axial Welds 2-564A/C 7.125 1.781 1.95E+18 0.652 1.27E+18 0.467 Lower Shell Axial Welds 2-564D/F 7.125 1.781 1.33E+18 0.652 8.65E+17 0.388 Circumferential Weld Seam 3-564 7.125 1.781 1.34E+18 0.652 8.71E+17 0.390 Page 37 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 12: NMP1 ART Calculations for 46 EFPY Adjustm-ents for 1/4T,

• * ...... "* . .. * *; .... .. LInitial

- - .. - Flux Lot Chemistry Descrpton ........ .Code o. HRTNDT Chemistry FactorT(F) :TNOT Margin.,Terms

.... .N o. (F... o r_(_F ) _ __Ct ARTNDT

____ ____ ___ __......___ _ _ .... I"C u (w t%) Ni fw t%)6

. ._ (F) a (;F) (F) ( F)

Upper Shell Plate G-307-3 P2074 - 28 0.2 0.48 134.6 69.7 0 17 131.7 Upper Shell Plate G-307-4 P2076 - 40 0.27 0.53 173.85 90.0 0 17 164.0 4.1 Upper Shell Plate G-307-10 P2091 - 20 0.22 0.51 148.85 77.0 0 17 131.0 Lower Shell Plate G-8-1 P2112 - 36 0.236 0.503 228.35 97.4 0 17 167.4 Lower Shell Plate G-8-3/4 P2130A - -3 0.176 0.586 146.8 62.6 0 8.5 76.6 Upper Shell Axial Welds 2-564A/C 86054B 4E5F -50 0.214 0.046 97.59 50.0 0 25.0 50.0 Lower Shell Axial Welds 2-564D/F 86054B 4E5F -50 0.214 0.046 97.59 41.5 0 20.8 33.0 Circumferential Weld Seam 3-564 1248 4M2F -50 0.214 0.076 99.9 42.6 0 21.3 35.2 Fluence.Data.

OFlu~ence a Location Wall Thickness (in) ID Attenuation Fluence at 1/4 T,f Fluence Factor, FF 2 2

. Full 1/4 T (n/cm ) 1/4T = e-O.24x (n/cm ) " f(O.28-O.lOlog f)

Upper Shell Plate G-307-3 7.125 1.781 2.46E+18 0.652 1.60E+18 0.518 Upper Shell Plate G-307-4 7.125 1.781 2.46E+18 0.652 1.60E+18 0.518 Upper Shell Plate G-307-10 7.125 1.781 2.46E+18 0.652 1.60E+18 0.518 Lower Shell Plate G-8-1 7.125 1.781 1.61E+18 0.652 1.05E+18 0.427 Lower Shell Plate G-8-3/4 7.125 1.781 1.61E+18 0.652 1.05E+18 0.427 Upper Shell Axial Welds 2-564A/C 7.125 1.781 2.40E+18 0.652 1.56E+18 0.512 Lower Shell Axial Welds 2-564D/F 7.125 1.781 1.60E+18 0.652 1.04E+18 0.425 Circumferential Weld Seam 3-564 7.125 1.781 1.61E+18 0.652 1.05E+18 0.427 Page 38 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 13: Heat Transfer Coefficients for NMPI 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-ft 2-°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 39 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 14: Feedwater Nozzle Material Properties Material Properties All Steels: Poisson's Ratio 0.3 Density 0.283 Reactor Vessel Plate (SA 302 Gr.B) [5, Material Group DJ T a E Thermal Conductivity, K Thermal Diffusivity Specific Heat, Cp t BTU/hr'fttF F iMn F psi ft 2 /hr BTUb "F 300 7.74E-06 2.80E+07 24.7 0.42 0.12 350 7.88E-06 24..3 0.409 0.123 400 8.01E-06 2.74E+07 24.6 0..398 0.126 326 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 ar E Thermal Conductivity, K Thermal Diffusivity Specific Heal, Cp F inn$F psi BTU/hritPF ft 2Amr BTU,7b'F 300 7,30E-06 2.85E+07 23.9 0.406 0.120 350 7.49E-06 23.7 0.396 0,122 400 7.66E-O6 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) 15, Material Group 83 T a E Therrnal Conductivity, K Thermal Diffusivity Specific Heal, Cp F inrint F psi BTU/hr t ft'F ft 2 /hr BTU/7b*F 300 7,18E-06 2.81E407 28.4 0,481 0.1207 350 7.47E-06 28.0 0.464 0.1234 400 2.75E+07 328 7.325E-06 "2.80E+07 28.2 0.4726 0.1221 Page 40 of 41 PTLR-1 Revision 0

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 41 of 41 PTLR-1 Revision 0