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:

Reviewed by:

Approved by:

Approved by:

G. 8. Inch Mechanical Design Engineering R. C Fri Mechanical Design Engineering P. E. B Supervisor Mech./Struc. Design Engineering A. D. Sterio, General Supervisor Design Engineering Date: 2./IY;/goo*

Date: -'// /**26.07 Date:

Date:

2/"7/o' 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): _5 250F/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): _5 100°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 1017 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 _< 100 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 if the 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 1000F 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 coP,200

• ,100-V,000 z-*- 900

" 800 LU D) 700 LU W 600 500 400 300 200 100 Beltline Region

-. Bottom Head

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

70°F 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. 600 500 -

400 300 200 100 -

0 -

Beltline Region

-. Bottom Head

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

70°F 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 Core Critical (Curve C), 28 EFPY Cooldown) -

1,900 1,800 1,700 1,600 1,500 1*,400 0.

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

- 800 uJ 700 U)

U) uJ

, 600 0.

500 400 300 200 100 0

I Minimum Criticality:

100°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 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,

uJWv 600 600 500 400 300 200 100 0i Beltline Region

-Bottom Head

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

70OF 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 600 0.

500 400 300 200 100 0

Beltline Region

- BottomHead

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

70°F 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 Core Critical (Curve C), 36 EFPY Cooldown) -

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.

700 U)

U, n 600 500 400 300 200 100 0

Minimum Criticality:

100°F 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 700 U) u)

W 600 0.

500 400 300 200 100 0j Beltline Region Bottom Head

............ Upper Vessel F

Bolt-up Temp:

70°F 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 w04,000 z

wU 800 U) 700 UJw

a. 600 500 400 300 200 100 0

Beltline Region

-. Bottom Head

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

70OF 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 Core Critical (Curve C), 46 EFPY Cooldown) -

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 700 U)

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 Vessel Radius, R =

106.5 ART 151.4 Kit =

0 Safety Factor =

1.5 M

=

2.472 Temperature Adjustment:

4.0 Pressure Adjustment -

27.7 Pressure Adjustment I1L 0.0 inches inches

°F=====>

28 EFPY (no thermal effects)

• F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

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

NMP1 Pressure and Temperature Limits Report Table 1 (Continued)

Gauge Fluid Temperature

(°F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 C(ksi-Vin) 50.38 51.08 51.81 52.57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 83.79 85.86 88.00 90.24 92.57 94.99 97.51 100.14 102.87 105.71 108.67 K.

(ksi-Vin) 33.59 34.05 34.54 35.05 35.57 36.12 36.69 37.29 37.91 38.55 39.22 39.92 40.64 41.40 42.18 43.00 43.85 44.74 45.66 46.62 47.62 48.66 49.75 50.87 52.05 53.27 54.54 55.86 57.24 58.67 60.16 61.71 63.33 65.01 66.76 68.58 70.48 72.45 Temperature Gauge for P-T Curve Pressure (psig) 909 922 935 949 963 978 993 1009 1026 1043 1062 1080 1100 1121 1142 1164 1187 1211 1236 1262 1289 1317 1346 1377 1409 1442 1476 1512 1549 1588 1628 1670 1714 1760 1807 1856 1908 1961

(*F) 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 Adjusted Pressure for P-T Curve (psig) 871 884 897 911 925 940 956 972 988 1006 1024 1043 1062 1083 1104 1126 1149 1173 1198 1224 1251 1280 1309 1339 1371 1404 1438 1474 1512 1550 1591 1633 1676 1722 1769 1819 1870 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 =

