LR-N18-0057, Pressure and Temperature Limits Report, Revision 1
| ML18159A410 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/08/2018 |
| From: | Fleming J Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18159A409 | List: |
| References | |
| LR-N18-0057, TS 6.9.1.10 | |
| Download: ML18159A410 (69) | |
Text
Enclosure 3 Contains Proprietary Information to be Withheld from Public Disclosure Pursuant to 10 CFR 2.390 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0PSEG NuclearLLC JUN 08 20t8 TS 6.9.1.10 LR-N18-0057 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) Revision 1 PSEG Nuclear LLC (PSEG) is transmitting Revision 1 of the PTLR in accordance with Hope Creek Generating Station (HCGS) Technical Specification (TS) 6.9.1.10. Revision 1 of the PTLR was issued as a result of the increase in maximum licensed thermal power level approved by the NRC in Hope Creek Amendment No. 212 on April 24, 2018. provides Revision 1 of the Hope Creek PTLR (Non-Proprietary). Enclosure 2 includes an affidavit from Electric Power Research Institute (EPRI) requesting withholding the proprietary information from public disclosure. Enclosure 3 provides Revision 1 of the Hope Creek PTLR (Proprietary) to be withheld from public disclosure under 10 CFR 2.390(a)(4). contains proprietary information as defined by 10 CFR 2.390(a)(4). EPRI, as the owner of the proprietary information, has executed the Enclosure 2 affidavit identifying that the proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. EPRI requests that the proprietary information in Enclosure 3 be withheld from public disclosure, in accordance with the requirements of 10 CFR 2.390(a)(4).
No new regulatory commitments are established by this submittal. If you have any questions or require additional information, please do not hesitate to contact Mr. Brian Thomas at (856) 339-2022.
Enclosure 3 Contains Proprietary Information to be JUN 0'8 2018 Withheld from Public Disclosure Pursuant to 10 CFR 2.390 Page 2 TS 6.9.1.10 LR-N18-0057 Respectfully, Je n Fleming Director- Site Regulatory Compliance
Enclosures:
- 1. Hope Creek Pressure and Temperature Limits Report Revision 1 (Non-Proprietary)
- 3. Hope Creek Pressure and Temperature Limits Report Revision 1 (Proprietary) cc: Administrator, Region I, NRC NRC Project Manager, Hope Creek NRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Chief, NJBNE Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. T. MacEwen, Hope Creek Commitment Tracking Coordinator LR-N18-0057 Hope Creek Pressure and Temperature Limits Report Revision 1 Non-Proprietary This is the non-proprietary version of Enclosure 3 of this letter which has the proprietary information removed. Portions of the document that have been removed are indicated by white space inside open and closed brackets as shown here ((.
PSEG Nuclear LLC Hope Creek Generating Station Pressure and Temp erature Limits Report (PTLR) for 32, 44, and 56 Effective Full-Power Years (EFPY) Revision 1-NP Prepared by: f:J,,..-evr._.g 1 Date: S 1 -:t ; \1-- Donnamarie Bush
*. Creek Engineeri Programs]
Reviewed y Date: ttf;/o Anthony Tramontana [Manager, Egineering Programs] Approved by: c* Date: "l-it 12 chick [Director, Engineering]
Hope Creek Generating Station PTLR Revision 1-NP Page 2 of 61 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 14 Figure 1 HCGS P-T Curve A (Hydrostatic Pressure and Leak Tests) for 32 EFPY 18 Figure 2 HCGS P-T Curve B (Normal Operation - Core Not Critical) for 32 EFPY 19 Figure 3 HCGS P-T Curve C (Normal Operation - Core Critical) for 32 EFPY 20 Figure 4 HCGS P-T Curve A (Hydrostatic Pressure and Leak Tests) for 44 EFPY 21 Figure 5 HCGS P-T Curve B (Normal Operation - Core Not Critical) for 44 EFPY 22 Figure 6 HCGS P-T Curve C (Normal Operation - Core Critical) for 44 EFPY 23 Figure 7 HCGS P-T Curve A (Hydrostatic Pressure and Leak Tests) for 56 EFPY 24 Figure 8 HCGS P-T Curve B (Normal Operation - Core Not Critical) for 56 EFPY 25 Figure 9 HCGS P-T Curve C (Normal Operation - Core Critical) for 56 EFPY 26 Figure 10 HCGS Feedwater Nozzle 2-D Finite Element Model for Thermal Stress [24] 27 Figure 11 HCGS Feedwater Nozzle 3-D Finite Element Model for Pressure Stress [26] 28 Figure 12 HCGS Instrument Nozzle Finite Element Model [19] 29 Table 1 HCGS Pressure Test (Curve A) P-T Curves for 32 EFPY 30 Table 2 HCGS Core Not Critical (Curve B) P-T Curves for 32 EFPY 33 Table 3 HCGS Core Critical (Curve C) P-T Curves for 32 EFPY 36 Table 4 HCGS Pressure Test (Curve A) P-T Curves for 44 EFPY 39 Table 5 HCGS Core Not Critical (Curve B) P-T Curves for 44 EFPY 42 Table 6 HCGS Core Critical (Curve C) P-T Curves for 44 EFPY 45 Table 7 HCGS Pressure Test (Curve A) P-T Curves for 56 EFPY 48 Table 8 HCGS Core Not Critical (Curve B) P-T Curves for 56 EFPY 51 Table 9 HCGS Core Critical (Curve C) P-T Curves for 56 EFPY 54 Table 10 HCGS ART Calculations for 32 EFPY 57 Table 11 HCGS ART Calculations for 44 EFPY 58 Table 12 HCGS ART Calculations for 56 EFPY 59 Table 13 Nozzle Stress Intensity Factors 60 Appendix A Hope Creek Reactor Vessel Materials Surveillance Program 61
Hope Creek Generating Station PTLR Revision 1-NP Page 3 of 61 1.0 Purpose The purpose of the Hope Creek Generating Station (HCGS) Pressure and Temperature Limits Report (PTLR) is to present operating limits relating to:
- 1. Reactor Coolant System (RCS) Pressure versus Temperature limits during Heat-up, Cool-down and Hydrostatic/Class 1 Leak Testing;
- 2. RCS Heat-up and Cool-down rates;
- 3. RPV head flange boltup temperature limits.
This report has been prepared in accordance with the requirements of Licensing Topical Reports SIR-05-044, Revision 1-A, contained within BWROG-TP-11-022-A, Revision 1 [1]. 2.0 Applicability This report is applicable to the HCGS RPV for up to 32, 44, and 56 Effective Full-Power Years (EFPY). The following HCGS Technical Specifications (TS) are affected by the information contained in this report: TS 3.4.6 RCS Pressure/Temperature (P-T) Limits TS 4.4.6 Surveillance Requirements
Hope Creek Generating Station PTLR Revision 1-NP Page 4 of 61 3.0 Methodology The limits in this report were derived as follows:
- 1. The methodology used is in accordance with Reference [1], Pressure - Temperature Limits Report Methodology for Boiling Water Reactors, August 2013, incorporating the NRC Safety Evaluation in Reference [2].
- 2. The neutron fluence is calculated in accordance with NRC Regulatory Guide 1.190 (RG 1.190) [3], using the RAMA computer code, as documented in Reference [4].
- 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) [5], as documented in Reference [6].
- 4. The pressure and temperature limits, which were calculated in accordance with Reference
[1], are documented in Reference [7].
- 5. This revision of the pressure and temperature limits report is to incorporate the following changes:
Revision 0: Initial issue of PTLR. Revision 1: Updated fluence for 1.6% power uprate conditions. 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 [8], provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance. Changes to the curves, limits, or parameters within this PTLR, based upon new surveillance capsule data of the RPV or other plant design assumption modifications in the UFSAR, cannot
Hope Creek Generating Station PTLR Revision 1-NP Page 5 of 61 be made without prior NRC approval. Such analysis and revisions shall be submitted to the NRC for review prior to incorporation into the PTLR. 4.0 Operating Limits The pressure-temperature (P-T) curves included in this report represent steam dome pressure versus minimum vessel metal 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, referred to as Curve B; and (c) core critical operation, referred to as Curve C. Complete P-T curves were developed for 32, 44, and 56 EFPY for HCGS, as documented in Reference [7]. The HCGS P-T curves for 32 EFPY are provided in Figures 1 through 3, for 44 EFPY are in Figures 4 through 6, and for 56 EFPY are in Figures 7 through 9. A tabulation of the curves is included in Tables 1 through 3 for 32 EFPY, Tables 4 through 6 for 44 EFPY, and Tables 7 through 9 for 56 EFPY. The adjusted reference temperature (ART) tables for the HCGS vessel beltline materials are shown in Table 10 for 32 EFPY, Table 11 for 44 EFPY, and Table 12 for 56 EFPY [6]. The resulting P-T curves are based on the geometry, design and materials information for the HCGS vessel with the following conditions: Heat-up/Cool-down rate limit during Hydrostatic Class 1 Leak Testing (Figures 1, 4, and 7: Curve A): 25F/hour1 [7]. 1 Interpreted as the temperature change in any 1-hour period is less than or equal to 25°F.
