Text

Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
	ML18270A390
Person / Time
Site:	Brunswick
Issue date:	09/27/2018
From:	William Gideon; Duke Energy Progress
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML18270A389	List: RA-18-0163, Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report;
References
	2018-118, EPID L-2018-LLA-0094, RA-18-0163
	Download: ML18270A390 (143)
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William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 o: 910.832.3698 September 27, 2018 Serial: RA-18-0163 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report

References:

1. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report, dated April 4, 2018, ADAMS Accession Number ML18094B058

2. Letter from William R. Gideon (Duke Energy) to the U.S. Nuclear Regulatory Commission Document Control Desk, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report, dated May 29, 2018, ADAMS Accession Number ML18149A487

3. E-Mail Capture from Dennis Galvin (NRC) to Lee Grzeck (Duke Energy), Brunswick RAIs - LAR to Revise TS to Relocate the Pressure-Temperature Limits to the Pressure and Temperature Limits Report (EPID L 2018-LLA-0094), dated August 31, 2018 Ladies and Gentlemen:

By letter dated April 4, 2018, as supplemented on May 29, 2018 (i.e., References 1 and 2),

Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment requested relocation of the Technical Specifications pressure-temperature (P-T) limits to a licensee-controlled Pressure and Temperature Limits Report (PTLR). Additionally, the current 32-effective full power year (EFPY) P-T limits are being updated to 54-EFPY P-T limits.

On August 31, 2018 (i.e., Reference 3), the NRC provided a request for additional information (RAI) regarding the LAR. Duke Energy's response to the RAI is included as Enclosure 1. contains proprietary information, as defined by 10 CFR 2.390. The Electric Power Research Institute (EPRI), as owner of the proprietary information, has executed the affidavit

U.S. Nuclear Regulatory Commission Page 2 of 3 provided in Enclosure 3, which identifies the proprietary information that has been handled and is classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure.

This document contains no new regulatory commitments.

I declare, under penalty of perjury, that the foregoing is true and correct. Executed on September 27, 2018.

~

William R. Gideon MAT/mat

Enclosures:

1. Response to Request for Additional Information

2. Excerpts from BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (SP) Data Source Book and Plant Evaluations (Proprietary Information - Withhold from Public Disclosure in Accordance With 10 CFR 2.390)

3. EPRI Affidavit Regarding Withholding

4. Excerpts from BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (SP) Data Source Book and Plant Evaluations (Non-proprietary)

5. Structural Integrity Calculation No. 1700147.302, Revision 0, Brunswick Nuclear Plant Unit 1 and 2 Updated P-T Curve Calculation for 54 EFPY

U.S. Nuclear Regulatory Commission Page 3 of 3 cc (with all Enclosures):

U.S. Nuclear Regulatory Commission, Region II ATTN: Ms. Catherine Haney, Regional Administrator 245 Peachtree Center Ave, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Dennis J. Galvin 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Gale Smith, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 cc (with Enclosures 1, 3, 4, and 5):

Chair - North Carolina Utilities Commission (Electronic Copy Only) 4325 Mail Service Center Raleigh, NC 27699-4300 swatson@ncuc.net Mr. W. Lee Cox, III, Section Chief (Electronic Copy Only)

Radiation Protection Section North Carolina Department of Health and Human Services 1645 Mail Service Center Raleigh, NC 27699-1645 lee.cox@dhhs.nc.gov

RA-18-0163 Enclosure 1 Page 1 of 9 Response to Request for Additional Information By letter dated April 4, 2018, as supplemented on May 29, 2018, Duke Energy Progress, LLC (Duke Energy), submitted a license amendment request (LAR) for the Brunswick Steam Electric Plant (BSEP), Unit Nos. 1 and 2. The proposed amendment requested relocation of the Technical Specifications pressure-temperature (P-T) limits to a licensee-controlled Pressure and Temperature Limits Report (PTLR). Additionally, the current 32-effective full power year (EFPY)

P-T limits are being updated to 54-EFPY P-T limits.

On August 31, 2018, the NRC provided a request for additional information (RAI) regarding the LAR. Duke Energy's responses are provided below.

