JAFP-17-0103, Pressure and Temperature Limits Report, Rev. 1 (40 Effective Full-Power Years)

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Pressure and Temperature Limits Report, Rev. 1 (40 Effective Full-Power Years)
ML17292A080
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Site: FitzPatrick Constellation icon.png
Issue date: 10/19/2017
From: Drews W
Exelon Generation Co
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Document Control Desk, Office of Nuclear Reactor Regulation
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JAFP-17-0103
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Proprietary Information Withhold Per 10 CFR 2.390 Exelon Generation Company, LLC James A, FitzPatrick NPP Exelon Generation Tel 375-349-6024 Fax 315-349-6480 William C. Drews Regulatory Assurance Manager JAF JAFP-1 7-0103 October 19, 2017 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Pressure and Temperature Limits Report, Rev. 1 (40 Effective Full-Power Years)

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059

Dear Sir or Madam,

Enclosed is Revision I to the James A. FitzPatrick (JAF) Pressure and Temperature Limits Report (PTLR). This revision incorporates analysis completed for bounding values at forty (40)

Effective Full Power Years (EFPY), and is submitted in accordance with JAF Technical Specification (TS) 5.6.7.

Enclosure I contains proprietary information. The Electric Power Research Institute (EPRI), as the owner of the proprietary information, has executed the enclosed affidavit. It identifies which information should be handled as proprietary. Exelon Generating Company, LLC hereby requests that Enclosure 1 be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. A non-proprietary version of the documentation is provided in .

There are no new regulatory commitments contained in this report. Questions concerning this report may be addressed to Mr. Steve DeFillippo, (315) 349-6455.

Very truly yours,

/JI William C. Drews Regulatory Assurance Manager WD/ds

Enclosure:

1. Pressure and Temperature Limits Report, Revision 1 (Proprietary)
2. Pressure and Temperature Limits Report, Revision 1 (Non-Proprietary) cc: next page Enclosure I to this letter contains Proprietary Information that should be withheld from public disclosure per 10 CFR 2.390. When separated from Enclosure 1 there are no applicable withholding criteria.

Proprietary Information Withhold Per 10 CFR 2.390 JAFP-1 7-0103 Page 2 of 2 cc: (w/out enclosure)

NRC Regional Administrator, NRC Region I NRC Project Manager NRC Resident Inspector NYSERDA NYSPSC Enclosure I to this letter contains Proprietary Information that should be withheld from public disclosure per 10 CFR 2.390. When separated from Enclosure 1 there are no applicable withholding criteria.

JAFP-1 7-0103 ENCLOSURE 2 Pressure and Temperature Limits Report Revision I (Non-proprietary)

(30 Pages)

EXELON GENERATION COMPANY, LLC JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) UP TO 40 EFFECTIVE FULL-POWER YEARS REVISION I Prepared by: ) CLZ Date:

Reviewed by: g. ck43i2?_ Date:

cj/

/L7 Approved by: Date: 7 Director, Engineering Concurred by: V%) t7-)i 2-zv / L__ Date:

Manager, Regulatory Assurance

JAF Pressure-Temperature Limits Report Table of Contents Section Page 1.0 Purpose 3 2.0 Applicability 3 3.0 Methodology 4 4.0 Operating Limits 5 5.0 Discussion 6 6.0 References 13 Figure 1 JAF Pressure Test (Curve A) ---40 EPFY 15 Figure 2 JAF Normal Operation Core Not Critical (Curve B) ---40 EFPY 16 Figure 3 JAF Normal Operation Core Critical (Curve C) --- 40 EFPY 17 Table I JAF Pressure Test (Curve A) ---40 EFPY 18 Table 2 JAF Core Not Critical (Curve B) --- 40 EFPY 21 Table 3 JAF Core Critical (Curve C) --- 40 EFPY 24 Table 4 JAF ART Calculations for 40 EFPY (Reference 6.10) 27 Table 5 JAF ART Calculations for N16 Nozzle for 40 EFPY (Reference 6.3) 28 Appendix A JAF Reactor Vessel Material Surveillance Programs 29 Revision 1 Page 2 of 30

JAF Pressure-Temperature Limits Report 1.0 PURPOSE The purpose of the James A. FitzPatrick Nuclear Power Plant Pressure and Temperature Limits Report (PTLR) is to present operating limits relating to:

  • RCS Heatup and Cooldown rates
  • RPV bottom head coolant temperature to RPV coolant L\T requirements during Recirculation Pump startups
  • RPV head flange boltup temperature limits This report has been prepared in accordance with the requirements of Licensing Topical Report SIR-05-044, Revision 1-A, contained within BWROG-TP-1 1-022-A, Revision 1 (Reference 6.1), as well as the methodology described in SI Calculation 0800846.301, Revision 1, (Reference 62), thereby satisfying JAF Technical Specification (TS) Section 5.6.7.

2.0 APPLICABILITY This report is applicable to the JAF RPV for up to 40 Effective Full-Power Years (EFPY).

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

  • Limiting Conditions for Operation and Surveillance Requirement Applicability Section 3.4.9 RCS Pressure and Temperature (PIT) Limits, The JAF Reactor Vessel Pressure and Temperature Limits for 40 to 54 EFPY have been developed per Reference 6.3. Only the 40 EFPY Limits are incorporated in this revision of the PTLR. Future revisions of the PTLR must be revised per the 1 OCFR5O.59 Review process as applicable.