Hope Creek Generating Station PTLR Revision 1-NP Page 6 of 61 Normal Operating Heat-up/Cool-down rate limit (Figures 2, 5, and 8: Curve B - non-nuclear heating, and Figures 3, 6, and 9: Curve C - nuclear heating): 100F/hour2 [7]. RPV bottom head coolant temperature to RPV coolant temperature T limit during Recirculation Pump startup: 145F [1]. Recirculation loop coolant temperature to RPV coolant temperature T limit during Recirculation Pump startup: 50F [1]. RPV flange and adjacent shell temperature limit 79F [7]. To address the NRC condition regarding lowest service temperature in Reference [2, Section 4.0], the minimum temperature is set to 79°F, which is equal to RTNDT,max + 60°F. This value is consistent with the minimum temperature limits and minimum bolt-up temperature in the current docketed P-T curves [9] (approved for use by the NRC in Reference [10]) and bounds the minimum temperature in the first set of P-T limits approved for initial operation [11]. 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. RG 1.99 [5] 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 HCGS vessel plate, weld, and forging materials [6]. This evaluation included the results of two surveillance capsules for the representative plate and weld materials. The Cu and Ni values were used with Table 1 of RG 1.99 to determine a chemistry factor (CF) per Paragraph 1.1 of RG 1.99 for welds. The Cu and Ni values were used with Table 2 of RG 1.99 to determine a CF per 2 Interpreted as the temperature change in any 1-hour period is less than or equal to 100°F.
Hope Creek Generating Station PTLR Revision 1-NP Page 7 of 61 Paragraph 1.1 of RG 1.99 for plates and forgings. However, for materials where surveillance data exists (i.e. HCGS plate heat no. 5K3238/1 and weld heat no. D53040), a fitted CF has been used in the calculation of ART for those heats, in accordance with Regulatory Position 2.1 in RG 1.99 [5]. Use of surveillance data from the BWRVIP ISP for HCGS was approved by the NRC in Reference [12]. The peak RPV ID fluence values of 8.86 x 1017 n/cm2 at 32 EFPY, 1.27 x 1018 n/cm2 at 44 EFPY, and 1.65 x 1018 n/cm2 at 56 EFPY used in the P-T curve evaluation were obtained from Reference [6] (interpolated from the fluence values at 24.1 and 56 EFPY in Reference [4]). Fluence values in Reference [4] were calculated in accordance with RG 1.190 [3]. These fluence values apply to the limiting beltline lower intermediate shell plates (heat nos. 5K2963/1, 5K2530/1, and 5K3238/1). A plant-specific damage assessment, in terms of displacements per atom (dpa), was performed to determine through-wall fluence for HCGS in Reference [4], as permitted by RG 1.99 [5]. The resulting attenuation factor is 0.70 for a postulated 1/4T flaw. Consequently, the 1/4T fluence for 32, 44, and 56 EFPY for the limiting lower intermediate shell plates are 6.15 x 1017 n/cm2, 8.83 x 1017 n/cm2, and 1.15 x 1018 n/cm2, respectively, for HCGS. The limiting value for ART is 90.5°F at 32 EFPY, 103.6°F at 44 EFPY, and 114.3°F at 56 EFPY [6]. The P-T limits are developed to bound all ferritic materials in the RPV, including the consideration of stress levels from structural discontinuities such as nozzles. HCGS has two sets of nozzles in the RPV beltline: the instrument (N16) and low pressure coolant injection (LPCI, N17) nozzles are located in the intermediate shell beltline plates [13]. The feedwater (FW) nozzle is considered in the evaluation of the non-beltline (upper vessel) region P-T limits. The limiting LPCI (N17) nozzles have an RPV ID fluence of 1.71 x 1017 n/cm2 at 56 EFPY, obtained from Reference [4] and calculated in accordance with RG 1.190 [3]. Similar to the RPV beltline plates and welds described above, through-wall fluence for the LPCI nozzles was
Hope Creek Generating Station PTLR Revision 1-NP Page 8 of 61 attenuated using the dpa methodology in Reference [4]. The resulting attenuation factor is 0.82 for a postulated 1/4T flaw in the LPCI nozzle blend radius. Consequently, the 1/4T fluence for 56 EFPY for the limiting LPCI nozzle location is 1.40 x 1017 n/cm2. The limiting value for ART is 8.8°F at 56 EFPY [6]. Comparing the limiting ART value of the LPCI nozzles with the initial RTNDT for non-beltline nozzles, 40°F, the non-beltline nozzles are more limiting. This assumption is further supported when comparing nozzle transients, where the FW nozzle, outside the beltline, experiences more severe thermal transients. Therefore, the P-T curves developed for the FW nozzle bound the LPCI nozzles. Due to this bounding assumption, LPCI nozzle evaluations should use the upper vessel P-T curve limits. The instrument (N16) nozzle material is ferritic and is welded to the RPV using a partial penetration weld. The effect of the penetration on the adjacent shell is considered in the development of bounding beltline P-T limits as described in Reference [7]. The N16 nozzles have a limiting RPV ID fluence of 1.90 x 1017 n/cm2 at 32 EFPY, 2.63 x 1017 n/cm2 at 44 EFPY, and 3.37 x 1017 n/cm2 at 56 EFPY [6]. This fluence value applies to the adjacent intermediate shell plates in which the nozzles are located. Similar to the RPV beltline plates and welds described above, through-wall fluence for the N16 nozzles was attenuated using the dpa methodology in Reference [4]. The resulting attenuation factor is 0.84 for a postulated 1/4T flaw in the N16 nozzle corner. Consequently, the 1/4T fluence for 32, 44, and 56 EFPY for the limiting N16 nozzle location is 1.59 x 1017 n/cm2, 2.22 x 1017 n/cm2, and 2.84 x 1018 n/cm2, respectively, for HCGS. The limiting value for ART of the N16 nozzles is 52.6°F at 32 EFPY, 60.3°F at 44 EFPY, and 67.0°F at 56 EFPY [6]. 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 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 cool-down and is in the outer wall during heat-up. However, as a
Hope Creek Generating Station PTLR Revision 1-NP Page 9 of 61 conservative simplification, the thermal gradient stresses at the 1/4T location are assumed to be tensile for both heat-up and cool-down. 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 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, and for a given pressure, the coolant saturation temperature is well above the P-T curve limiting temperature. Consequently, the material toughness at a given pressure would exceed the allowable toughness. For the core not critical curve (Curve B) and the core critical curve (Curve C), the P-T curves specify a coolant heat-up and cool-down temperature rate of 100°F/hour for which the curves are applicable. However, the core not critical and the core critical curves were also developed to bound Service Level A/B RPV thermal transients. For the hydrostatic pressure and leak test curve (Curve A), a coolant heat-up and cool-down temperature rate of 25°F/hour 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 heat-up/cool-down rate limits cannot be maintained. The initial RTNDT, 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/cm2 for E > 1MeV) are shown in Tables 10, 11, and 12 for 32, 44, and 56 EFPY, respectively [6]. Use of initial RTNDT values in the determination of P-T curves for HCGS was approved by the NRC in Reference [14]. Per Reference [6] and in accordance with Appendix A of Reference [1], the HCGS representative weld and plate surveillance materials data were reviewed from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) [15, 16].
Hope Creek Generating Station PTLR Revision 1-NP Page 10 of 61 The representative heat of the plate material (5K3238/1) in the ISP is not the same as the target plate material (5K3025/1) for HCGS. However, the surveillance heat 5K3238/1 does exist in the HCGS vessel beltline, and there are two irradiated data sets for this plate. For plate heat 5K3238/1, since the scatter in the fitted results is less than 1-sigma (17°F) [16], the data is credible per Reference [5], and a reduced margin term ( = 17°F/2 = 8.5°F) is used for the plate material when calculating the ART. The representative heat of the weld material (D53040) in the ISP is the same as the limiting weld material in the vessel beltline region of HCGS. Per Reference [16], scatter in the surveillance data exceeds the credibility criteria for weld heat D53040, however, the fitted CF bounds the RG 1.99 CF. Therefore, the higher surveillance-based CF is used in the ART calculation for weld heat no. D53040, with a full margin term ( = 28°F). The RG 1.99 table CFs were used in the determination of the ART values for all HCGS beltline materials except for plate heat 5K3238/1 and weld heat D53040. The only computer code used in the determination of the HCGS P-T curves was the ANSYS finite element computer program: ANSYS, Release 8.1 (Service Pack 1) [17] for: o FW nozzle (non-beltline) through-wall thermal stress distributions in Reference [18]. o Instrument nozzle thermal and pressure stress distributions in Reference [19]. ANSYS Mechanical APDL and PrepPost, Release 11.0 (Service Pack 1) [20] for the FW nozzle (non-beltline) pressure stress distribution in Reference [21]. ANSYS finite element analyses were used to develop the stress distributions through the FW and instrument nozzles, and these stress distributions were used in the determination of the stress intensity factors for these nozzles [18, 19, 21]. At the time that each of the analyses above was performed, the ANSYS program was controlled under the vendors 10 CFR 50 Appendix B [22] Quality Assurance Program for nuclear quality-related work. Benchmarking consistent with NRC GL 83-11, Supplement 1 [23] was performed as a part of the computer program