MVIB RAI-1 Appendix A to Attachment 1 to the proposed PTLR states:

"Representative surveillance capsule materials for the BSEP Unit 1 and 2 limiting beltline plate are contained in the River Bend and Supplemental Surveillance Program (SSP)

Capsules C, F, and H. Representative materials for the BSEP Unit 1 and 2 limiting beltline weld are in the Duane Arnold and SSP-F surveillance capsules."

The NRC staff notes that the information quoted above is inconsistent with that contained in Table 4-4 of BWRVIP-86, Revision 1-A (ADAMS Accession No. ML131760082). Please explain this apparent discrepancy and correct the PTLR if warranted.

Response to MVIB RAI-1 Table 4-4 in BWRVIP-86, Revision 1-A shows the following information for the BSEP Units 1 and 2 Integrated Surveillance Program (ISP) surveillance material assignments:

Representative Target Surveillance Representative Surveillance Plant Vessel Material Heat Material Source Capsules Material Number Weld 5P6756 SSP-C, -F, -H, and River Bend BSEP Unit 1 Plate B0673-1 Duane Arnold and SSP-F Weld 5P6756 SSP-C, -F, -H, and River Bend BSEP Unit 2 Plate B0673-1 Duane Arnold and SSP-F In the statement in Appendix A to Attachment 1 of the proposed Pressure Temperature Limits Report (PTLR), the words "plate" and "weld" were incorrectly transposed in identifying the source capsule locations for the representative materials. The statement in the PTLR will be corrected as follows: "

Representative surveillance capsule materials for the BSEP Unit 1 and 2 limiting beltline weld are contained in the River Bend and Supplemental Surveillance Program (SSP)

Capsules C, F, and H. Representative materials for the BSEP Unit 1 and 2 limiting beltline plate are in the Duane Arnold and SSP-F surveillance capsules.

RA-18-0163 Enclosure 1 Page 2 of 9 This change will bring the information in the PTLR into agreement with Table 4-4 of BWRVIP-86, Revision 1-A MVIB RAI-2 Page 9 of Attachment 1 to the proposed PTLR (in Section 5.0) states:

"The representative heat of the plate material for both BSEP Unit 1 and Unit 2 (B0673-1) in the ISP is not the same as the target plate material in BSEP Unit 1 (B8496-1) or BSEP Unit 2 (C4500-2). The representative heat of the weld material for both BSEP Unit 1 and Unit 2 (5P6756) is not the same heat number as the target weld material in BSEP Unit 1 (1P4218) or BSEP Unit 2 (S3986). Therefore, for all BSEP Unit 1 and Unit 2 beltline materials, the CF values are calculated using table values from R.G. 1.99, Revision 2, Position 1.1."

Notwithstanding the licensees statement above the staff notes:

1) BSEP is a member of the BWRVIP-ISP;

2) BWRVIP-ISPs selection of the representative surveillance plate and weld for BSEP units based on material characteristics instead of heat number was accepted by the NRC.

3) Regulatory Guide (RG) 1.99, "Radiation Embrittlement of Reactor Vessel Materials," Revision 2, Position 2.1 provides guidance for evaluating the adjusted reference temperature used in establishing the plants P-T limits when two or more credible surveillance data sets becomes available;

4) Table 4-8 of BWRVIP-86, Revision 1-A indicated that two or more surveillance data (i.e., sufficient data) exist for the target reactor pressure vessel limiting plate and weld.

Therefore, please revise the submittal to utilize the BWRVIP-ISP data in accordance with RG 1.99, Revision 2, provide a basis using BWR fleet surveillance data to demonstrate that the BWRVIP-ISPs selection of the representative surveillance plate and weld for BSEP units is inadequate, or provide a justified alternate approach to support failure to use available surveillance data.

Response to MVIB RAI-2 The requirements in BWRVIP-86, Revision 1-A are clear that representative surveillance data from the ISP should not be utilized in accordance with Position 2.1 of Regulatory Guide 1.99, Revision 2 (i.e., Reference 1), unless the heat number of the surveillance material matches the heat number of the target vessel material. The Safety Evaluation (SE) for Revision 0 of BWRVIP-86 not only approved the ISP guidance for utilization of surveillance data, but also established the NRCs own requirement that surveillance data not be used directly unless there is a heat match.