Revision 1 Page 3 of 30

JAF Pressure-Temperature Limits Report 3.0 METHODOLOGY The limits in this report were derived as follows:

1) The methodology used is in accordance with Reference 6.1, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, incorporating the NRC Safety Evaluation in Reference 6.4.
2) The neutron fluence is calculated in accordance with NRC Regulatory Guide 1.190 (RG 1.190), Reference 6.5, using the RAMA computer code, as documented in References 6.6 and 6.7.
3) The adjusted reference temperature (ART) values for the limiting beltline materials are calculated in accordance with NRC Regulatory Guide 1.99, Revision 2 (RG 1.99), Reference 6.8, and supplemented by data from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) in Reference 6.9. ART calculations are documented in References 6.3 and 6.10.
4) The pressure and temperature limits were calculated in accordance with References 6.1 and 6.2, as documented in Reference 6.3.
5) This revision of the pressure and temperature limits is to incorporate the following changes:
  • Revision 0: Initial issue of PTLR
  • Revision 1:

o Incorporated P-T limits for 40 EFPY and removed curves for 32 EFPY.

o Incorporated P-T limits for instrument (N 16) nozzle and description of nozzle stress analyses.

o Updated information on BWRVIP ISP surveillance capsule data for JAF representative materials.

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 (Reference 6.11),

provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance.

Revision 1 Page 4 of 30

JAF Pressure-Temperature Limits Report Changes to the curves, limits, or parameters within this PTLR, based upon revised RPV fluence calculation methodology, cannot be made without prior NRC approval. Such analysis and revisions shall be submitted to the NRC for review prior to incorporation into the PTLR.

4O OPERATING LIMITS The pressure-temperature (P-T) 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 beitline 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, referred to as Curve B; and (c) core critical operation, referred to as Curve C, in accordance with 10 CFR 50, Appendix G (Reference 6.12).

Complete P-T curves were developed for 40 EFPY for JAF, as documented in Reference 6.3. The JAF P-T curves for 40 EFPY are provided in Figures 1 through 3, and a tabulation of the curves is included in Tables 1 through 3. For Curves A, B, and C in Tables 1, 2, and 3, respectively, three tables are included for the beltline, bottom head, and upper vessel/feedwater nozzle (non-beltline) regions.

The resulting P-I curves are based on the geometry, design and materials information for the JAF vessel with the following conditions:

  • Heatup and Cooldown rate limit during Hydrostatic and Class 1 Leak Testing (Figure 1: Curve A): 20°Flhour1.
  • Normal Operating Heatup and Cooldown rate limit (Figure 2: Curve B non -

nuclear heating, and Figure 3: Curve C nuclear heating):

- 100°Flhour2.

1 Interpreted as the temperature change in any 1-hour period is less than or equal to 20°F.

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

Revision 1 Page 5 of 30

JAF Pressure-Temperature Limits Report

  • RPV bottom head coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: 145°F.
  • Recirculation loop coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: 50°F.
  • RPV head installation temperature limit (Figure 1: Curve A Hydrostatic and Class 1 Leak Testing; Figure 2: Curve B - non-nuclear heating): 70°F.
  • RPV flange and adjacent shell criticality temperature limit (Figure 3: Curve C nuclear heating): 90°F.

The minimum bolt-up temperature is selected to address the NRC condition in Section 4.0 of Reference 6.4 regarding lowest service temperature (LST) for all ferritic components of the reactor coolant pressure boundary (RCPB), including piping and other non-RPV components. The minimum temperature is set to 70°F for Curves A and B, which is equal to the closure stud LST (Reference 6.13, Table 3-3), and 90°F for Curve C, which is equal to RTNDT,max + 60°F, where RTNDTmax (the bounding nil-ductility reference temperature for the closure flange region) is 30° F. These temperatures bound the minimum temperature limits and minimum bolt-up temperatures in the current docketed P-T curves (Reference 6.14, approved by the NRC in Reference 6.15). These temperatures also bound the non RPV ferritic components of the RCPB, such as piping, which was impact tested at a temperature that is 60°F below the anticipated minimum service temperature, per the fabrication requirements described in the JAFNPP FSAR (Reference 6.16, Section 16.5.10).

5.0 DISCUSSION The ART of the limiting beltline material is used to adjust the beltline P-T curves to account for irradiation effects. RG 1.99 (Reference 6.8) provides the methods for determining the ART. The RG 1.99 methods for determining the limiting material and adjusting the P-I curves using ART are discussed in this section.

The JAF reactor vessel beltline copper (Cu) and nickel (Ni) values were obtained from the evaluation of the JAF vessel plate and weld materials (Reference 6.10). The Cu and Ni values were used with Tables 1 and 2 of RG 1.99 to determine a chemistry factor (CF) per Revision 1 Page 6 of 30

JAF Pressure-Temperature Limits Report Regulatory Position 1.1 of RG 1.99 for welds and plates, respectively (Reference 6.8).