Hope Creek Generating Station PTLR Revision 1-NP Page 11 of 61 verification by comparing the solutions produced by the computer code to hand calculations for several problems. The plant-specific HCGS FW nozzle analyses were performed to determine through-wall pressure stress distributions and thermal stress distributions due to bounding thermal transients. Detailed information regarding the analyses can be found in References [18] and [21]. The following summarizes the development of the thermal and pressure stress intensity factors for the FW nozzle: A two-dimensional axisymmetric finite element model of the FW nozzle was constructed for the determination of thermal stresses (Figure 10). Details of the model and material properties are provided in Reference [24]. Temperature-dependent material properties were based on the ASME Code, Section II, Part D, 2001 Edition through 2003 Addenda [25]. Heat transfer coefficients were calculated in Reference [24] and are a function of FW temperature and flow rate. Potential leakage past the primary thermal sleeve is considered in the heat transfer calculations. With respect to operating conditions, the bounding thermal transients during normal and upset operating conditions were analyzed [18]. The thermal stress distribution, corresponding to the limiting time presented in Reference [18], along a linear path through the nozzle corner is used. The boundary integral equation/influence function (BIE/IF) methodology presented in Reference [1] was used to calculate the thermal stress intensity factor, KIt, by fitting a third order polynomial equation to the path stress distribution for the thermal load case. A three-dimensional finite element model of the FW nozzle was constructed (Figure 11) for the determination of pressure stresses. Details of the model and material properties are provided in Reference [26]. Material properties were based on the ASME Code, Section II, Part D, 2001 Edition through 2003 Addenda [25]. The properties were taken at a
Hope Creek Generating Station PTLR Revision 1-NP Page 12 of 61 temperature of 350°F, which is the approximate average service temperature of the FW nozzle at HCGS [21]. The use of temperature-independent material properties is consistent with design basis documents. Use of temperature-dependent material properties is expected to have minimal impact on the results of the analysis. With respect to pressure stress, a unit pressure of 1000 psig was applied to the internal surfaces of the 3-D model in Reference [21]. The pressure stress distribution was taken along a linear path through the nozzle corner. The BIE/IF methodology presented in Reference [1] was used to calculate the applied pressure stress intensity factor, KIp, by fitting a third order polynomial equation to the path stress distribution for the pressure load case. The resulting KIp may be linearly scaled to determine the KIp for various RPV internal pressures. The plant-specific HCGS instrument nozzle analysis was performed to determine through-wall pressure stress distributions and thermal stress distributions due to bounding thermal transients. Detailed information regarding the analysis can be found in Reference [19]. The following summarizes the development of the thermal and pressure stress intensity factors for the instrument nozzle: A one-quarter symmetric, three-dimensional finite element model of the instrument nozzle was constructed and is shown in Figure 12. Temperature-dependent material properties, taken from the ASME Code, Section II, Part D, 2001 Edition with 2003 Addenda edition [25], were used in the evaluation and are described in Reference [27]. With respect to operating conditions, the bounding thermal transient for the region corresponding to the instrument nozzles during normal and upset operating conditions was analyzed [19]. The thermal stress distribution, corresponding to the limiting time in Reference [19], along a linear path through the nozzle corner is used. The BIE/IF methodology presented in Reference [1] was used to calculate the thermal stress intensity
Hope Creek Generating Station PTLR Revision 1-NP Page 13 of 61 factor, KIT, due to the thermal stresses by fitting a third order polynomial equation 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 [19]. With respect to pressure stress, a unit pressure of 1000 psig was applied to the internal surfaces of the finite element model (FEM) [19]. The pressure stress distribution was taken along the same path as the thermal stress distribution. The BIE/IF methodology presented in Reference [1] is used to calculate the pressure stress intensity factor, KIP, by fitting a third order polynomial equation to the path stress distribution for the pressure load case. The resulting KIP can be linearly scaled to determine the KIP for various RPV internal pressures
Hope Creek Generating Station PTLR Revision 1-NP Page 14 of 61 6.0 References
- 1. BWROG-TP-11-022-A, Revision 1, Pressure Temperature Limits Report Methodology for Boiling Water Reactors, August 2013. (ADAMS Accession No. ML13277A557)
- 2. 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. ML13277A557).
- 3. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence, March 2001.
- 4. TransWare Report No. PSE-FLU-005-R-001, Revision 0, Hope Creek Nuclear Generating Station Unit 1 Reactor Pressure Vessel Fluence Evaluation at End of Cycle 19 with Projections to 56 EFPY, February 27, 2017, SI File No. 1700220.201.
- 5. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.
- 6. Structural Integrity Associates Calculation No. 1601009.301, Revision 1, Hope Creek RPV Beltline ART Evaluation, March 27, 2017.
- 7. Structural Integrity Associates Calculation No. 1601009.303, Revision 1, Hope Creek Updated P-T Curve Calculation for 32, 44, and 56 EFPY, March 27, 2017.
- 8. U.S. Code of Federal Regulations, Title 10, Part 50, Section 59, Changes, tests and experiments, August 28, 2007.
- 9. Attachment 3 to PSEG Letter No. LR-N04-0136, dated March 31, 2004, SI Report No.
SIR-00-136, Revision 1, Revised Pressure-Temperature (P-T) Curves for Hope Creek, March 23, 2004. (ADAMS Accession No. ML040990522)
Hope Creek Generating Station PTLR Revision 1-NP Page 15 of 61
- 10. Hope Creek License Amendment No. 157, Change of Pressure-Temperature Limits and Extension of Validity to 32 Effective Full-Power Years, dated November 1, 2004. (TAC No. MC2534, ADAMS Accession No. ML042050079)
- 11. PSEG Design Information Transmittal No. H-TODI-2016-0066, dated November 14, 2016. SI File No. 1601009.201.
- 12. Hope Creek License Amendment No. 151, Revision to the Reactor Pressure Vessel Material Surveillance Program, dated July 23, 2004. (TAC No. MB7151, ADAMS Accession No. ML033230591)
- 13. PSEG Document No. VTD 431282, SI Calculation No. 0800118.317, Revision 0, Validation of Beltline Materials, September 12, 2008.
- 14. Hope Creek Generating Station, Issuance of Amendment 88 (TAC No. M93054, ADAMS Accession No. ML011760521), November 28, 1995.
- 15. BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations. EPRI, Palo Alto, CA: 2014.
3002003144. EPRI PROPRIETARY INFORMATION.
- 16. EPRI Letter 2017-017, Final BWRVIP Integrated Surveillance Program (ISP) Data Applicable to Hope Creek Generating Station, January 19, 2017. EPRI PROPRIETARY INFORMATION.
- 17. ANSYS, Release 8.1 (w/ Service Pack 1), ANSYS Inc., June 2004.
- 18. PSEG Document No. VTD 327370, Structural Integrity Associates Calculation No. HC-05Q-304, Revision 2, Feedwater Nozzle (N4A through N4F) Thermal and Stress Analysis, October 22, 2009.
- 19. PSEG Document No. VTD 431277, Structural Integrity Associates Calculation No.
0800118.311, Revision 1, Stress Analysis of Reactor Pressure Vessel 2" Instrument Nozzles N16A through N16D, October 29, 2009.
Hope Creek Generating Station PTLR Revision 1-NP Page 16 of 61
- 20. ANSYS Mechanical and PrepPost, Release 11.0 (w/ Service Pack 1), ANSYS, Inc.,
August 2007.
- 21. PSEG Document No. VTD 432637, Structural Integrity Associates Calculation No.
1200619.305, Revision 0, Greens Function Analysis of Feedwater Nozzle, March 19, 2015.
- 22. U.S. Code of Federal Regulations, Title 10, Energy, Part 50, Appendix B, Quality Assurance for Nuclear Power Plants and Fuel Reprocessing Plants.
- 23. U.S. Nuclear Regulatory Commission, Generic Letter 83-11, Supplement 1, License Qualification for Performing Safety Analyses, June 24, 1999.
- 24. PSEG Document No. VTD 327367, Structural Integrity Associates Calculation No. HC-05Q-301, Revision 3, Feedwater Nozzle (N4A through N4F) Finite Element Model and Heat Transfer Coefficients, June 4, 2010.
- 25. ASME Boiler and Pressure Vessel Code, Section II, Part D, Material Properties, 2001 Edition with Addenda through 2003.
- 26. PSEG Document No. VTD 431269, Structural Integrity Associates Calculation No.
0800118.303, Revision 1, Feedwater Nozzle (N4A through N4F) Finite Element Model, October 19, 2009.
- 27. PSEG Document No. VTD 431267, Structural Integrity Associates Calculation No.
0800118.301, Revision 0, Material Properties and Methodology of Heat Transfer Coefficient Calculation for Hope Creek Environmental Fatigue Evaluation, May 30, 2008.
- 28. U.S. Code of Federal Regulations, Title 10, Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, January 31, 2008.
- 29. GE Nuclear Energy Report No. GE-NE-523-A164-1294R1, Hope Creek Generating Station RPV Surveillance Materials Testing and Fracture Toughness Analysis, December 1997. SI File No. PSEG-10Q-201P. GE PROPRIETARY INFORMATION.
Hope Creek Generating Station PTLR Revision 1-NP Page 17 of 61
- 30. BWRVIP- 298NP: BWR Vessel and Internals Project: Testing and Evaluation of the Hope Creek 120° Capsule, EPRI, Palo Alto, CA: 2014. 3002007844. SI File No.
1601009.201.
- 31. 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.
Hope Creek Generating Station PTLR Revision 1-NP Page 18 of 61 Figure 1: HCGS P-T Curve A (Hydrostatic Pressure and Leak Tests) for 32 EFPY C.urve A -*PressureTest, Composite Curves
-Beltline ---Bottom Head *
- - Non-8eltJine -overall
- - r--(r/f--- ,_
1300
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Minimum BoltUp t l i r Temperature 79°F
) ;
=
i 0 100 150 200 250 Minimum Reactor Vessel MetaiJemperature (°F)
Hope Creek Generating Station PTLR Revision 1-NP Page 19 of61 Figure 2: HCGS P-T Curve B (Normal Operation- Core Not Critical) for 32 EFPY Curve B ... Core Not Critical, Composite Curves
-Beltline --- Bottom Head - Non-Beltline -overall 1300 1200 1100 1000 900 -;a 'iii .e: 800 Gi Ill Ill cu 0 700 u
ftl cu a:
.5 .... 600 *e cu Ill Ill 500 cu 1-****** *+* ******* ;* ******+** ** ** *l** *** ***'i*** * * **' * *****+ *** * ......