The ISP surveillance capsule data were reviewed for the BSEP representative materials, plate heat no. B0673-1, contained in the Duane Arnold and SSP-F capsules, and weld heat no.

5P6756, contained in the River Bend and SSP-C, -F, and -H capsules. An evaluation of the data for the BSEP representative materials is provided in BWRVIP-135, Revision 3, Tables A-3-4 and B-11-4 (i.e., Reference 2). Review of that data confirms that for the BSEP representative materials, the measured Charpy T30 shift values are within the normally accepted scatter in the predicted shift. That is, the difference between the measured shift and

RA-18-0163 Enclosure 1 Page 3 of 9 the predicted shift is smaller than the margin term, where margin is the lesser of the predicted shift or 34°F for plates or 56°F for welds. Relevant excerpts of BWRVIP-135, Revision 3 are included as Enclosure 2. Enclosure 4 provides a non-proprietary version.

Therefore, the use of BWRVIP ISP surveillance data in the proposed PTLR is fully in compliance with the approved procedures in BWRVIP-86, Revision 1-A and the requirements of Regulatory Guide 1.99, Revision 2.

BWRVIP-86, Revision 1-A provides the requirements for the BWRVIP ISP and was approved by NRC SE on October 20, 2011. The use of surveillance data, as proposed by the NRC in MVIB RAI-2, appears to conflict with the NRC approved requirements of the ISP as detailed in BWRVIP-86, Revision 1-A, Section 5.6, which specifically discusses Data Utilization and identifies two options.

Option 1 states the following:

Under option 1, if the heat of material does not specifically match the limiting heat of beltline material for that vessel, the chemistry factor for the limiting beltline material will be determined by the tables in Reg. Guide 1.99, Rev. 2. The corresponding margin term as stated in Position C.1 will apply. Data from the representative material will be analyzed to confirm that the measured Charpy T30 shift is within the normally expected scatter in the predicted shift. The same method (i.e., Position C.1) will be applied to calculate adjusted reference temperature (ART) for all weld and plate materials in the vessel beltline.

Position 1.1 is located in Position C.1 of Regulatory Guide 1.99, Revision 2. Therefore, this statement provides the basis for how ISP data was utilized in the development of the BSEP PTLR.

Option 2 specifically states the following:

If two or more surveillance data sets with matching heat numbers are available for the limiting beltline material, Option 2 may be used to calculate adjusted reference temperature when the data has been determined to be credible. The chemistry factor and margin term are calculated using Reg. Guide 1.99, Rev. 2, Position C.2.

MVIB RAI-2 requests that data for the representative surveillance materials be applied directly to the target vessel materials using Regulatory Guide 1.99, Revision 2, Position 2.1 even though the surveillance material heat numbers do not match the materials in the BSEP reactor vessels.

Position 2.1 is located in Section C.2, Surveillance Data Available, of Regulatory Guide 1.99, Revision 2, and the requirements shown above specifically state Position C.2 may only be used when the heat numbers of the materials match. Therefore, the use of Position 2.1, as requested in the RAI, is not permitted per the NRC approved requirements in BWRVIP-86, Revision 1-A.

The BWRVIP-86, Revision 1-A data utilization requirements quoted above were also contained in Revision 0 of BWRVIP-86. The NRC issued a SE for BWRVIP-86, Revision 0, on February 1, 2002. The following was stated in Section 4.1 of that SE:

It should, however, be noted that although a surveillance material may be determined to be the "best representative material for a specific RPV material, the similarity between the surveillance material and the RPV material may not be sufficient to justify direct use (see Regulatory Guide 1.99, Revision 2, position C.2) of the surveillance data in

RA-18-0163 Enclosure 1 Page 4 of 9 determining the behavior of the RPV material. This topic is discussed further in Section 4.3 below. It is sufficient to mention at this point that additional differences between surveillance materials and RPV materials (e.g., heat treatment during fabrication) can complicate the direct use of such surveillance data, particularly if advanced fracture mechanics-based evaluations (i.e., the Master Curve methodology),

which are outside of the scope of this submittal, were to be employed.