However, for materials where surveillance data exists (i.e. JAF plate heat number C3278-2 and weld heat number 13253/12008), a fitted CF has been used in the ART calculations for those heats, in accordance with Regulatory Position 2.1 in RG 1.99 (Reference 6.8).

The peak RPV ID fluence used in the P-I curve evaluation for 40 EFPY is 2.41x1 018 n/cm2 for JAF (Table 2 of Reference 6.10). Fluence values were linearly interpolated for 40 EFPY based on the fluence values for 22.2 and 54 EFPY provided in Reference 6.6, which were calculated using methods that comply with the guidelines of RG 1.190 (Reference 6.5). An ID fluence value of 1.993x1018 n/cm2 applies to the limiting beltline lower shell plate C3376-2 for JAF. This fluence value was adjusted for the limiting lower shell plates based upon an attenuation factor of 0.682 for a postulated flaw with depth 1/4 of the wall thickness (114t).

As a result, the 1/4t40 EFPY fluence for the limiting beltline lower shell plate is 1.359x1018 n/cm2 for JAF. An ID fluence value of I .834x1 018 n/cm2 applies to the limiting beltline lower shell weld 27204/1 2008. This fluence value was adjusted based upon an attenuation factor of 0.724 for a postulated 1/4t flaw. As a result, the 1/4t 40 EFPY fluence for the limiting beltline lower shell weld is 1 .328x1 018 n/cm2 for JAF. The limiting ART for the JAF beltline for 40 EFPY is 118°F, corresponding to the lower shell weld 27204/1 2008 (Reference 6.10).

The P-I limits are developed to bound all ferritic materials in the RPV, including the consideration of stress levels from structural discontinuities such as nozzles. JAF has one set of nozzles in the RPV beltline, the instrument (N 16) nozzles located in the lower-intermediate shell beltline plates (Reference 6.3). The feedwater (FW) nozzle is considered in the evaluation of the non-beltline (upper vessel) region P-T limits.

The N16 nozzles and welds are fabricated from non-ferritic materials and do not require specific evaluation. However, the geometric discontinuity caused by the penetrations in the adjacent plates is considered in the development of bounding beltline P-T limits as described in Reference 6.3. The N16 nozzle locations have a limiting RPV ID fluence of 5.63x1 017 n/cm2 at 40 EFPY (Reference 6.7). For the N16 nozzles, a plant-specific damage assessment, in terms of displacements per atom (dpa), was performed to determine Revision 1 Page 7 of 30

JAF Pressure-Temperature Limits Report through-wall fluence in Reference 6.7, as permitted by RG 1.99. The ratio of the fluence at the 114t depth to the fluence at the ID is 0.682 for a postulated 114t flaw in the N16 nozzle corner. Consequently, the 1/4t fluence for 40 EFPY for the N16 nozzle locations is 3.84x1 017 n/cm2 (Reference 6.7). The limiting value for ART for the N16 nozzles is 35.3°F for 40 EFPY (Reference 6.3).

The P-T 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 114t 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 stress at the 1/4t location is assumed to be tensile for both heatup and cooldown. This results in the approach of applying the maximum tensile stress at the 1/4t location. This approach is conservative because irradiation effects cause the allowable toughness at 1/4t to be less than that at 3/4t for a given metal temperature. This approach causes no operational difficulties, since the BWR 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 developed based on a coolant heatup and cooldown temperature rate of 100°FIhr for which the curves are applicable. However, the core not critical and the core critical curves were also developed to bound Service Level NB RPV thermal transients. For the hydrostatic pressure and leak test curve (Curve A), a coolant heatup and cooldown temperature rate of 20°FIhr 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. So, 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.

Revision 1 Page 8 of 30

JAF Pressure-Temperature Limits Report The initial RTNDT, chemistry (weight-percent Cu and Ni) and adjusted reference temperature at the 1/4t location for 40 EFPY for all RPV beltline plates and welds significantly affected by fluence (i.e., fluence> 10 n/cm2 for E> 1 MeV) are shown in Table 4. Table 5 shows the ART calculations for the N16 nozzles, based on the fluence at the nozzle locations and the material parameters of the adjacent vessel plates. The initial RTNDT values shown in Tables 4 and 5 (obtained from Reference 6.13) have been previously approved for use by the NRC (Reference 6.17).

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) representative weld and plate surveillance material data for JAF were reviewed from BWRVIP-135, Revision 3 (Reference 6.9), and in accordance with Appendix A of Reference 6.1. Although Reference 6.10 cites Revision .1 of BWRVIP-135, there were no changes in the latest revision that affected the JAF ART calculation. Use of surveillance data from the BWRVIP ISP for JAF was approved by the NRC in Reference 6.18.

For the JAF target plate material G-3415-3, (heat number C3376-2), the ISP representative plate material (C6345-1) is not the same heat number as the target plate, nor does the ISP representative heat exist in the JAF beltline. For the JAF target weld materials 2-233A, B &

C (heat number 27204/1 2008), the ISP representative weld material (27204) is not the same heat number as the target weld. Therefore, the CF values for the target plate and weld (heat numbers C3376-2 and 27204/1 2008) were calculated using table values from RG 1.99 Regulatory Position 1.1 (Reference 6.8).