400 300 200 0
***** ****** ** ************'* * * * *1** ********* ****** **'**..*"'* *'"'***** *1 i
r! Minimum Bolt-Up i l. Temperature= 79°F 0 so 100 150 200 250 Minimum Reactor Vessel Metal Temperature {°F)
Hope Creek Generating Station PTLR Revision 1-NP Page 20 of61 Figure 3: HCGS P-T Curve C (Normal Operation- Core Critical) for 32 EFPY Curve C .. Core Critical, Composite Curves
-Beltline --- Bottom Head - Non-Beltline -overall 1300 1200 1100 900 Minimum Core Critical Temperature= 79°F 0 50 100 150 200 250 Minimum Reactor Vessel MetaJ Temperature (°F}
Hope Creek Generating Station PTLR Revision 1-NP Page 21 of 61 Figure 4: HCGS P-T Curve A (Hydrostatic Pressure and Leak Tests) for 44 EFPY Curve A - Pressure Test, Composite Curves
-Beltline --- Bottom Head - - Non-Beltline -overall 1300 1200 1100 1000 900 "iii .S: 800 a;
Ill Ill cu
- c 0 700 t .,.f u
L
' J ftl cu J-*-* >**"""'"' "*"* <- **- +**-- 1***-, ..o. ...... .. ... . ...-.- - ...... ,._ .. .. -. ..* r--***-*--*i-**'"""" i**"* *-- +***""-*>****"") ********i**-**-*' ""*' +'*"-'"*+ *""' _.;...... c.;..- .. ,*+***-**1 a: .5 600 'i§ cu Ill Ill 500 cu Is:. ! * ****** ** '* ****** * * * *!** ****** ** * ****** ** * ********* * ... . .. .... 1 **** * ** ;**** * * * * * *!****** * * * * !** ** ** **
- 1 *** * >* * + * * ** :,
400 300 200 100 0 0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature {°F}
Hope Creek Generating Station PTLR Revision 1-NP Page 22 of61 Figure 5: HCGS P-T Curve B (Normal Operation- Core Not Critical) for 44 EFPY Curve B - Core Not Critical, Composite Curves
-Beltline --- Bottom Head - - Non-Beltline -overall 1300 1200 1100 1000 900 iii .a 800 Gi Ill Ill CD 0 700 u
ca
.5 .... 600 "j§
- i CD
- I Ill 500 Ill CD
/;;.
400 l l 300
/ . !
.,,**+-,,**>>,.,.'""'"'w****"""' )- .,.,.,,.,.,.***"w'"'""'****'""{ww""0'.-""'"0'+'**)*.,*<**u>>l 200 i
... , .. ..; ...) . ....
100 Minimum Bolt-Up i Temperature= 79°F 0 0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature (°F}
Hope Creek Generating Station PTLR Revision 1-NP Page 23 of 61 Figure 6: HCGS P-T Curve C (Normal Operation- Core Critical) for 44 EFPY Curve C - Core Critical, Composite Curves
-Beltline --- Bottom Head - Non-Beltline -overall 1300 1200 1100 1000 900 iii .S: 800 Gi ut ut cu 0
700 u nJ cu a:
.5 ... 600 *e
- i cu Ill ut 500 cu 6:.
400 300 200 100 0 0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature {°F)
Hope Creek Generating Station PTLR Revision 1-NP Page 24 of61 Figure 7: HCGS P-T Curve A (Hydrostatic Pressure and Leak Tests) for 56 EFPY Curve A - Pressure Tet, Composite Curves
- Beltline ---Bottom Head - - Non-Beltline --..overall 1300 1200
, +1+ ! -- '..,.,,.,+*w.*. ****\"""'**l'" *'*'*'*'f'""""'\"'"'">"'""i-"""'*"'
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* ** ** ***! * ** **** * * * * *** ** -+-+---t-1--+-+---+- -+--1 1000
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900
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700 u Ill C1l a:: i l [ v
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---* *'II!**!!V "<"*'" .. ;:""'**"'*l 400 300 200 100 Minimum Bolt-Up Temperature= 79°F 0
0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature (°F)
Hope Creek Generating Station PTLR Revision 1-NP Page 25 of 61 Figure 8: HCGS P-T Curve B (Normal Operation- Core Not Critical) for 56 EFPY Curve B - Core Not Critical, Composite Curves
-Beltline ---Bottom Head - Non-Beltline -overall 1300 1200
******* *-;-** ****** *** ******* **********i* ** *****i***** ****f
)
1100 1000 900 tiii "iii
.9: 800 Qi 11'1 11'1 Q.l (5 700 ca Q.l a:
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r t r Q.l 11'1 11'1 500 Q.l I i i
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200 --+--+---r----r--+-- 100 Minimum Bolt-Up Temperature = 79°F 0 0 so 100 150 200 250 Minimum Reactor Vessel Metal Temperature (°F)
Hope Creek Generating Station PTLR Revision 1-NP Page 26 of 61 Figure 9: HCGS P-T Curve C (Normal Operation- Core Critical) for 56 EFPY Curve C- Core Critical, Composite Curves
-Beltline ---Bottom Head - - Non-Beltline -overall 1300 1200 1100 1000 900 bi *;a .S: 800 Gi Ill Ill Ql 0
700 u ca Ql a:
!*- tlr ---!- + ,' .... 600 *e
- I -n .. .. * ': ' - * -- -- .*- ------ --------I -** ... **** * --*- -*------ --- ------- ---**---*---------- -*- ---------- .. ,
Ql
-----*--------- * -- ----"* *----*-** **-"**+ -- ------- -----------*-- --------->-------**-------*-* -- --
Ill 500 ; ;; czr. l j Ill Ql r tr 6:. J
+-------------------+*__ -
--- ____-+__ - -
400
,..,..,, ,+*-w.*w*+-*- <* "'""- '"'+*- -***.-.* *+ ..... ... ...... ...... .. .,.... .... *"*"'l ............ ****,*---*--**** 1 l *"'!"'"' r*
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. --* l j+,
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, ... .. ...... .. .. ... (.. .. ...... (. . .. ..... .,.. .... .. .. , ........ .. ;
. . ...... . .."' .......... (... ....... !
100 Minimum Core Critical Temperature = 79°F 0 0 50 100 150 200 250 Minimum Reactor Vessel Metal Temperature (°F)
Hope Creek Generating Station PTLR Revision 1-NP Page 27 of 61 Figure 10: HCGS Feedwater Nozzle 2-D Finite Element Model for Thermal Stress [24]
Hope Creek Generating Station PTLR Revision 1-NP Page 28 of 61 Figure 11: HCGS Feedwater Nozzle 3-D Finite Element Model for Pressure Stress [26]
Hope Creek Generating Station PTLR Revision 1-NP Page 29 of 61 Figure 12: HCGS Instrument Nozzle Finite Element Model [19]
Hope Creek Generating Station PTLR Revision 1-NP Page 30 of 61 Table 1: HCGS Pressure Test (Curve A) P-T Curves for 32 EFPY Beltline Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 497.3 87.1 542.8 94.1 588.4 100.3 633.9 105.7 679.5 110.7 725.0 115.1 770.5 119.2 816.1 123.0 861.6 126.6 907.2 129.9 952.7 134.1 999.6 137.9 1046.6 141.5 1093.5 144.9 1140.5 148.0 1187.4 151.0 1234.4 153.8 1281.3 156.4 1328.3
Hope Creek Generating Station PTLR Revision 1-NP Page 31 of 61 Table 1: HCGS Pressure Test (Curve A) P-T Curves for 32 EFPY (continued) Non-Beltline Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 312.6 109.0 312.6 109.0 815.1 113.1 864.9 116.9 914.8 120.4 964.7 123.7 1014.5 126.8 1064.4 129.7 1114.2 132.4 1164.1 135.0 1214.0 137.5 1263.8 139.8 1313.7
Hope Creek Generating Station PTLR Revision 1-NP Page 32 of 61 Table 1: HCGS Pressure Test (Curve A) P-T Curves for 32 EFPY (continued) Bottom Head Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 693.7 84.3 742.0 89.1 790.3 93.4 838.6 97.4 886.9 101.1 935.2 104.6 983.5 107.8 1031.8 110.9 1080.1 113.7 1128.4 116.4 1176.6 119.0 1224.9 121.4 1273.2 123.8 1321.5
Hope Creek Generating Station PTLR Revision 1-NP Page 33 of 61 Table 2: HCGS Core Not Critical (Curve B) P-T Curves for 32 EFPY Beltline Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 197.0 90.1 245.1 99.2 293.3 106.9 341.4 113.5 389.5 119.4 437.6 124.7 485.7 129.4 533.8 133.8 581.9 137.8 630.1 141.5 678.2 144.9 726.3 148.1 774.4 151.2 822.5 155.0 871.9 158.6 921.2 161.9 970.6 165.1 1020.0 168.0 1069.3 170.8 1118.7 173.4 1168.1 175.9 1217.4 178.3 1266.8 180.6 1316.2
Hope Creek Generating Station PTLR Revision 1-NP Page 34 of 61 Table 2: HCGS Core Not Critical (Curve B) P-T Curves for 32 EFPY (continued) Non-Beltline Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 133.7 87.5 178.4 94.8 223.2 101.1 267.9 106.8 312.6 139.0 312.6 139.0 692.3 141.9 740.7 144.7 789.0 147.3 837.4 149.8 885.8 152.2 934.2 154.5 982.5 156.7 1030.9 158.7 1079.3 160.7 1127.6 162.7 1176.0 164.5 1224.4 166.3 1272.8 168.0 1321.1