The discussion continues in Section 4.3 of the SE, where NRC established the following conditions regarding use of ISP surveillance data:

The staff has concluded that the BWRVIP proposal for how surveillance data resulting from the ISP may be used to support BWR RPV fracture toughness (integrity) evaluations was acceptable. Consistent with current practice based on the use of data from plant-specific surveillance programs, data which is to be used directly (see position C.2. of NRC Regulatory Guide 1.99, Revision 2) to modify RPV integrity evaluations should come from surveillance material samples with the same heat number as the limiting RPV material. If position C.2. is used, appropriate adjustments for chemistry and irradiation temperature differences between the surveillance material and the RPV limiting material must be addressed. The NRC staff will review the direct utilization of surveillance data resulting from the ISP program as part of plant-specific RPV integrity evaluations. Surveillance materials which do not share the same heat number with the limiting RPV material may be used for general monitoring, but not for direct determination of RPV embrittlement. In such cases, the chemistry factor table of position C.1. of NRC Regulatory Guide 1.99, Revision 2 should be used. [emphasis added]

The discussion above shows that the NRC imposed a condition that surveillance data be utilized using Position C.2, which includes Position 2.1, for materials with the same heat number only. It further states that for materials that do not share the same heat number, Position C.1 should be used, which is consistent with the approach taken in the BSEP PTLR.

Finally, it is noted that the SE for BWRVIP-86, Revision 1-A, states in Section 4.0, Limitations and Conditions, that:

Conditions discussed in previous NRC staff SEs, not explicitly modified in this SE, remain in effect for this SE.

Because the SE for BWRVIP-86, Revision 1, includes no discussion concerning the utilization of surveillance data, the conditions from the SE for BWRVIP-86, Revision 0, as discussed above, remain in effect.

In summary, the utilization of BWRVIP ISP surveillance data in the proposed PTLR is fully in compliance with the approved procedures in BWRVIP-86, Revision 1-A, and the requirements of Regulatory Guide 1.99, Revision 2.

MVIB RAI-3 Section 3 of the PTLR states that, "The 54 EFPY limiting material in Unit 1 is plate heat number B8496 which is located in the lower intermediate shell. The limiting material in Unit 2 are the N16 nozzles, heat number Q2Q1VW." This statement indicated that there is only one limiting material in the beltline region for each BSEP unit. However, the abrupt change of curve pattern regarding the P-T limits for the beltline region of Unit 2 shown in Figures 5 and 6 of

RA-18-0163 Enclosure 1 Page 5 of 9 to the PTLR suggests that two limiting materials exist for Unit 2. Please explain this apparent discrepancy.

Response to MVIB RAI-3 The materials with the limiting ART values in the Unit 1 and 2 beltlines are plate heat no. B8496 and instrument nozzle (i.e., N16) heat no. Q2Q1VW, respectively. The NRC noted a discontinuity in the P-T curve for the Unit 2 beltline (i.e., Curves B and C in Figures 5 and 6 in the proposed PTLR). The discontinuity is caused by two different beltline components producing the limiting P-T curve over different temperature ranges. The beltline plates/welds produced the limiting beltline curve at lower temperatures, up to approximately 130°F for Curve B and 170°F for Curve C, while the N16 nozzles produced the limiting beltline curve at higher temperatures. The P-T curves for individual components are shown in Figures B-5 and B-6 in Appendix B to the attached SI Calculation No. 1700147.302, Revision 0. A copy of SI Calculation No. 1700147.302, Revision 0, is included in Enclosure 5 of this submittal.

MVIB RAI-4 Page 5 of Attachment 1 to the PTLR (in Section 4.0) states, "The Single Relief or Safety Valve (SRV) Blowdown thermal transient eventhas a maximum cooldown rate of 954 °F/hr and is the limiting Service A/B event used in the calculations of Limit Curve B and Curve C." Please confirm that, in addition to the beltline region, a cooldown rate of 954 °F/hr was also used for developing the P-T limits for the instrument nozzle, the bottom head, and the non-beltline region. If a different cooldown rate was used, please justify its use. Confirm that the composite curve is the only P-T limits monitored during operation.