Vessel thickness, t =

Vessel Radius, R =

ART =

Kit =

Safety Factor =

Mm =

Temperature Adjustment =

Pressure Adjustment =

Pressure Adjustment =

Heat Up and Cool Down Rate =

Gauge Fluid Temperature

(*F) 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 K3. (ksi-Vin) 35.82 35.82 35.93 36.04 36.16 36.28 36.40 36.53 36.67 36.81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38.81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 41.23 41.56 41.90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 Beltline 7.125 106.5 151.4 12.91 2.0 2.472 12.2 27.7 52.2 100 Kim (ksi-Vin) 11.45 11.45 11.51 11.56 11.62 11.68 11.74 11.81 11.88 11.95 12.02 12.10 12.18 12.26 12.35 12.44 12.53 12.63 12.73 12.84 12.95 13.06 13.18 13.30 13.43 13.57 13.71 13.85 14.00 14.16 14.32 14.50 14.67 14.86 15.05 15.25 15.46 15.68 15.90 16.14 16.38 16.64 16.90 17.18 17.46 17.76 18.07 18.40 Gauge Pressure (psig) 310 310 311 313 315 316 318 320 321 323 325 327 330 332 334 337 339 342 345 347 350 353 357 360 364 367 371 375 379 383 388 392 397 402 407 413 418 424 430 437 443 450 457 465 473 481 489 498 inches inches

°F=====>

ksi??in

'F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

"F/Hr 28 EFPY Temperature for P-T Curve

('F) 70 70 70 70 70 70 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 Adjusted Pressure for P-T Curve (psig) 0 230 232 233 235 236 238 240 242 244 246 248 250 252 254 257 259 262 265 268 271 274 277 280 284 287 291 295 299 303 308 312 317 322 327 333 339 344 351 357 364 370 378 385 393 401 409 418 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 Curve Temperature

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

NMPI Pressure and Temperature Limits Report Table 3 (Continued)

Adjusted P-T curveAdjusted PoT Curve Temperature P

ure

(°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 Vessel Radius, R =

106.5 ART 159.0 Safety Factor 1 5 Temperature Adjustment 4 0 Pressure Adjustment 27.7',

Pressure Adjustment "10;0 inches inches

'F=====>

36 EFPY (no thermal effects)

• F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

Gauge Fluid Temperature (5F6 56 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 Temperature Gauge for P-T Curve 3,

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

NMPI Pressure and Temperature Limits Report Table 4 (Continued)

Gauge Fluid Temperature

(°F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 Kc (ksi-Vin) 47.96 48.56 49.19 49.84 50.52 51.23 51.96 52.73 53.52 54.35 55.22 56.11 57.05 58.02 59.04 60.09 61.19 62.33 63.52 64.76 66.04 67.38 68.78 70.23 71.74 73.32 74.95 76.66 78.43 80.28 82.20 84.20 86.28 88.44 90.70 93.05 95.49 98.03 100.68 103.43 106.30 109.28 Klm (ksi-Vin) 31.97 32.37 32.79 33.23 33.68 34.15 34.64 35.15 35.68 36.24 36.81 37.41 38.03 38.68 39.36 40.06 40.79 41.55 42.35 43.17 44.03 44.92 45.85 46.82 47.83 48.88 49.97 51.10 52.29 53.52 54.80 56.13 57.52 58.96 60.47 62.03 63.66 65.35 67.12 68.95 70.86 72.85 Gauge Pressure (psig) 865 876 888 899 912 924 938 951 966 981 996 1013 1029 1047 1065 1084 1104 1125 1146 1168 1192 1216 1241 1267 1295 1323 1352 1383 1415 1449 1483 1519 1557 1596 1637 1679 1723 1769 1817 1866 1918 1972 Temperature for P-T Curve

(°F) 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 Adjusted Pressure for P-T Curve (psig) 828 839 850 862 874 887 900 914 928 943 959 975 992 1009 1028 1047 1066 1087 1108 1131 1154 1178 1203 1230 1257 1285 1315 1346 1378 1411 1446 1482 1519 i558 1599 1641 1685 1731 1779 1829 1880 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 =