Hope Creek Generating Station PTLR Revision 1-NP Page 35 of 61 Table 2: HCGS Core Not Critical (Curve B) P-T Curves for 32 EFPY (continued) Bottom Head Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 445.5 86.0 494.1 92.1 542.7 97.5 591.3 102.4 639.9 106.9 688.4 111.0 737.0 114.8 785.6 118.3 834.2 121.6 882.8 124.7 931.4 127.6 980.0 130.3 1028.6 133.0 1077.1 135.4 1125.7 137.8 1174.3 140.0 1222.9 142.2 1271.5 144.3 1320.1
Hope Creek Generating Station PTLR Revision 1-NP Page 36 of 61 Table 3: HCGS Core Critical (Curve C) P-T Curves for 32 EFPY Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 90.6 101.3 139.4 116.7 188.2 128.4 237.0 137.9 285.7 145.9 334.5 152.7 383.3 158.8 432.1 164.2 480.9 169.0 529.7 173.5 578.5 177.6 627.3 181.3 676.1 184.8 724.9 188.1 773.7 191.2 822.5 195.0 871.9 198.6 921.2 201.9 970.6 205.1 1020.0 208.0 1069.3 210.8 1118.7 213.4 1168.1 215.9 1217.4 218.3 1266.8 220.6 1316.2
Hope Creek Generating Station PTLR Revision 1-NP Page 37 of 61 Table 3: HCGS Core Critical (Curve C) P-T Curves for 32 EFPY (continued) Non-Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 1.1 96.2 45.6 109.0 90.1 119.2 134.6 127.6 179.1 134.9 223.6 141.2 268.1 146.8 312.6 179.0 312.6 179.0 692.3 181.9 740.7 184.7 789.0 187.3 837.4 189.8 885.8 192.2 934.2 194.5 982.5 196.7 1030.9 198.7 1079.3 200.7 1127.6 202.7 1176.0 204.5 1224.4 206.3 1272.8 208.0 1321.1
Hope Creek Generating Station PTLR Revision 1-NP Page 38 of 61 Table 3: HCGS Core Critical (Curve C) P-T Curves for 32 EFPY (continued) Bottom Head Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 266.4 93.7 316.3 105.0 366.2 114.2 416.0 122.0 465.9 128.8 515.8 134.7 565.6 140.0 615.5 144.8 665.4 149.2 715.2 153.2 765.1 156.9 815.0 160.4 864.8 163.7 914.7 166.7 964.6 169.6 1014.4 172.3 1064.3 174.9 1114.2 177.3 1164.1 179.6 1213.9 181.9 1263.8 184.0 1313.7
Hope Creek Generating Station PTLR Revision 1-NP Page 39 of 61 Table 4: HCGS Pressure Test (Curve A) P-T Curves for 44 EFPY Beltline Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 460.5 88.5 506.6 96.4 552.8 103.3 598.9 109.4 645.0 114.7 691.2 119.6 737.3 124.0 783.4 130.3 832.2 135.8 880.9 140.8 929.6 145.3 978.3 149.5 1027.1 153.3 1075.8 156.9 1124.5 160.2 1173.2 163.3 1221.9 166.2 1270.7 169.0 1319.4
Hope Creek Generating Station PTLR Revision 1-NP Page 40 of 61 Table 4: HCGS Pressure Test (Curve A) P-T Curves for 44 EFPY (continued) Non-Beltline Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 312.6 109.0 312.6 109.0 815.1 113.1 864.9 116.9 914.8 120.4 964.7 123.7 1014.5 126.8 1064.4 129.7 1114.2 132.4 1164.1 135.0 1214.0 137.5 1263.8 139.8 1313.7
Hope Creek Generating Station PTLR Revision 1-NP Page 41 of 61 Table 4: HCGS Pressure Test (Curve A) P-T Curves for 44 EFPY (continued) Bottom Head Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 693.7 84.3 742.0 89.1 790.3 93.4 838.6 97.4 886.9 101.1 935.2 104.6 983.5 107.8 1031.8 110.9 1080.1 113.7 1128.4 116.4 1176.6 119.0 1224.9 121.4 1273.2 123.8 1321.5
Hope Creek Generating Station PTLR Revision 1-NP Page 42 of 61 Table 5: HCGS Core Not Critical (Curve B) P-T Curves for 44 EFPY Beltline Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 169.4 91.2 215.3 101.0 261.2 109.2 307.1 116.3 352.9 122.4 398.8 127.9 444.7 132.9 490.6 137.4 536.4 141.5 582.3 145.3 628.2 150.8 677.4 155.8 726.6 160.3 775.8 164.5 825.0 168.3 874.2 171.9 923.4 175.2 972.6 178.3 1021.8 181.2 1071.0 184.0 1120.2 186.6 1169.4 189.1 1218.6 191.5 1267.8 193.7 1317.0
Hope Creek Generating Station PTLR Revision 1-NP Page 43 of 61 Table 5: HCGS Core Not Critical (Curve B) P-T Curves for 44 EFPY (continued) Non-Beltline Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 133.7 87.5 178.4 94.8 223.2 101.1 267.9 106.8 312.6 139.0 312.6 139.0 692.3 141.9 740.7 144.7 789.0 147.3 837.4 149.8 885.8 152.2 934.2 154.5 982.5 156.7 1030.9 158.7 1079.3 160.7 1127.6 162.7 1176.0 164.5 1224.4 166.3 1272.8 168.0 1321.1
Hope Creek Generating Station PTLR Revision 1-NP Page 44 of 61 Table 5: HCGS Core Not Critical (Curve B) P-T Curves for 44 EFPY (continued) Bottom Head Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 445.5 86.0 494.1 92.1 542.7 97.5 591.3 102.4 639.9 106.9 688.4 111.0 737.0 114.8 785.6 118.3 834.2 121.6 882.8 124.7 931.4 127.6 980.0 130.3 1028.6 133.0 1077.1 135.4 1125.7 137.8 1174.3 140.0 1222.9 142.2 1271.5 144.3 1320.1
Hope Creek Generating Station PTLR Revision 1-NP Page 45 of 61 Table 6: HCGS Core Critical (Curve C) P-T Curves for 44 EFPY Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 78.2 103.0 124.0 119.1 169.8 131.3 215.7 141.1 261.5 149.3 307.3 156.3 353.2 162.5 399.0 167.9 444.8 172.9 490.7 177.4 536.5 181.5 582.3 185.3 628.2 190.8 677.4 195.8 726.6 200.3 775.8 204.5 825.0 208.3 874.2 211.9 923.4 215.2 972.6 218.3 1021.8 221.2 1071.0 224.0 1120.2 226.6 1169.4 229.1 1218.6 231.5 1267.8 233.7 1317.0
Hope Creek Generating Station PTLR Revision 1-NP Page 46 of 61 Table 6: HCGS Core Critical (Curve C) P-T Curves for 44 EFPY (continued) Non-Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 1.1 96.2 45.6 109.0 90.1 119.2 134.6 127.6 179.1 134.9 223.6 141.2 268.1 146.8 312.6 179.0 312.6 179.0 692.3 181.9 740.7 184.7 789.0 187.3 837.4 189.8 885.8 192.2 934.2 194.5 982.5 196.7 1030.9 198.7 1079.3 200.7 1127.6 202.7 1176.0 204.5 1224.4 206.3 1272.8 208.0 1321.1
Hope Creek Generating Station PTLR Revision 1-NP Page 47 of 61 Table 6: HCGS Core Critical (Curve C) P-T Curves for 44 EFPY (continued) Bottom Head Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 266.4 93.7 316.3 105.0 366.2 114.2 416.0 122.0 465.9 128.8 515.8 134.7 565.6 140.0 615.5 144.8 665.4 149.2 715.2 153.2 765.1 156.9 815.0 160.4 864.8 163.7 914.7 166.7 964.6 169.6 1014.4 172.3 1064.3 174.9 1114.2 177.3 1164.1 179.6 1213.9 181.9 1263.8 184.0 1313.7
Hope Creek Generating Station PTLR Revision 1-NP Page 48 of 61 Table 7: HCGS Pressure Test (Curve A) P-T Curves for 56 EFPY Beltline Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 432.8 89.7 478.7 98.4 524.7 105.9 570.6 112.4 616.5 118.2 662.5 123.3 708.4 130.8 755.9 137.4 803.4 143.2 850.8 148.3 898.3 153.0 945.8 157.3 993.3 161.3 1040.8 164.9 1088.2 168.4 1135.7 171.5 1183.2 174.5 1230.7 177.4 1278.1 180.1 1325.6
Hope Creek Generating Station PTLR Revision 1-NP Page 49 of 61 Table 7: HCGS Pressure Test (Curve A) P-T Curves for 56 EFPY (continued) Non-Beltline Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 312.6 109.0 312.6 109.0 815.1 113.1 864.9 116.9 914.8 120.4 964.7 123.7 1014.5 126.8 1064.4 129.7 1114.2 132.4 1164.1 135.0 1214.0 137.5 1263.8 139.8 1313.7
Hope Creek Generating Station PTLR Revision 1-NP Page 50 of 61 Table 7: HCGS Pressure Test (Curve A) P-T Curves for 56 EFPY (continued) Bottom Head Region Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 693.7 84.3 742.0 89.1 790.3 93.4 838.6 97.4 886.9 101.1 935.2 104.6 983.5 107.8 1031.8 110.9 1080.1 113.7 1128.4 116.4 1176.6 119.0 1224.9 121.4 1273.2 123.8 1321.5