Response to MVIB RAI-4 The P-T limits for the beltline region, instrument nozzle, bottom head, and non-beltline region are bounding with respect to the limiting Service Level A/B event, which is the SRV blowdown transient with maximum cooldown rate of 954°F/hr. To develop the P-T curves for the beltline region, N16 nozzle, and non-beltline region (i.e., feedwater nozzle), the applied thermal stress intensity factors, KIT, used as input to the P-T curves were obtained from the stress distribution output of a plant-specific finite element analysis (FEA). For the bottom head, KIT was determined from KIT for the beltline shell, scaling to account for differences in wall thickness between the bottom head and beltline plates. For each component, stresses and stress intensity factors were calculated for each of two transients, (1) the Shutdown transient and (2) the limiting Service Level A/B transient, identified as the SRV blowdown event with a maximum cooldown rate during the transient of 954°F/hr. The KIT for the SRV blowdown event was found to bound KIT for the shutdown transient for the N16 nozzle, beltline region, and bottom head. The KIT for the shutdown transient was found to bound KIT for the SRV blowdown event for the feedwater nozzle. For each component, the bounding KIT was used as input to the P-T curve for that component.

BSEP has confirmed that the composite (i.e., overall bounding) P-T curve is the only set of P-T limits monitored during operation.

MVIB RAI-5 Whenever a new TR methodology is applied to generate the P-T limits, the NRC performs confirmatory calculations to verify successful implementation of the methodology. For the

RA-18-0163 Enclosure 1 Page 6 of 9 present submission, insufficient information has been provided to permit the NRC staff to perform these calculations. Therefore,

1) For the beltline region, using Table 2 on page 29 of Attachment 1 (BSEP Unit 1, Core Not Critical, Curve B, Beltline Region) to the PTLR as an example, provide fluid temperature, the temperature at a quarter thickness of the vessel wall (1/4T temperature), the pressure K (KIP), and KIT value for a sufficient number of pairs of pressure and temperature in the Table, so that the NRC staff can verify the P-T limits.

2) For the non-beltline region, since the P-T limits for it first appeared in the proposed P-T limits, please explain the assumptions, including those specific to the BSEP units, made to ensure that the BSEP P-T limits based on the feedwater nozzle bound the non-beltline region (e.g., recirculation inlet and outlet nozzles and core spray nozzle). Using Table 2 on page 31 of Attachment 1 (BSEP Unit 1, Core Not Critical, Curve B, Non-Beltline Region) to the PTLR as an example, provide fluid temperature, 1/4T temperature, the RTNDT value, and KIP and KIT values for a typical temperature and pressure pair, so that the NRC staff can verify the P-T limits.

3) For the bottom head region, due to lack of neutron embrittlement, the P-T limits for it should remain unchanged. Please explain why the proposed bottom head P-T limits are different from that in the current licensing basis. Using Table 2 on page 30 of Attachment 1 (BSEP Unit 1, Core Not Critical, Curve B, Bottom Head Region) to the PTLR as an example, provide similar information requested in Item 2, so that the NRC staff can verify the P-T limits. Please also elaborate the details of the KIT calculation.

Response to MVIB RAI-5 Responses to items 1 through 3 for this RAI are provided below.

1) For the beltline region, values for fluid temperature, KIP, and KIT used in development of the P-T limits are provided in Appendix B of the attached SI Calculation No.

1700147.302, Revision 0 (i.e., Enclosure 5). Values for metal temperature at 1/4T location are not used, as the fluid temperature is conservatively used to calculate the P-T limits for the beltline, non-beltline, and bottom head regions.

2) For the non-beltline region, values for fluid temperature, KIP, and KIT used in development of the P-T limits are provided in Appendix B of the attached SI Calculation No. 1700147.302, Revision 0.

The feedwater nozzle is assumed to be the bounding non-beltline component for development of the BSEP P-T limits. The basis for this assumption is provided in Section 3.0 of the attached SI Calculation No. 1700147.302, Revision 0. The bounding RTNDT for the non-beltline region for each unit, excluding the bottom head, is used in development of the feedwater nozzle P-T limits.