Vessel thickness, t =

Vessel Radius, R =

ART =

Kit =

Safety Factor =

Mm =

Temperature Adjustment =

Pressure Adjustment =

Pressure Adjustment =

Heat Up and Cool Down Rate =

Gauge Fluid Temperature (F) 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 KI, (ksi-Vin) 35.45 3S.45 35.54 35.64 35.74 35.84 35.95 36.06 36.18 36.30 36.43 36.56 36.70 36.84 36.99 37.14 37.30 37.47 37.64 37.83 38.02 38.21 38.42 38.63 38.85 39.08 39.32 39.57 39.83 40.10 40.38 40.68 40.98 41.30 41.63 41.97 42.33 42.70 43.09 43.50 43.92 44.35 44.81 45.28 45.78 46.29 46.82 47.38 Beltllne K 7.125 106.5 159.0 12.91 2.0 2.472 12.2 27.7 52.2 100 Kim (ksi-Vin) 11.27 11.27 11.31 11.36 11.41 11.46 11.52 11.57 11.63 11.69 11.76 11.82 11.89 11.96 12.04 12.11 12.19 12.28 12.37 12.46 12.55 12.65 12.75 12.86 12.97 13.08 13.20 13.33 13.46 13.59 13.73 13.88 14.03 14.19 14.36 14.53 14.71 14.90 15.09 15.29 15.50 15.72 15.95 16.18 16.43 16.69 16.95 17.23

°F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

'F/Hr Gauge Pressure (psig) 305 305 306 308 309 310 312 313 315 317 318 320 322 324 326 328 330 332 335 337 340 342 345 348 351 354 357 361 364 368 372 376 380 384 389 393 398 403 408 414 420 425 432 438 445 452 459 466 inches inches

°F=====>

ksi??in Temperature for P-T Curve

(*F) 70 70 70 70 70 70 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 Adjusted Pressure for P-T Curve (psig) 0 225 226 228 229 230 232 233 235 237 238 240 242 244 246 248 250 2S2 255 257 260 263 265 268 271 274 278 281 284 288 292 296 300 304 309 313 318 323 329 334 340 346 352 358 365 372 379 387 36 EFPY Page 26 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 5 (Continued)

Gauge Fluid Temperature

('F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 KIc (ksi-Vin) 47.96 48.56 49.19 49.84 50.52 51.23 51.96 52.73 53.52 54.35 55.22 56.11 57.05 58.02 59.04 60.09 61.19 62.33 63.52 64.76 66.04 67.38 68.78 70.23 71.74 73.32 74.95 76.66 78.43 80.28 82.20 84.20 86.28 88.44 90.70 93.05 95.49 98.03 100.68 103.43 106.30 109.28 112.38 115.62 118.98 122.48 126.12 129.92 133.86 137.97 142.25 146.70

.151.33 156.15 161.17 Klm (ksi-Vin) 17.52 17.82 18.14 18.46 18.80 19.16 19.52 19.91 20.30 20.72 21.15 21.60 22.07 22.55 23.06 23.59 24.14 24.71 25.30 25.92 26.57 27.24 27.93 28.66 29.41 30.20 31.02 31.87 32.76 33.68 34.64 35.64 36.68 37.77 38.89 40.07 41.29 42.56 43.88 45.26 46.69 48.18 49.74 51.35 53.03 54.78 56.60 58.50 60.47 62.53 64.67 66.89 69.21 71.62 74.13 Gauge Pressure (psig) 474 482 491 500 509 518 528 539 550 561 572 585 597 610 624 638 653 669 685 702 719 737 756 776 796 817 840 863 887 912 938 965 993 1022 1053 1084 1118 1152 1188 1225 1264 1304 1346 1390 1435 1483 1532 1583 1637 1692 1750 1811 1873 1938 2006 Temperature for P-T Curve