However, surveillance test data is available for two heats which do exist in the JAF beltline:

plate heat number C3278-2 and weld heat number 13253/1 2008, with data provided in Reference 6.9.

For RPV plate G-3414-2 (heat number C3278-2), test data is available for two capsules from the JAF surveillance program and six capsules from the Supplemental Surveillance Program (SSP) (Reference 6.9). The fifed CF of {E}]J for this material bounds the CF

((

from the RG 1.99 tables, therefore, the higher surveillance-based CF is used for plate heat C3278-2. The scatter in the surveillance data exceeds the credibility criteria, so a standard REDACTED EPRI REFERENCE 6.9 PROPRIETARY Revision 1 {E}J] Page 9 of 30 INFORMATION INDICATED BY tt

JAF Pressure-Temperature Limits Report full margin (Gc = 17.0 °F) was used in the ART calculations for plate heat number C3278-2 as shown in Table 4 (Reference 6.10).

The surveillance-based CF for plate heat number C3278-2 is also used in the calculation of ART for instrument nozzle N16A (Table 5), which is based on material parameters for the adjacent shell plate and fluence at the nozzle location. Consequently, ARTNDT and a for the N16A nozzle differ from those calculated for plate heat number C3278-2 in Table 4.

For RPV welds 1-233A, B & C (heat number 13253/12008), test data for two capsules is available from the SSP capsules (Reference 6.9). A fitted CF of (( was reported for the 13253/1 2008 weld heat (Reference 6.9). Since the surveillance weld chemistry differs slightly from the vessel best-estimate weld chemistry, an adjusted chemistry factor of 326.94°F was calculated using the ratio procedure (Reference 6.10). Because the surveillance data is credible, the margin term was cut in half (Gii = 14.0° F) in calculations of the ART values for weld heat number 13253/12008 as shown in Table 4 (Reference 6.10). The RG 1.99 table CFs were used in the determination of the ART values for all JAF beltline materials except for plate heat C3278-2 and weld heat 13253/12008.

The only computer code used in the determination of the JAF P-T curves was the ANSYS finite element (FE) computer program for the FW nozzle (non-beltline) and instrument (N 16) nozzle stresses (various code versions as identified below).

ANSYS finite element analyses (FEA) were performed to determine through-wall thermal and pressure stress distributions for the JAF FW nozzle (Reference 6.19) and for the instrument (N 16) nozzles (Reference 6.2). These stress distributions were used in the determination of the stress intensity factors for the FW nozzle (References 6.3 and 6.20) and N16 nozzles (Reference 6.21).

The plant-specific JAF FW nozzle analyses were performed to determine through-wall pressure and thermal stress distributions due to bounding thermal transients. Detailed information regarding the analyses and results can be found in References 6.20, 6.19, REDACTED EPRI REFERENCE 6.9 PROPRIETARY INFORMATION INDICATED BY {E}jj Revision 1 (( Page 10 of 30

JAF Pressure-Temperature Limits Report 6.22. The following summarizes the development of the thermal and pressure stress intensity factors for the FW nozzle:

  • With respect to operating conditions, stress distributions for a thermal shock of 450°F represents the maximum thermal shock for the FW nozzle during normal and upset operating conditions. The stress results for a 450°F shock are appropriate for use in developing the non-beltline P-T curves based on the limiting FW nozzle, as a shock of 450°F is representative of the Turbine Roll transient during startup, which produces the highest tensile stresses at the FW nozzle l/4t location. Because operation is along the saturation curve, these stresses are scaled to reflect the worst-case step change due to the available temperature difference. Therefore, these stresses represent bounding stresses in the FW nozzle associated with 100°F/hr heatup/cooldown limits associated with the P-T curves for the upper vessel region. The boundary integral equation/influence function (BIE/IF) methodology presented in Reference 6.1 was used in Reference 6.20 to calculate the thermal stress intensity factor, Kit, by fifing a third order polynomial equation to the path stress distribution for the thermal load case.
  • Heat transfer coefficients used in the Reference 6.19 analyses were obtained from a GE evaluation of overall heat transfer coefficients for various BWR FW nozzle thermal sleeve configurations. The configuration used in the plant-specific analyses in Reference 6.19 represents a triple thermal sleeve sparger with seal no. 1 failed.
  • With respect to pressure stress, a unit pressure of 1,000 psig was applied to the internal surfaces of the FE model. The pressure stress distribution was taken along the same path as the thermal stress distribution. The BIE/IF methodology presented in Reference 6.1 was used in Reference 6.20 to calculate the pressure stress intensity factor, Kin, by fitting a third order polynomial equation to the path stress distribution for the pressure load case. The resulting Ki can be linearly scaled to determine the Ki for various RPV internal pressures.
  • A two-dimensional axisymmetric FE model of the FW nozzle was constructed in Reference 6.19 and evaluated using the ANSYS code (Reference 6.23). The pressure stress distribution used to determine Ki reflects a scaling factor of 3.0 to account for three-dimensional effects on the pressure stresses (Reference 6.3).