Hope Creek Generating Station PTLR Revision 1-NP Page 51 of 61 Table 8: HCGS Core Not Critical (Curve B) P-T Curves for 56 EFPY Beltline Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 148.6 93.6 197.8 104.9 247.0 114.1 296.2 121.9 345.3 128.6 394.5 134.5 443.7 139.8 492.9 144.6 542.0 151.4 590.7 157.3 639.3 162.6 687.9 167.5 736.5 171.8 785.1 175.9 833.7 179.6 882.4 183.1 931.0 186.3 979.6 189.4 1028.2 192.2 1076.8 195.0 1125.4 197.5 1174.1 200.0 1222.7 202.3 1271.3 204.6 1319.9
Hope Creek Generating Station PTLR Revision 1-NP Page 52 of 61 Table 8: HCGS Core Not Critical (Curve B) P-T Curves for 56 EFPY (continued) Non-Beltline Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 133.7 87.5 178.4 94.8 223.2 101.1 267.9 106.8 312.6 139.0 312.6 139.0 692.3 141.9 740.7 144.7 789.0 147.3 837.4 149.8 885.8 152.2 934.2 154.5 982.5 156.7 1030.9 158.7 1079.3 160.7 1127.6 162.7 1176.0 164.5 1224.4 166.3 1272.8 168.0 1321.1
Hope Creek Generating Station PTLR Revision 1-NP Page 53 of 61 Table 8: HCGS Core Not Critical (Curve B) P-T Curves for 56 EFPY (continued) Bottom Head Region Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 445.5 86.0 494.1 92.1 542.7 97.5 591.3 102.4 639.9 106.9 688.4 111.0 737.0 114.8 785.6 118.3 834.2 121.6 882.8 124.7 931.4 127.6 980.0 130.3 1028.6 133.0 1077.1 135.4 1125.7 137.8 1174.3 140.0 1222.9 142.2 1271.5 144.3 1320.1
Hope Creek Generating Station PTLR Revision 1-NP Page 54 of 61 Table 9: HCGS Core Critical (Curve C) P-T Curves for 56 EFPY Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 68.8 106.3 116.1 123.9 163.5 136.8 210.8 147.1 258.1 155.7 305.4 162.9 352.8 169.3 400.1 174.9 447.4 180.0 494.7 184.6 542.0 191.4 590.7 197.3 639.3 202.6 687.9 207.5 736.5 211.8 785.1 215.9 833.7 219.6 882.4 223.1 931.0 226.3 979.6 229.4 1028.2 232.2 1076.8 235.0 1125.4 237.5 1174.1 240.0 1222.7 242.3 1271.3 244.6 1319.9
Hope Creek Generating Station PTLR Revision 1-NP Page 55 of 61 Table 9: HCGS Core Critical (Curve C) P-T Curves for 56 EFPY (continued) Non-Beltline Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 1.1 96.2 45.6 109.0 90.1 119.2 134.6 127.6 179.1 134.9 223.6 141.2 268.1 146.8 312.6 179.0 312.6 179.0 692.3 181.9 740.7 184.7 789.0 187.3 837.4 189.8 885.8 192.2 934.2 194.5 982.5 196.7 1030.9 198.7 1079.3 200.7 1127.6 202.7 1176.0 204.5 1224.4 206.3 1272.8 208.0 1321.1
Hope Creek Generating Station PTLR Revision 1-NP Page 56 of 61 Table 9: HCGS Core Critical (Curve C) P-T Curves for 56 EFPY (continued) Bottom Head Region Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure
°F psi 79.0 0.0 79.0 266.4 93.7 316.3 105.0 366.2 114.2 416.0 122.0 465.9 128.8 515.8 134.7 565.6 140.0 615.5 144.8 665.4 149.2 715.2 153.2 765.1 156.9 815.0 160.4 864.8 163.7 914.7 166.7 964.6 169.6 1014.4 172.3 1064.3 174.9 1114.2 177.3 1164.1 179.6 1213.9 181.9 1263.8 184.0 1313.7
Hope Creek Generating Station PTLR Revision 1-NP Page 57 of 61 Table 10: HCGS ART Calculations for 32 EFPY Chemistry Adjustments For 1/4T Initial Chemistry Fluence Fluence Fluence Flux (wt%) Description Heat/Lot No. RTNDT Factor, at ID at 1/4T Factor, RTNDT Margin Terms ART Type (°F) Cu Ni CF (°F) (n/cm2) (n/cm2) FF (°F) (°F) (°F) i (°F) Intermediate Shell (3) 5K3025/1 - 19 0.15 0.71 112.8 3.15E+17 2.23E+17 0.184 20.8 10.4 0.0 60.5 Intermediate Shell (3) 5K2608/1 - 19 0.09 0.58 58.0 3.15E+17 2.23E+17 0.184 10.7 5.3 0.0 40.4 Intermediate Shell (3) 5K2698/1 - 19 0.10 0.58 65.0 3.15E+17 2.23E+17 0.184 12.0 6.0 0.0 42.9 Lower Intermediate Shell (4) 5K2963/1 - -10 0.07 0.58 44.0 8.86E+17 6.15E+17 0.327 14.4 7.2 0.0 18.8 Plates Lower Intermediate Shell (4) 5K2530/1 - 19 0.08 0.56 51.0 8.86E+17 6.15E+17 0.327 16.7 8.3 0.0 52.3 Lower Intermediate Shell (4) 5K3238/1 - 7 0.09 0.64 58.0 8.86E+17 6.15E+17 0.327 19.0 9.5 0.0 44.9 Lower Shell (5) 5K3230/1 - -10 0.07 0.56 44.0 6.08E+17 4.24E+17 0.267 11.8 5.9 0.0 13.5 Lower Shell (5) 6C35/1 - -11 0.09 0.54 58.0 6.08E+17 4.24E+17 0.267 15.5 7.8 0.0 20.0 Lower Shell (5) 6C45/1 - 1 0.08 0.57 51.0 6.08E+17 4.24E+17 0.267 13.6 6.8 0.0 28.3 Vertical W13 510-01205 SMAW -40 0.09 0.54 108.7 3.11E+17 2.20E+17 0.182 19.8 9.9 0.0 -0.4 Vertical W13 D53040/1125-02205 SAW -30 0.08 0.63 110.1 3.11E+17 2.20E+17 0.182 20.1 10.0 0.0 10.1 Vertical W14 510-01205 SMAW -40 0.09 0.54 108.7 7.75E+17 5.43E+17 0.306 33.3 16.6 0.0 26.5 Vertical W14 D53040/1125-02205 SAW -30 0.08 0.63 110.1 7.75E+17 5.43E+17 0.306 33.7 16.8 0.0 37.4 Vertical W15 510-01205 SMAW -40 0.09 0.54 108.7 5.29E+17 3.69E+17 0.247 26.9 13.5 0.0 13.8 Vertical W15 D53040/1125-02205 SAW -30 0.08 0.63 110.1 5.29E+17 3.69E+17 0.247 27.3 13.6 0.0 24.5 Welds Girth W6 (Shell 3-4) 519-01205 SMAW -49 0.01 0.53 20.0 3.15E+17 2.23E+17 0.184 3.7 1.8 0.0 -41.6 Girth W6 (Shell 3-4) 504-01205 SMAW -31 0.01 0.51 20.0 3.15E+17 2.23E+17 0.184 3.7 1.8 0.0 -23.6 Girth W6 (Shell 3-4) 510-01205 SMAW -40 0.09 0.54 108.7 3.15E+17 2.23E+17 0.184 20.0 10.0 0.0 0.0 Girth W6 (Shell 3-4) D53040/1810-02205 SAW -49 0.08 0.63 110.1 3.15E+17 2.23E+17 0.184 20.3 10.1 0.0 -8.5 Girth W6 (Shell 3-4) D55733/1810-02205 SAW -40 0.10 0.68 126.4 3.15E+17 2.23E+17 0.184 23.3 11.6 0.0 6.5 Girth W7 (Shell 4-5) 510-01205 SMAW -40 0.09 0.54 108.7 6.08E+17 4.24E+17 0.267 29.1 14.5 0.0 18.1 Girth W7 (Shell 4-5) D53040/1125-02205 SAW -30 0.08 0.63 110.1 6.08E+17 4.24E+17 0.267 29.5 14.7 0.0 28.9 LPCI (N17; A-D) 19468/1 - -20 0.12 0.80 86.0 9.80E+16 8.04E+16 0.094 8.1 4.1 0.0 -3.8 Nozzles LPCI (N17; A-D) 10024/1 - -20 0.14 0.82 105.1 9.80E+16 8.04E+16 0.094 9.9 5.0 0.0 -0.2 Instrument (N16; A, D) 5K3025/1 (adj. plate) - 19 0.15 0.71 112.8 1.90E+17 1.59E+17 0.149 16.8 8.4 0.0 52.6 Instrument (N16; B, C) 5K2698/1 (adj. plate) - 19 0.10 0.58 65.0 1.90E+17 1.59E+17 0.149 9.7 4.8 0.0 38.4 LPCI Nozzle W179 001-01205 SMAW -40 0.02 0.51 27.0 2.77E+17 2.09E+17 0.177 4.8 2.4 0.0 -30.5 Nozzle LPCI Nozzle W179 519-01205 SMAW -49 0.01 0.53 20.0 2.77E+17 2.09E+17 0.177 3.5 1.8 0.0 -41.9 Welds LPCI Nozzle W179 504-01205 SMAW -31 0.01 0.51 20.0 2.77E+17 2.09E+17 0.177 3.5 1.8 0.0 -23.9 Surveillance Plate 5K3238/1 - 7 0.09 0.64 (( }} 8.86E+17 6.15E+17 0.327 16.1 8.0 0.0 39.1 ISP Surveillance Weld D53040 SAW -30 0.07 0.57 (( }} 7.75E+17 5.43E+17 0.306 64.5 28.0 0.0 90.5 REDACTED EPRI PROPRIETARY INFORMATION [16] (such information is marked with double braces (( }} and a bar in the right-hand margin)
Hope Creek Generating Station PTLR Revision 1-NP Page 58 of 61 Table 11: HCGS ART Calculations for 44 EFPY Chemistry Adjustments For 1/4T Initial Chemistry Fluence Fluence Fluence Flux (wt%) Description Heat/Lot No. RTNDT Factor, at ID at 1/4T Factor, RTNDT Margin Terms ART Type (°F) Cu Ni CF (°F) (n/cm2) (n/cm2) FF (°F) (°F) (°F) i (°F) Intermediate Shell (3) 5K3025/1 - 19 0.15 0.71 112.8 4.38E+17 3.10E+17 0.224 25.2 12.6 0.0 69.5 Intermediate Shell (3) 5K2608/1 - 19 0.09 0.58 58.0 4.38E+17 3.10E+17 0.224 13.0 6.5 0.0 45.0 Intermediate Shell (3) 5K2698/1 - 19 0.10 0.58 65.0 4.38E+17 3.10E+17 0.224 14.6 7.3 0.0 48.1 Lower Intermediate Shell (4) 5K2963/1 - -10 0.07 0.58 44.0 1.27E+18 8.83E+17 0.392 17.3 8.6 0.0 24.5 Plates Lower Intermediate Shell (4) 5K2530/1 - 19 0.08 0.56 51.0 1.27E+18 8.83E+17 0.392 20.0 10.0 0.0 59.0 Lower Intermediate Shell (4) 5K3238/1 - 7 0.09 0.64 58.0 1.27E+18 8.83E+17 0.392 22.8 11.4 0.0 52.5 Lower Shell (5) 5K3230/1 - -10 0.07 0.56 44.0 8.84E+17 6.17E+17 0.327 14.4 7.2 0.0 18.8 Lower Shell (5) 6C35/1 - -11 0.09 0.54 58.0 8.84E+17 6.17E+17 0.327 19.0 9.5 0.0 27.0 Lower Shell (5) 6C45/1 - 1 0.08 0.57 51.0 8.84E+17 6.17E+17 0.327 16.7 8.3 0.0 34.4 