3) For the bottom head region, values for fluid temperature, KIP, and KIT used in development of the P-T limits are provided in Appendix B of the attached SI Calculation No. 1700147.302, Revision 0.

In the proposed PTLR, the bottom head curve has been updated from the curve in the current P-T limits to bound the SRV blowdown transient, as discussed in the response to MVIB RAI-4 above.

RA-18-0163 Enclosure 1 Page 7 of 9 The method for calculating applied KIT for the bottom head is provided in Step 3 of Section 2.0 in the attached SI Calculation No. 1700147.302, Revision 0. KIT for the bottom head is determined from the KIT for the beltline shell and is scaled to account for the increased thickness of the bottom head relative to the beltline plates. The scaling factor is determined using the relationship between stress intensity factor and wall thickness given in Paragraph G-2214.3 of ASME Section XI, Nonmandatory Appendix G, for a postulated axial or circumferential inside surface defect:

KIT = 0.953 x 10-3

CR

t2.5 where CR is cooldown rate in °F/hr and t is vessel wall thickness in inches. The scaled KIT for the bottom head is calculated by:

KIT,bottom head / tbottom head2.5 = KIT,beltline / t beltline2.5 The bottom head center plates and side plates have different thicknesses. Considering the effect of thickness on both the allowable RPV internal pressure and KIT, the thicker bottom head center plates are found to produce the most limiting P-T Curves B and C.

For P-T Curve A, KIT is zero, and the thinner bottom head side plates produce the most limiting P-T Curve A. The bottom head thickness and KIT found to produce the most limiting P-T curve is used for each curve.

SNPB RAI 1 In the supplement to the LAR dated May 29, 2018, the licensee submitted WCAP-17660-NP, "Neutron Exposure Evaluations for Core Shroud and Pressure Vessel Brunswick Units 1 and 2,"

dated November 2012. Section 1.0 of WCAP-17660-NP states that the neutron fluence calculational methodology used in the fluence analysis has been applied to the Brunswick reactors in the past and was previously reviewed and accepted in the NRC staff in BSEP Units 1 and 2 Amendment Nos. 228 and 256, respectively, issued on June 18, 2003 (ADAMS Accession No. ML031710175). Section 1.0 states that neutron fluence calculational methodology complies with RG 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence." These amendments contain the NRC staff evaluation of the Brunswick neutron fluence calculational methodology used to determine the fluence for the current P-T limits. The same neutron fluence calculational methodology was used as part of license renewal in 2006.

However, Section 3.0 of WCAP-17660-NP states that the neutron fluence calculational methodology has been enhanced:

Several enhancement[s] to the analytical model to better describe the [boiling water reactor] fuel and bypass coolant features for the outermost row of peripheral assemblies, which are the most influential to the neutron exposures at the core shroud and the reactor vessel. The results of this evaluation indicate that, in general, the projected neutron exposures of critical components are less than those reported in [the 2003 license amendment request].

Confirm that the methodology to be used as part of the proposed pressure temperature limits report methodology is the same as the previously approved Brunswick neutron fluence calculational methodology in Amendment Nos. 228 and 256 so the NRC staff can confirm continued adherence to RG 1.190. If not, describe and justify the differences.

RA-18-0163 Enclosure 1 Page 8 of 9 Response to SNPB RAI 1 The fluence calculational methodology in Westinghouse Report No. WCAP-17660-NP, Revision 0 (i.e., Reference 3), which is used as the basis for the proposed P-T limits, is the same as the previously used fluence calculational methodology in Carolina Power & Light (CP&L) Calculation No. 0B11-0012, Revision 0 (i.e., Reference 4) for the current P-T limits in Amendments 228 and 256.

The model enhancements cited in the RAI refer to the modeling of the core geometry. In WCAP-17660-NP, the interior regions of the core and the peripheral regions of the core are modeled as separate regions, whereas in the CP&L Calculation No. 0B11-0012, Revision 0, the entire core was modeled as a single region.