Details of the model are provided in Reference 6.19.

Revision 1 Page 11 of 30

JAF Pressure-Temperature Limits Report The plant-specific JAF instrument (N 16) nozzle analysis was performed to determine through-wall pressure and thermal stress distributions due to bounding thermal transients.

Detailed information regarding the analysis can be found in Reference 6.2. The following summarizes the development of the thermal and pressure stress intensity factors for the N16 nozzles:

  • A one-quarter symmetric, three-dimensional FE model of the N16 nozzle was constructed in Reference 6.2 using the ANSYS code (Reference 6.24).

Temperature-dependent material properties, taken from the ASME Code,Section II, Part D, 2001 Edition with 2003 Addenda (Reference 6.25), were used in the evaluation.

  • With respect to operating conditions, the bounding thermal transient for the region corresponding to the instrument nozzles during normal and upset operating conditions, the SRV blowdown event, was analyzed (Reference 6.2). The thermal stress distribution, corresponding to the limiting time in Reference 6.2, along a linear path through the nozzle corner, is used. The BIE/IF methodology presented in Reference 6.1 was used to calculate the thermal stress intensity factor, Kit, due to the path stress by fitting a third order polynomial to the path stress distribution for the thermal load case.
  • Boundary conditions and heat transfer coefficients used for the thermal analysis are described in Reference 6.2.
  • With respect to pressure stress, a unit pressure of 1,000 psig was applied to the internal surfaces of the FE model (Reference 6.2). The pressure stress distribution was taken along the same path as the thermal stress distribution. The BIE/IF methodology presented in Reference 6.1 was used to calculate the pressure stress intensity factor, Kin, due to the path stress by fitting a third order polynomial to the path stress distribution for the pressure load case. The resulting Ki can be linearly scaled to determine the Ki for various RPV internal pressures.

Revision 1 Page 12 of 30

JAF Pressure-Temperature Limits Report

6.0 REFERENCES

6.1 Licensing Topical Report (LTR) BWROG-TP-1 1-022-A, Revision 1 (SIR-05-044, Revision 1-A), Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, August 2013, ADAMS Accession No. ML13277A557.

6.2 SI Calculation No. 0800846.301, Revision 1, 2 Instrument Nozzle Stress Analysis, May 7, 2009.

6.3 SI Calculation No. 1400824.301, Revision 0, FitzPatrick Updated P-T Curve Calculation for 40, 48, and 54 EFPY, September 1,2017.

6.4 U.S. NRC Letter to BWROG dated May 16, 2013, Final Safety Evaluation for Boiling Water Reactor Owners Group Topical Report BWROG-TP-11-022, Revision 1, November 2011, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors (TAC NO. ME7649, ADAMS Accession No. ML13107A062) 6.5 U.S. Nuclear Regulatory Commission Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, March 2001.

6.6 TransWare Report No. ENT-FLU-002-R-005, Revision 0, Non-Proprietary Version of James A. FitzPatrick Reactor Pressure Vessel Fluence Evaluation at End Of Cycle 17 and 54 EFPY, October 31, 2007.

6.7 TransWare Report No. EXL-JAF-001-R-001, Revision 1, Determination of Fast Neutron Fluence (>1.0 MeV) in the James A. FitzPatrick Reactor Pressure Vessel N16 Instrumentation Nozzle at 40 EFPY and 54 EFPY, August 16, 2017. TRANSWARE PROPRIETARY INFORMATION.

6.8 U. S. Nuclear Regulatory Commission Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.

6.9 B WRVIP- 135, Revision 3: B WR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations. EPRI, Palo Alto, CA: 2014.

3002003144. EPRI PROPRIETARY INFORMATION.

6.10 SI Calculation No. FITZ-1OQ-301, Revision 0, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts, February 15, 2008.

6.11 U.S. Code of Federal Regulations, Title 10, Part 50, Section 59, Changes, tests and experiments.

6.12 U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Appendix G, Fracture Toughness Requirements.

6.13 General Electric Report GENE-B1100732-01, Revision 1, Plant Fitzpatrick RPV Surveillance Materials Testing and Analysis of 120 degree capsule at 13.4 EFPY, February 1998.

6.14 Attachment 5 to Entergy Letter JAFP-08-0034, James A. FitzPatrick Nuclear Power Plant Report, Pressure and Temperature Limits Report (PTLR) up to 32 Effective Full Power Years, Entergy Nuclear Operations, Revision 0, April 14, 2008. (ADAMS Accession No. ML081200881) 6.15 JAF License Amendment No. 292, Relocation of Pressure and Temperature Curves to the Pressure and Temperature Limits Report Consistent with TSTF-419-A (TAC No.

MD8556), dated October 3, 2008. (ADAMS Accession No. ML082630365)

Revision 1 Page 13 of 30

JAF Pressure-Temperature Limits Report 6.16 James A. FitzPatrick Nuclear Power Plant Final Safety Analysis Report Update, Section 16.5, Pressure Integrity of Piping and Equipment Pressure Parts, Subsection 16.5.10.