Vertical W13 510-01205 SMAW -40 0.09 0.54 108.7 4.33E+17 3.06E+17 0.222 24.1 12.1 0.0 8.3 Vertical W13 D53040/1125-02205 SAW -30 0.08 0.63 110.1 4.33E+17 3.06E+17 0.222 24.5 12.2 0.0 18.9 Vertical W14 510-01205 SMAW -40 0.09 0.54 108.7 1.11E+18 7.76E+17 0.368 40.0 20.0 0.0 40.0 Vertical W14 D53040/1125-02205 SAW -30 0.08 0.63 110.1 1.11E+18 7.76E+17 0.368 40.5 20.3 0.0 51.1 Vertical W15 510-01205 SMAW -40 0.09 0.54 108.7 7.70E+17 5.37E+17 0.304 33.0 16.5 0.0 26.1 Vertical W15 D53040/1125-02205 SAW -30 0.08 0.63 110.1 7.70E+17 5.37E+17 0.304 33.5 16.7 0.0 37.0 Welds Girth W6 (Shell 3-4) 519-01205 SMAW -49 0.01 0.53 20.0 4.38E+17 3.10E+17 0.224 4.5 2.2 0.0 -40.0 Girth W6 (Shell 3-4) 504-01205 SMAW -31 0.01 0.51 20.0 4.38E+17 3.10E+17 0.224 4.5 2.2 0.0 -22.0 Girth W6 (Shell 3-4) 510-01205 SMAW -40 0.09 0.54 108.7 4.38E+17 3.10E+17 0.224 24.3 12.2 0.0 8.7 Girth W6 (Shell 3-4) D53040/1810-02205 SAW -49 0.08 0.63 110.1 4.38E+17 3.10E+17 0.224 24.7 12.3 0.0 0.3 Girth W6 (Shell 3-4) D55733/1810-02205 SAW -40 0.10 0.68 126.4 4.38E+17 3.10E+17 0.224 28.3 14.2 0.0 16.6 Girth W7 (Shell 4-5) 510-01205 SMAW -40 0.09 0.54 108.7 8.84E+17 6.17E+17 0.327 35.6 17.8 0.0 31.2 Girth W7 (Shell 4-5) D53040/1125-02205 SAW -30 0.08 0.63 110.1 8.84E+17 6.17E+17 0.327 36.0 18.0 0.0 42.1 LPCI (N17; A-D) 19468/1 - -20 0.12 0.80 86.0 1.35E+17 1.10E+17 0.117 10.1 5.0 0.0 0.1 Nozzles LPCI (N17; A-D) 10024/1 - -20 0.14 0.82 105.1 1.35E+17 1.10E+17 0.117 12.3 6.2 0.0 4.6 Instrument (N16; A, D) 5K3025/1 (adj. plate) - 19 0.15 0.71 112.8 2.63E+17 2.22E+17 0.183 20.7 10.3 0.0 60.3 Instrument (N16; B, C) 5K2698/1 (adj. plate) - 19 0.10 0.58 65.0 2.63E+17 2.22E+17 0.183 11.9 6.0 0.0 42.8 LPCI Nozzle W179 001-01205 SMAW -40 0.02 0.51 27.0 3.81E+17 2.87E+17 0.214 5.8 2.9 0.0 -28.5 Nozzle LPCI Nozzle W179 519-01205 SMAW -49 0.01 0.53 20.0 3.81E+17 2.87E+17 0.214 4.3 2.1 0.0 -40.4 Welds LPCI Nozzle W179 504-01205 SMAW -31 0.01 0.51 20.0 3.81E+17 2.87E+17 0.214 4.3 2.1 0.0 -22.4 Surveillance Plate 5K3238/1 - 7 0.09 0.64 (( }} 1.27E+18 8.83E+17 0.392 19.3 8.5 0.0 43.3 ISP Surveillance Weld D53040 SAW -30 0.07 0.57 (( }} 1.11E+18 7.76E+17 0.368 77.6 28.0 0.0 103.6 REDACTED EPRI PROPRIETARY INFORMATION [16] (such information is marked with double braces (( }} and a bar in the right-hand margin)
Hope Creek Generating Station PTLR Revision 1-NP Page 59 of 61 Table 12: HCGS ART Calculations for 56 EFPY Chemistry Adjustments For 1/4T Initial Chemistry Fluence Fluence Fluence Flux (wt%) Description Heat/Lot No. RTNDT Factor, at ID at 1/4T Factor, RTNDT Margin Terms ART Type (°F) Cu Ni CF (°F) (n/cm2) (n/cm2) FF (°F) (°F) (°F) i (°F) Intermediate Shell (3) 5K3025/1 - 19 0.15 0.71 112.8 5.60E+17 3.97E+17 0.258 29.1 14.5 0.0 77.1 Intermediate Shell (3) 5K2608/1 - 19 0.09 0.58 58.0 5.60E+17 3.97E+17 0.258 15.0 7.5 0.0 48.9 Intermediate Shell (3) 5K2698/1 - 19 0.10 0.58 65.0 5.60E+17 3.97E+17 0.258 16.8 8.4 0.0 52.5 Lower Intermediate Shell (4) 5K2963/1 - -10 0.07 0.58 44.0 1.65E+18 1.15E+18 0.445 19.6 9.8 0.0 29.2 Plates Lower Intermediate Shell (4) 5K2530/1 - 19 0.08 0.56 51.0 1.65E+18 1.15E+18 0.445 22.7 11.4 0.0 64.4 Lower Intermediate Shell (4) 5K3238/1 - 7 0.09 0.64 58.0 1.65E+18 1.15E+18 0.445 25.8 12.9 0.0 58.7 Lower Shell (5) 5K3230/1 - -10 0.07 0.56 44.0 1.16E+18 8.10E+17 0.376 16.5 8.3 0.0 23.1 Lower Shell (5) 6C35/1 - -11 0.09 0.54 58.0 1.16E+18 8.10E+17 0.376 21.8 10.9 0.0 32.6 Lower Shell (5) 6C45/1 - 1 0.08 0.57 51.0 1.16E+18 8.10E+17 0.376 19.2 9.6 0.0 39.4 Vertical W13 510-01205 SMAW -40 0.09 0.54 108.7 5.55E+17 3.92E+17 0.256 27.8 13.9 0.0 15.7 Vertical W13 D53040/1125-02205 SAW -30 0.08 0.63 110.1 5.55E+17 3.92E+17 0.256 28.2 14.1 0.0 26.4 Vertical W14 510-01205 SMAW -40 0.09 0.54 108.7 1.44E+18 1.01E+18 0.419 45.5 22.8 0.0 51.1 Vertical W14 D53040/1125-02205 SAW -30 0.08 0.63 110.1 1.44E+18 1.01E+18 0.419 46.1 23.1 0.0 62.3 Vertical W15 510-01205 SMAW -40 0.09 0.54 108.7 1.01E+18 7.04E+17 0.350 38.1 19.0 0.0 36.2 Vertical W15 D53040/1125-02205 SAW -30 0.08 0.63 110.1 1.01E+18 7.04E+17 0.350 38.6 19.3 0.0 47.2 Welds Girth W6 (Shell 3-4) 519-01205 SMAW -49 0.01 0.53 20.0 5.60E+17 3.97E+17 0.258 5.2 2.6 0.0 -38.7 Girth W6 (Shell 3-4) 504-01205 SMAW -31 0.01 0.51 20.0 5.60E+17 3.97E+17 0.258 5.2 2.6 0.0 -20.7 Girth W6 (Shell 3-4) 510-01205 SMAW -40 0.09 0.54 108.7 5.60E+17 3.97E+17 0.258 28.0 14.0 0.0 16.1 Girth W6 (Shell 3-4) D53040/1810-02205 SAW -49 0.08 0.63 110.1 5.60E+17 3.97E+17 0.258 28.4 14.2 0.0 7.8 Girth W6 (Shell 3-4) D55733/1810-02205 SAW -40 0.10 0.68 126.4 5.60E+17 3.97E+17 0.258 32.6 16.3 0.0 25.2 Girth W7 (Shell 4-5) 510-01205 SMAW -40 0.09 0.54 108.7 1.16E+18 8.10E+17 0.376 40.9 20.4 0.0 41.8 Girth W7 (Shell 4-5) D53040/1125-02205 SAW -30 0.08 0.63 110.1 1.16E+18 8.10E+17 0.376 41.4 20.7 0.0 52.8 LPCI (N17; A-D) 19468/1 - -20 0.12 0.80 86.0 1.71E+17 1.40E+17 0.137 11.8 5.9 0.0 3.6 Nozzles LPCI (N17; A-D) 10024/1 - -20 0.14 0.82 105.1 1.71E+17 1.40E+17 0.137 14.4 7.2 0.0 8.8 Instrument (N16; A, D) 5K3025/1 (adj. plate) - 19 0.15 0.71 112.8 3.37E+17 2.84E+17 0.213 24.0 12.0 0.0 67.0 Instrument (N16; B, C) 5K2698/1 (adj. plate) - 19 0.10 0.58 65.0 3.37E+17 2.84E+17 0.213 13.8 6.9 0.0 46.6 LPCI Nozzle W179 001-01205 SMAW -40 0.02 0.51 27.0 4.85E+17 3.65E+17 0.246 6.6 3.3 0.0 -26.7 Nozzle LPCI Nozzle W179 519-01205 SMAW -49 0.01 0.53 20.0 4.85E+17 3.65E+17 0.246 4.9 2.5 0.0 -39.2 Welds LPCI Nozzle W179 504-01205 SMAW -31 0.01 0.51 20.0 4.85E+17 3.65E+17 0.246 4.9 2.5 0.0 -21.2 Surveillance Plate 5K3238/1 - 7 0.09 0.64 (( }} 1.65E+18 1.15E+18 0.445 21.9 8.5 0.0 45.9 ISP Surveillance Weld D53040 SAW -30 0.07 0.57 (( }} 1.44E+18 1.01E+18 0.419 88.3 28.0 0.0 114.3 REDACTED EPRI PROPRIETARY INFORMATION [16] (such information is marked with double braces (( }} and a bar in the right-hand margin)
Hope Creek Generating Station PTLR Revision 1-NP Page 60 of 61 Table 13: Nozzle Stress Intensity Factors Nozzle Applied Pressure, KIp-app Thermal, KIt Feedwater 78.46 41.85 Instrument (N16) 75.94 24.75 0.5 KI in units of ksi-in
Hope Creek Generating Station PTLR Revision 1-NP Page 61 of 61 Appendix A HOPE CREEK REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM In accordance with 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements [28], two surveillance capsules have been removed from the HCGS reactor vessel in 1994 after 6.01 EFPY [29] and in 2015 after 24.1 EFPY [30]. The 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 materials within the core beltline region. HCGS is currently committed to use the BWRVIP ISP, and has made a licensing commitment to use the ISP for HCGS 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 NRC. HCGS committed to use the ISP in place of its existing surveillance programs in the license amendment issued by the NRC regarding the implementation of the BWRVIP ISP, dated July 23, 2004 [12]. Under the ISP, a capsule was removed in 2015 after 24.1 EFPY [30]. HCGS continues to be a host plant under the ISP. One additional standby HCGS capsule is currently scheduled to be removed and tested under the ISP during the license renewal period in approximately 2036 at 40 EFPY [31]. LR-N18-0057 EPRI Affidavit supporting the withholding of information in Enclosure 3 from public disclosure
II -=* -