('F) 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 260 262 Adjusted Pressure for P-T Curve (psig) 394 403 411 420 429 439 449 459 470 481 493 505 517 531 544 559 573 589 605 622 639 657 676 696 716 738 760 783 807 832 858 885 913 942 973 1005 1038 1072 1108 1145 1184 1224 1266 1310 1356 1403 1452 1504 1557 1613 1670 1731 1793 1859 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 poT Curve 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 Vessel Radius, R:

.106.5 ART 167-4 Kit 1;0 Safety Factor 1.5 Mm 2.472 Temperature Adjustment =

4.0 Pressure Adjustment 27.7 Pressure Adjustment 10.0 inches inches

'F=====>

46 EFPY (no thermal effects)

'F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70°F) psig (instrument uncertainty)

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

(*F) 70 70 70 70 70 70 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 Adjusted Pressure for P-T Curve (psig) 0 602 603 605 607 609 611 613 615 617 619 622 624 627 629 632 635 638 641 644 648 651 655 659 663 667 671 675 680 685 690 695 701 706 712 718 725 732 738 746 753 761 769 778 Page 30 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 7 (Continued)

Gauge Fluid Temperature

(*F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 Kc (ksi-Vin) 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 50.38 51.08 51.81 52.57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 83.79 85.86 88.00 90.24 92.57 94.99 97.51 100.14 102.87 105.71 108.67 KIm (ksi-Vin) 30.45 30.79 31.14 31.51 31.89 32.29 32.71 33.14 33.59 34.05 34.54 35.05 35.57 36.12 36.69 37.29 37.91 38.55 39.22 39.92 40.64 41.40 42.18 43.00 43.85 44.74 45.66 46.62 47.62 48.66 49.75 50.87 52.05 53.27 54.54 55.86 57.24 58.67 60.16 61.71 63.33 65.01 66.76 68.58 70.48 72.45 Temperature Gauge for P-T Curve Pressure (psig) 824 833 843 853 863 874 885 897 909 922 935 949 963 978 993 1009 1026 1043 1062 1080 1100 1121 1142 1164 1187 1211 1236 1262 1289 1317 1346 1377 1409 1442 1476 1512 1549 1588 1628 1670 1714 1760 1807 1856 1908 1961

('F) 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 Adjusted Pressure for P-T Curve (psig) 787 796 805 815 826 836 848 859 871 884 897 911 925 940 956 972 988 1006 1024 1043 1062 1083 1104 1126 1149 1173 1198 1224 1251 1280 1309 1339 1371 1404 1438 1474 1512 1550 1591 1633 1676 1722 1769 1819 1870 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 =

Component =

Vessel thickness, t =

Vessel Radius, R =

ART =

Kit =

Safety Factor =

Mm=

Temperature Adjustment =

Pressure Adjustment =

Pressure Adjustment =

Heat Up and Cool Down Rate =

Gauge Fluid Temperature

(°F) 48 48 50 52 54 56 58 60 62 64 66 68 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 Kkc (ksi-Vin) 35.10 35.10 35.18 35.26 35.35 35.43 35.53 35.62 35.72 35.82 35.93 36.04 36.16 36.28 36.40 36.53 36.67 36.81 36.96 37.11 37.27 37.44 37.61 37.79 37.98 38.17 38.37 38.59 38.81 39.03 39.27 39.52 39.78 40.05 40.33 40.62 40.92 41.23 41.56 41.90 42.26 42.63 43.01 43.41 43.83 44.26 44.72 45.19

! -<N-MP1 BeltIlne 7.125.