6.17 JAF License Renewal Final SER, dated January 24, 2008, Open Item 4.2.2-1 (P-T Limits). (ADAMS Accession No. ML080250372) 6.18 JAF License Amendment No. 285, Changes to the Reactor Vessel Material Surveillance Program, dated July 26, 2006. (TAC No. MC9682, ADAMS Accession No. MLO61ZI 0335) 6.19 GE Report NEDC-30799-P, James A. FitzPatrick Nuclear Power Station Feedwater Nozzle Fracture Mechanics Analysis to Show Compliance with NUREG-0619, December 1984. GE PROPRIETARY INFORMATION.

6.20 SI Calculation No. FITZ-IOQ-302, Revision 0, Revised Pressure-Temperature Curves, February 26, 2008.

6.21 SI Calculation No. 0800846.302, Revision 1, Comparison of Instrument Nozzle (N16) and Beltline P-I curves for 32 EFPY, May 13, 2009.

6.22 SI Calculation No. NYPA-62Q-301, Revision 0, Benchmark Analysis, January 18, 1999.

6.23 G.J. DeSalvo and J.A. Swanson, ANSYS Engineering Analysis System Users Manual, Swanson Analysis Systems, Inc., March 1975.

6.24 ANSYS Release 8.1 (w/Service Pack 1), ANSYS, Inc., June 2004.

6.25 ASME Boiler and Pressure Vessel Code,Section II, Part D, Material Properties, 2001 Edition with Addenda through 2003.

6.26 BWRVIP 86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan. EPRI, Palo Alto, CA: 2012. 1025144.

EPRI PROPRIETARY INFORMATION.

6.27 U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements.

Revision 1 Page 14 of 30

JAF Pressure-Temperature Limits Report Figure 1: JAF Pressure Test (Curve A) ---40 EFPY Curve A Pressure Test, Composite Curves Befttine Bottom Head Non-Beitline a==OveraIl 1300 1200 1100 1000 900 In

$00 in In a) 0 700 a)

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Revision 1 Page 15 of 30

JAF Pressure-Temperature Limits Report Figure 2: JAF Normal Operation Core Not Critical (Curve B) ---40 EFPY Curve B Core Not Critical, Composite Curves Beftilne Bottom Head Non-Beitline =OveraII 1300 I

I 1200 1100 1000 900 800 a) v a) S I, I 0 700 a) 4- 600 E

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0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature (°F)

Revision 1 Page 16 of 30

JAF Pressure-Temperature Limits Report Figure 3: JAF Normal Operation Core Critical (Curve C) ---40 EFPY Curve C Core Critical, Composite Curves Beftilne Bottom Head Non-Beittine OveraII 1300 T

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500 I I a)

I 0.

TJ 400 f-300 ------

I 200 Minimum Criticality 100 = 90°F 0 r ]_Temperature 0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature (°F)

Revision 1 Page 17 of 30

JAF Pressure-Temperature Limits Report Table Ia: JAF Pressure Test (Curve A) --- Beltline (40 EFPY)

Curve A Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 592.3 87.0 640.8 99.6 689.4 109.7 737.9 118.1 786.5 125.3 835.0 131.6 883.5 137.1 932.1 142.2 980.6 146.7 1029.1 150.9 1077.7 154.8 1126.2 158.3 1174.7 161.7 1223.3 164.8 1271.2 167.8 1320.3 Revision 1 Page 18 of 30

JAF Pressure-Temperature Limits Report Table Ib: JAF Pressure Test (Curve A) --- Bottom Head (All EFPY)

Curve A Pressure Test P-TCurve P-TCutve Temperature Pressure

°F psi 70.0 0.0 70.0 677.3 74.9 726.5 79.4 775.7 83.5 824.9 87.3 874.1 90.8 923.4 94.1 972.6 97.2 1021.8 100.1 1071.0 102.8 1120.2 105.4 1169.4 107.9 1218.6 110.3 1267.8 112.5 1317.0 Revision 1 Page 19 of 30

JAF Pressure-Temperature Limits Report Table Ic: JAF Pressure Test (Curve A) --- Non-Beltline (All EFPY)

Curve A Pressure Test P-TCurve P-TCurve Temperature Pressure

°F psi 70.0 0.0 70.0 312.6 120.0 312.6 120.0 1532.8 Revision 1 Page 20 of 30

JAF Pressure-Temperature Limits Report Table 2a: JAF Core Not Critical (Curve B) --- Beltline (40 EFPY)

Curve B Core Not Critical P-T Curve P-T Curve Temperature Pressure psi 70.0 0.0 70.0 279.4 76.5 320.1 82.2 360.9 87.3 401.6 103.4 450.0 115.6 498.4 125.4 546.8 133.5 595.2 140.6 643.6 146.7 692.0 152.2 740.4 157.1 788.8 161.6 837.1 165.2 885.5 169.6 933.9 173.1 982.3 176.4 1030.7 179.5 1079.1 182.4 1127.5 185.2 1175.9 187.8 1224.3 190.3 1272.7 192.7 1321.0 Revision 1 Page 21 of 30

JAF Pressure-Temperature Limits Report Table 2b: JAF Core Not Critical (Curve B) --- Bottom Head (All EFPY)