SNPB RAI 2 In the supplement to the LAR dated May 29, 2018, (WCAP-17660-NP), in Section 2.1 in the subsection titled, "Fuel Cycle Modeling," the licensee described the approach used to determine the reactor pressure vessel neutron fluence for future nominal Maximum Extended Load Line Limit Analysis Plus (MELLLA+) equilibrium fuel cycles. The licensee also provided tables with assumed relative power fraction (RPF), axial power, and axial void fraction distribution inputs to the fluence calculational model for operating under MELLLA+ conditions to be used to confirm that the actual core design is comparable to the nominal. If the actual RPFs, axial power, or axial void fraction distributions are not bounded by those nominally assumed when MELLLA+ is implemented at Brunswick, updated fluence values would need to be determined for input to P-T limits re-assessment. However, the licensee does not describe an approach for determining updated fluence values.

Describe the approach for determining updated fluence values if the actual RPFs, axial power, or axial void fraction distributions are not bounded by those assumed in the WCAP-17660-NP fluence analysis when MELLLA+ is implemented at BSEP.

Response to SNPB RAI 2 If the assumptions supporting the fluence projections in WCAP-17660-NP are not implemented or are not realistic for actual MELLLA+ operating conditions, then the actual neutron fluence will diverge from the fluence projections. Neutron fluence will be re-evaluated on an as-needed basis to include operating data and new fuel projections. In-vessel neutron dosimetry will also be used to track neutron fluence and ensure the adequacy of the fluence projections while avoiding violation of P-T Limits.

References

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

2. 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.

3. Westinghouse Report No. WCAP-17660-NP, Revision 0, Neutron Exposure Evaluations for Core Shroud and Pressure Vessel, Brunswick Units 1 and 2, November 2012.

RA-18-0163 Enclosure 1 Page 9 of 9

4. CP&L Calculation No. 0B11-0012, Revision 0, [Westinghouse Electric Company LLC Report LTR-REA-02-7], Neutron Exposure Evaluation for the Core Shroud and Pressure Vessel, Brunswick Units 1 and 2, January 2002.

RA-18-0163 Enclosure 3 EPRI Affidavit Regarding Withholding

2018-118 BWR Vessel & Internals Project (BWRVIP)

September 18, 2018 Mr. Victor Bliss Duke Energy 8470 River Road SE Southport, NC 28461

Subject:

Transmittal of EPRI Proprietary Affidavit to the NRC The purpose of this letter is to transmit EPRI proprietary affidavit for transmittal of the following document to the NRC:

Duke Energy Submittal to the NRC, Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report, Enclosure 2, Excerpts from BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (SP) Data Source Book and Plant Evaluations Please note that the enclosed document contains EPRI proprietary information. A letter requesting that the report be withheld from public disclosure and an affidavit describing the basis for withholding this information are provided as Attachment 1.

If you have any questions on this subject, please contact me by telephone at 704-502-6440 or by e-mail at amcgehee@epri.com Sincerely, Andrew McGehee EPRI, BWRVIP Program Manager

BWRVIP 2018-118, Attachment 1

RA-18-0163 Enclosure 4 Excerpts from BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (SP) Data Source Book and Plant Evaluations Non-Proprietary

EPRI PROPRIETARY LICENSED MATERIAL 2014 TECHNICAL REPORT BWRVIP-135, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations SED N

R I LICE A L M AT E SED N WARNING: NOTICE: This report contains proprietary information that is the intellectual property of R I LICE A L Please read the Export Control EPRI. Accordingly, it is available only under license from EPRI and may not be reproduced M AT E Agreement on the back cover. or disclosed, wholly or in part, by any licensee to any other person or organization.

EPRI PROPRIETARY LICENSED MATERIAL BWRVIP-135, Revision 3: BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations 3002003144 Technical Report, December 2014 EPRI Project Manager R. Carter All or a portion of the requirements of the EPRI Nuclear Quality Assurance Program apply to this product.

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EPRI PROPRIETARY LICENSED MATERIAL Plant-Specific Evaluations Brunswick 1 Representative Surveillance Materials The ISP Representative Surveillance Materials for the Brunswick 1 vessel target weld and plates are shown in the following table.