- ELECTRIC POWER RESEARCH INSTITUTE NEIL WILMSHURST Vice President and Chief Nuclear Officer Ref. EPRI Docket No. 99902016 May 15, 2018 Document Control Desk Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Request for Withholding of the following Proprietary Information Included in: PSEG Nuclear LLC, Hope Creek Generating Station, titled:
* "Pressure* and Temperature Limits Report {PTLR) for 32, 44, and 56 Effective Fuii.Power Years (EFPY)",
. Revision 1-P, dated September 2017 To Whom It May Concern:
This is a request under 10 C.F.R. §2.390(a)(4) that the U.S. Nuclear Regulatory Commission ("NRC") withhold from public disclosure the report identified in the enclosed Affidavit consisting of the proprietary information owned by Electric Power Research Institute, Inc. ("EPRI") identified above in the attached report. Proprietary and non-proprietary versions of the Report and the Affidavit in support of this request are enclosed. EPRI desires to disclose the Proprietary Information in confidence to assist the NRC review of the enclosed submittal to the NRC by PSEG. The Proprietary Information is not to be divulged to anyone outside of the NRC or to any of its contractors, nor shall any copies be made of the Proprietary Information provided herein. EPRI welcomes any discussions and/or questions relating to the information enclosed. If you have any questions about the legal aspects of this request for withholding, please do not hesitate to contact me at (704) 595-2732. Questions on the content of the Report should be directed to Andy McGehee of EPRI at (704) 502-6440. Sincerely,
\W l)P/
Attachment(s) Together ... Shaping the Future of Electricity 1300 West W.T. Harris Boulevard, CharloHe, NC 28262-8550 USA
- 704.595.2732
- Mobile 704.490.2653
- nwilmshurst@epri.com
II ELECTRIC POWER RESEARCH INSTITUTE AFFIDAVIT RE: Request for Withholding of the Following ProprietaryInformation Included In: PSEG Nuclear LLC, Hope Creek Generating Station, titled:
"Pressure and Temperature Limits Report (PTLR) for 32, 44, and 56 Effective Full Power Years (EFPY)",
Revision 1-P, dated September 2017 I, Neil Wilmshurst, being duly sworn, depose and state as follows: I am the Vice President and Chief Nuclear Officer at Electric Power Research Institute, Inc. whose principal office is located at 3420 Hillview Avenue, Palo Alto, California ("EPRI") and I have been specifically delegated responsibility for the above-listed Report contains EPRI Proprietary Information that is sought under this Affidavit to be withheld "Proprietary Information". I am authorized to apply to the U.S. Nuclear Regulatory Commission ("NRC") for the withholding of the Proprietary Information on behalf of EPRI. EPRI Proprietary Information is identified in the above referenced report with underlined text inside double brackets. Examples of such identification is as follows: ((This sentence is an example{E})) Tables containing EPRI Proprietary Information are identified with double brackets before and after the object. In each case the superscript notation {E} refers to this affidavit and all the bases included below, which provide the reasons for the proprietary determination. EPRI requests that the Proprietary Information be withheld from the public on the following bases: Withholding Based Upon Privileged And Confidential Trade Secrets Or Commercial Or Financial Information (see e.g. 10 C.F.R. §2.390(a)(4))::
- a. The Proprietary Information is owned by EPRI and has been held in confidence by EPRI. All entities accepting copies of the Proprietary Information do so subject to written agreements imposing an obligation upon the recipient to maintain the confidentiality of the Proprietary Information. The Proprietary Information is disclosed only to parties who agree, in writing, to preserve the confidentiality thereof.
- b. EPRI considers the Proprietary Information contained therein to constitute trade secrets of EPRI. As such, EPRI holds the information in confidence and disclosure thereof is strictly limited to individuals and entities who have agreed, in writing, to maintain the confidentiality of the Information.
- c. The information sought to be withheld is considered to be proprietary for the following reasons. EPRI made a substantial economic investment to develop the Proprietary Information and, by prohibiting public disclosure, EPRI derives an economic benefit in the form of licensing royalties and other additional fees from the confidential nature of the Proprietary Information. If the Proprietary Information were publicly available to consultants and/or other businesses providing services in the electric and/or nuclear power industry, they would be able to use the Proprietary Information for their own commercial benefit and profit and without expending the substantial economic resources required of EPRI to develop the Proprietary Information.
- d. EPRI's classification of the Proprietary Information as trade secrets is justified by the Uniform Trade Secrets Act which California adopted in 1984 and a version of which has been adopted by over forty states. The California Uniform Trade Secrets Act, California Civil Code §§3426 - 3426.11, defines a "trade secret" as follows:
"'Trade secret' means information, including a formula, pattern, compilation, program device, method, technique, or process, that:
(1) Derives independent economic value, actual or potential, from not being generally known to the public or to other persons who can obtain economic value from its disclosure or use; and (2) Is the subject of efforts that are reasonable under the circumstances to maintain its secrecy."
- e. The Proprietary Information contained therein are not generally known or available to the public. EPRI developed the Information only after making a determination that the Proprietary Information was not available from public sources. EPRI made a substantial investment of both money and employee hours in the development of the Propretary Information. EPRI was required to devote these resources and effort to derive the Proprietary Information. As a result of such effort and cost, both in terms of dollars spent and dedicated employee time, the Proprietary Information is highly valuable to EPRI.
- f. A public disclosure of the Proprietary Information would be highly likely to cause substantial harm to EPRI's competitive position and the ability of EPRI to license the Proprietary Information both domestically and internationally. The Proprietary Information and Report can only be acquired and/or duplicated by others using an equivalent investment of time and effort.
I have read the foregoing and the matters stated herein are true and correct to the best of my knowledge, information and belief. I make this affidavit under penalty of perjury under the laws of the United States of America and under the laws of the State of California. Executed at 1300 W WT Harris Blvd, Charlotte, NC being the premises and place of business of Electric Power Research Institute, Inc. Date: (\J\ I lot'K. [ lJ Neil Wilmshurst
(State of North Carolina) (County of Mecklenburg) Subscribed an wp to (or affirmed} before me on this /S y of -----'-'-- 20J1 by mi;_ , proved to me on the basis of satisfac evidence to be the person(s) who appeared before me. Signature {2.rlm(aJ J/. Ct(/Jf (Seal) Ad My Commission Expires _g_day of JUL , 2o:tt}}