Curve B Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 491.6 76.4 540.3 82.0 589.0 87.1 637.7 91.7 686.4 96.0 735.1 99.9 783.8 103.5 832.5 106.8 881.2 110.0 929.9 113.0 978.6 115.8 1027.3 118.4 1076.0 120.9 1124.7 123.3 1173.4 125.6 1222.1 127.8 1270.8 129.9 1319.5 Revision 1 Page 22 of 30

JAF Pressure-Temperature Limits Report Table 2c: JAF Core Not Critical (Curve B) --- Non-Beitline (All EFPY)

Curve B Core Not Critical P-TCurve P-TCurve Temperature Pressure

°F psi 70.0 0.0 70.0 233.9 77.3 273.3 83.5 312.6 150.0 312.6 150.0 1382.7 Revision 1 Page 23 of 30

JAF Pressure-Temperature Limits Report Table 3a: JAF Core Critical (Curve C) --- Beltline (40 EFPY)

Curve C Core Critical P-TCurve P-TCurve Temperature Pressure

°F psi 90.0 0.0 90.0 182.0 100.0 225.9 108.4 269.8 115.5 313.8 121.8 357.7 127.3 401.6 143.4 450.0 155.6 498.4 165.4 546.8 173.5 595.2 180.6 643.6 186.7 692.0 192.2 740.4 197.1 788.8 201.6 837.1 205.8 885.5 209.6 933.9 213.1 982.3 216.4 1030.7 219.5 1079.1 222.4 1127.5 225.2 1175.9 227.8 1224.3 230.3 1272.7 232.7 1321.0 Revision 1 Page 24 of 30

JAF Pressure-Temperature Limits Report Table 3b: JAF Core Critical (Curve C) --- Bottom Head (All EFPY)

Curve C Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 90.0 0.0 90.0 373.6 99.4 423.2 107.3 472.7 114.1 522.3 120.1 571.8 125.5 621.4 130.3 671.0 134.7 720.5 138.8 770.1 142.5 819.6 146.0 869.2 149.3 918.7 152.3 968.3 155.2 1017.9 158.0 1067.4 160.5 1117.0 163.0 1166.5 165.3 1216.1 167.6 1265.7 169.7 1315.2 Revision 1 Page 25 of 30

JAF Pressure-Temperature Limits Report Table 3c: JAF Core Critical (Curve C) --- Non-Beltline (All EFPY)

Curve C Core Critical P-TCurve P-TCurve Temperature Pressure psi 90.0 0.0 90.0 155.9 101.3 195.1 110.1 234.2 117.3 273.4 123.5 312.6 190.0 312.6 190.0 1382.7 Revision 1 Page 26 of 30

JAF Pressure-Temperature Limits Report Table 4: JAF ART Calculations for 40 EFPY (Reference 6.10)

. . Adjustments For 1I4t

.. Chemistry Chemistry Flux Type & Lot Initial ARTNDT Margin Terms ART Description Code No. Heat No. Factor No. RTNDT ( F) Cu Ni

( F) (°F) a (°F) a1 (°F) (°F)

Lower Shell #1 G-3415-1R C3394-1 -10.0 0.11 0.56 73.60 35.4 17.0 0.0 59.4 Lower Shell #2 G-3415-3 C3376-2 - 24.0 0.13 0.60 91.00 43.8 17.0 0.0 101.8

. LowerShell#3 G-3415-2 C3103-2 -2.0 0.14 0.57 98.65 47.5 17.0 0.0 79.5 Lower-Int. Shell #1 G-3413-7 C3368-1 -10.0 0.12 0.50 81.00 43.5 17.0 0.0 67.5

{E}))

Lower-lnt. Shell #2 G-3414-2 C3278-2 -10.0 0.11 0.61 (( 48.1 17.0 0.0 72.1 Lower-Int. Shell #3 G-3414-1 C3301-1 -18.0 0.18 0.57 131.15 70.5 17.0 0.0 86.5

. . Adjustments For 114t

.. Chemistry Chemistry Flux Type & Lot Initial ARTNDT Margin Terms ART Description Code No. Heat No. Factor No. RTNDT ( F) Cu Ni ( F) (°F) a (°F) Gj (°F) (°F)

{E})) 14.0 0.0 112.7 L. lnt. Shell Long. Weld #1 1-233-A 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 (( 134.7

{E})) 14.0 0.0 102.4 L. lnt. Shell Long. Weld #2 1-233-B 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 (( 124.4

{E})) 14.0 0.0 112.7 0 L. lnt. Shell Long. Weld #3 1-233-C 13253/12008 Flux 1092 Lot 3947 -50.0 0.21 0.873 (( 134.7 L lnt/L Shell Girth Weld 1 240 305414 Flux 1092 Lot3947 500 0337 0609 20911 1034 280 00 1094 Lower Shell Long. Weld #1 2-233-A 27204112008 Flux 1092 Lot 3774 48.0 0.219 0.996 231.06 110.0 28.0 0.0 118.0 Lower Shell Long. Weld #2 2-233-B 27204/12008 Flux 1092 Lot 3774 -48.0 0.219 0.996 231.06 92.1 28.0 0.0 100.1 Lower Shell Long. Weld #3 2-233-C 27204/12008 Flux 1092 Lot 3774 -48.0 0.219 0.996 231.06 88.1 28.0 0.0 96.1