10615 167.4 o12:91/

4.2.72 12;2 27.7 52.2 100 Kim (ksi-Vin) 11.09 11.09 11.13 11.17 11.22 11.26 11.31 11.35 11.40 11.45 11.51 11.56 11.62 11.68 11.74 11.81 11.88 11.95 12.02 12.10 12.18 12.26 12.35 12.44 12.53 12.63 12.73 12.84 12.95 13.06 13.18 13.30 13.43 13.57 13.71 13.85 14.00 14.16 14.32 14.50 14.67 14.86 15.05 15.25 15.46 15.68 15.90 16.14 Gauge Pressure (psig) 300 300 301 302 304 305 306 307 309 310 311 313 315 316 318 320 321 323 325 327 330 332 334 337 339 342 345 347 350 353 357 360 364 367 371 375 379 383 388 392 397 402 407 413 418 424 430 437 inches inches

'F=====>

ksi??in

'F (instrument uncertainty) psig (hydrostatic pressure head for a full vessel at 70 'F) psig (instrument uncertainty)

°F/Hr 46 EFPY Temperature for P-T Curve

('F) 70 70 70 70 70 70 70 72 74 76 78 80 82 84 86 88 90 92 94 96 98 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 Adjusted Pressure for P-T Curve (psig) 0 220 221 223 224 225 226 227 229 230 232 233 235 236 238 240 242 244 246 248 250 2S2 254 257 2S9 262 265 268 271 274 277 280 284 287 291 295 299 303 308 312 317 322 327 333 339 344 3S1 357 Page 32 of 41 PTLR-1 Revision 0

NMP1 Pressure and Temperature Limits Report Table 8 (Continued)

Gauge Fluid Temperature

('F) 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 202 204 206 208 210 212 214 216 218 220 222 224 226 228 230 232 234 236 238 240 242 244 246 248 250 252 254 256 258 K,, (ksi-Vin) 45.68 46.18 46.71 47.27 47.84 48.44 49.06 49.71 50.38 51.08 51.81 52.57 53.36 54.18 55.04 55.93 56.86 57.83 58.83 59.88 60.96 62.10 63.28 64.50 65.78 67.11 68.50 69.94 71.44 73.00 74.62 76.31 78.07 79.90 81.81 83.79 85.86 88.00 90.24 92.57 94.99 97.51 100.14 102.87 105.71 108.67 111.75 114.96 118.30 121.77 125.38 129.14 133.06 137.14 141.38 145.79 150.39 155.17 160.15 Km Gauge (ksi-Vin)

Pressure (psig) 16.38 16.64 16.90 17.18 17.46 17.76 18.07 18.40 18.73 19.08 19.45 19.83 20.22 20.64 21.06 21.51 21.97 22.46 22.96 23.48 24.03 24.59 25.18 25.80 26.43 27.10 27.79 28.51 29.26 30.04 30.85 31.70 32.58 33.49 34.45 35.44 36.47 37.55 38.66 39.83 41.04 42.30 43.61 44.98 46.40 47.88 49.42 51.02 52.69 54.43 56.23 58.12 60.07 62.11 64.23 66.44 68.74 71.13 73.62 443 450 457 465 473 481 489 498 507 517 526 537 547 559 570 582 595 608 621 636 650 666 682 698 715 733 752 772 792 813 835 858 882 907 932 959 987 1016 1046 1078 1111 1145 1180 1217 1256 1296 1338 1381 1426 1473 1522 1573 1626 1681 1739 1798 1860 1925 1993 Adjusted Temperature Pressure for for P-T Curve P-T Curve (F)

(psig) 154 364 156 370 158 378 160 385 162 393 164 401 166 409 168 418 170 427 172 437 174 447 176 457 178 468 180 479 182 490 184 502 186 515 188 528 190 542 192 556 194 570 196 586 198 602 200 618 202 636 204 654 206 672 208 692 210 712 212 733 214 755 216 778 218 802 220 827 222 852 224 879 226 907 228 936 230 967 232 998 234 1031 236 1065 238 1101 240 1138 242 1176 244 1216 246 1258 248 1301 250 1346 252 1393 254 1442 256 1493 258 1546 260 1601 262 1659 264 1718 266 1781 268 1845 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 RT NDT=

40.0 Adjusted P-T Curve Temperature

(°F) 100 100 102 104 106 108 110 112 114 116 118 120 122 124 126 128 130 132 134 136 138 140 142 144 146 148 150 152 154 156 158 160 162 164 166 168 170 172 174 176 178 180 182 184 186 188 190 192 194 196 198 200 Adjusted P-T