. . Fluence Wall Thickness (in) Attenuation, 114t Fluence at 1I4t Fluence Factor, FF at ID e24x f(O.28.O.fOIOgf)

Location Full 1!4t (nlcm2) (nlcm2)

Lower Shell #1 6.375 1.594 1 .993E+1 8 0.682 1 .359E+1 8 0.481 LowerShell#2 6.375 1.594 1.993E+18 0.682 1.359E+18 0.481

. LowerShell#3 6.375 1.594 1.993E+18 0.682 1.359E+18 0.481 Lower-Int. Shell#1 5.375 1.344 2.41E+18 0.724 1.746E+18 0.537 Lower-Int. Shell #2 5.375 1.344 2.41E+18 0.724 1.746E+18 0.537 Lower-Int. Shell#3 5.375 1.344 2.41E+18 0.724 1.746E+18 0.537 L. Int. Shell Long. Weld #1 5.375 1.344 1.348E+18 0.724 9.761E+17 0.412 L. Int. Shell Long. Weld #2 5.375 1.344 1.146E+18 0.724 8.299E+17 0.381 co L. mt. Shell Long. Weld #3 5.375 1.344 1 .348E+1 8 0.724 9.761 E+1 7 0.412 L. lnt./L. Shell Girth Weld 5.375 1.344 1.993E+18 0.724 1.444E+18 0.494 Lower Shell Long. Weld #1 5.375 1.344 1 .834E+1 8 0.724 1 .328E+1 8 0.476 Lower Shell Long. Weld #2 5.375 1.344 1.26E+18 0.724 9.125E÷17 0.399 Lower Shell Long. Weld #3 5.375 1.344 1.151E+18 0.724 8.338E+17 0.381 REDACTED EPRI REFERNCE 6.9 PROPRIETARY Page 27 of 30 INFORMATION INDICATED BY {f))J

((

JAF Pressure-Temperature Limits Report Table 5: JAF ART Calculations for NI 6 Nozzle for 40 EFPY (Reference 6.3)

Adjustments For 1/4t Chemistry Chemistry Heat Initial IRTNDT Margin ART Description Plate Location Factor No. RTNDT (°F)

Cu Ni (°F) a ci (wt %) (wt %) (°F) (°F) (°F) (°F)

>- Lower-mt shell #1

0. Nozzle N16B -10 0.12 0.50 81.00 20.5 10.2 0.0 31.0 U C3368-1 w Lower-mt Shell #2, {E}jj 0 Nozzle N16A -10 0.11 0.61 (( 22.7 11.3 0.0 35.3 C3278-2 Wall Thickness (in.) Fluence at ID Fluence @ 114t Fluence Factor, FF Location ff0.28.0.1010gf)

Full 1/4t (n/cm2) (n/cm2)

Nozzle N16B 5.375 1.344 5.63E+17 3.84E+1 7 0.253 Nozzle N16A 5.375 1.344 5.63E+1 7 3.84E÷1 7 0.253 REDACTED EPRI RFERENCE 6.9 PROPRIETARY Page 28 of 30 INFORMATION INDICATED BY {E}]J

((

JAF Pressure-Temperature Limits Report APPENDIX A JAF Reactor Vessel Material Surveillance Programs In accordance with JO CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements (Reference 6.27), two surveillance capsules have been removed from the JAF RPV. The first surveillance capsule at JAF was removed in April 1985 after 5.98 EFPY and the second capsule was removed in November 1996 after 13.4 EFPY (Reference 6.13). Both surveillance capsules contained flux wires for neutron fluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel core beitline region.

The flux wires and test specimens removed from the capsules were tested according to the latest version of ASTM El 85. The methods and results of testing are presented in Reference 6.13, as required by 10 CFR 50, Appendices G and H (References 6.12 and 6.27). There are two remaining JAF surveillance capsules (the capsule removed in 1996 was re-constituted and returned to the vessel in 1998) which will remain in place to serve as backup surveillance material for the BWRVIP program, or as otherwise needed.

JAF committed to replace its original RPV material surveillance program with the BWRVIP ISP (Reference 6.26) in the license amendment issued by the NRC regarding implementation of the BWRVIP ISP, dated July 26, 2006 (Reference 6.18), and has made a licensing commitment to use the ISP for JAF during the period of extended operation. The BWRVIP ISP meets the requirements of 10 CFR 50, Appendix H, for integrated surveillance programs, and has been approved by the NRC. Under the ISP, there are no further capsules scheduled for removal from the JAF reactor vessel.

Representative surveillance materials for the JAF target beltline plate are contained in the LaSalIe 1 surveillance capsules. The next LaSalle I surveillance capsule is scheduled to be withdrawn and tested under the ISP in approximately 2030 at 33 EFPY (Reference 6.26). Representative surveillance materials for the JAF target beltline weld Page 29 of3O

JAF Pressure-Temperature Limits Report were contained in the SSP-D and SSP-l capsules. No further SSP capsules are scheduled for withdrawal (Reference 6.26).

Page 30 of 30

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