.Curve Pressure (psig) 0 113 119 122 126 131 136 141 147 153 159 165 172 179 186 194 202 210 219 228 238 248 254 257 259 262 265 268 271 274 277 280 284 287 291 295 299 303 308 312 317 322 327 333 339 344 351 357 364 370 375 375 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 a)

.6~

'U K

Upper Shell Plate Upper Shell Plate Upper Shell Plate Lower Shell Plate Lower Shell Plate.

G-307-3 G-307-4 G-307-10 G-8-1 G-8-3/4 P2074 P2076 P2091 P2112 P2130A 28 40 20 36

-3 0.2 0.27 0.22 0.236 0.176 0.48 0.53 0.51 0.503 0.586 134.6 173.85 148.85 228.35 146.8 57.7 74.6 63.8 81.4 52.3 0

0 0

0 0

17 17 17 17 8.5 119.7 148.6 117.8 151.4 66.3

-I P

P 4

4 4

In 0

Upper Shell Axial Welds Lower Shell Axial Welds Circumferential Weld Seam 2-564A/C 2-564D/F 3-564 86054B 86054B 1248 4E5F 4E5F 4M2F

-50

-50

-50 0.214 0.214 0.214 0.046 0.046 0.076 97.59 97.59 99.9 41.4 34.6 35.6 0

0 0

20.7 17.3 17.8 32.8 19.3 21.2 Fluence at-1/4 T, f Fluence Factor, FF (n/cm2) f(O.28-O101og f)

Ina'

.6~

'UK Upper Shell Plate Upper Shell Plate Upper Shell Plate Lower Shell Plate Lower Shell Plate G-307-3 G-307-4 G-307-10 G-8-1 G-8-3/4 7.125 7.125 7.125 7.125 7.125 1.781 1.781 1.781 1.781 1.781 1.63E+18 1.63E+18 1.63E+18 1.12E+18 1.12E+18 0.652 0.652 0.652 0.652 0.652 1.06E+18 1.06E+18 1.06E+18 7.29E+17 7.29E+17 0.429 0.429 0.429 0.357 0.357 1

1 1

I I

Upper Shell Axial Welds Lower Shell Axial Welds Circumferential Weld Seam 2-564A/C 2-564D/F 3-564 7.125 7.125 7.125 1.781 1.781 1.781 1.59E+18 1.11E+18 1.12E+18 0.652 0.652 0.652 1.04E+18 7.22E+17 7.29E+17 0.424 0.355 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 Flux Lot. 'Initial r**:"*

Flux.Lot Chemistry Description, Code-No.

Heat No.

RTNDT Chemistry ARTNOT Margin Terms ARTNDT No.

Factor-(F)

Cu (wt%)

Ni (wt%)

_(°F) o, (*F) 0A (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

_Full 1/4 T (n/cm 2) 1/4T = e-0.24x (n/cm2) 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 ARTNDT

.N o.

(F.

_ __Ct o r_(_F )

_.... I"C u (w t% )

N i 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 Upper Shell Plate G-307-10 P2091 20 0.22 0.51 148.85 77.0 0

17 131.0 4.1 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 Full 1/4 T (n/cm2 )

1/4T = e-O.24x (n/cm2)

" 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 Heat Transfer Temperature Coefficient Region

(°F)

(Btu/hr-ft2 -°F) 1 550.0 205.1 2

550.0 205.1 3

550.0 205.1 4

550.0 205.1 100% Flow Case Heat Transfer Temperature Coefficient Region

(°F)

(Btu/hr-ft2-°F) 1 100.0 2108.8 2

325.0 673.9 3

325.0 191.8 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 F

iMnt F psi BTU/hr'fttF 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

inrintF psi BTU/hr tft'F ft2/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