Table 2-10 Target Vessel Materials and ISP Representative Materials for Brunswick 1 Target Vessel Materials ISP Representative Materials Weld 1P4218 5P6756 Plate B8496-1 B0673-1 Summary of Available Surveillance Data: Plate The representative plate material B0673-1 is contained in the following ISP capsules:

Duane Arnold Capsules SSP Capsule F Specific surveillance data related to plate heat B0673-1 are summarized in Appendix A-3. Four capsules containing this plate heat have been tested. The Charpy V-notch surveillance results are as follows:

Table 2-11 T30 Shift Results for Plate Heat B0673-1 Cu Ni Fluence Capsule 17 2 T30 (°F)

(wt%) (wt%) (10 n/cm ,E > 1 MeV)

Duane Arnold 288° 5.09 41.8 Duane Arnold 36° 11.7 77.0 0.15 0.65 SSP F 18.699 73.4 Duane Arnold 108° 26.3 94.3 The results given in Appendix A-3 show a fitted chemistry factor (CF) of (( {E})), as compared to a value of 111.25°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( {E})), which is well within the 1-sigma value of 17°F for plates as given in Reg. Guide 1.99, Rev. 2.

Conclusions and Recommendations Because the representative plate material is not the same heat number as the target plate in the Brunswick 1 vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables (Regulatory Position 1.1) to determine the projected ART value for the target vessel plate. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.

2-8

EPRI PROPRIETARY LICENSED MATERIAL Plant-Specific Evaluations Summary of Available Surveillance Data: Weld The representative weld material 5P6756 is contained in the following ISP capsules:

River Bend Capsules SSP Capsules C, F, and H Specific surveillance data related to weld heat 5P6756 are presented in Appendix B-11 and the results are summarized below. Four capsules containing weld heat 5P6756 have been tested.

The Charpy V-notch surveillance results are as follows:

Table 2-12 T30 Shift Results for Weld Heat 5P6756 Cu Ni Fluence Capsule 17 2 T30 (°F)

(wt%) (wt%) (10 n/cm , E > 1 MeV)

River Bend 183° 11.6 53.7 SSP F 19.364 61.9 0.06 0.93 SSP H 15.766 63.7 SSP C 2.93 23.6 The results given in Appendix B-11 show a fitted chemistry factor (CF) of (( {E})), as compared to a value of 82.0°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is well within the 1-sigma value of 28°F for welds as given in Reg. Guide 1.99, Rev. 2.

Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the Brunswick 1 vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables to determine the projected ART value for the target vessel weld. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.

2-9

EPRI PROPRIETARY LICENSED MATERIAL Plant-Specific Evaluations Brunswick 2 Representative Surveillance Materials The ISP Representative Surveillance Materials for the Brunswick 2 vessel target weld and plates are shown in the following table.

Table 2-13 Target Vessel Materials and ISP Representative Materials for Brunswick 2 Target Vessel Materials ISP Representative Materials Weld S3986 5P6756 Plate C4500-2 B0673-1 Summary of Available Surveillance Data: Plate The representative plate material B0673-1 is contained in the following ISP capsules:

Duane Arnold Capsules SSP Capsule F Specific surveillance data related to plate heat B0673-1 are summarized in Appendix A-3. Four capsules containing this plate heat have been tested. The Charpy V-notch surveillance results are as follows:

Table 2-14 T30 Shift Results for Plate Heat B0673-1 Cu Ni Fluence Capsule 17 2 T30 (°F)

(wt%) (wt%) (10 n/cm , E > 1 MeV)

Duane Arnold 288° 5.09 41.8 Duane Arnold 36° 11.7 77.0 0.15 0.65 SSP F 18.699 73.4 Duane Arnold 108° 26.3 94.3 The results given in Appendix A-3 show a fitted chemistry factor (CF) of (( {E})), as compared to a value of 111.25°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is (( {E})) which is well within the 1-sigma value of 17°F for plates as given in Reg. Guide 1.99, Rev. 2.

Conclusions and Recommendations Because the representative plate material is not the same heat number as the target plate in the Brunswick 2 vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables (Regulatory Position 1.1) to determine the projected ART value for the target vessel plate. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.

2-10

EPRI PROPRIETARY LICENSED MATERIAL Plant-Specific Evaluations Summary of Available Surveillance Data: Weld The representative weld material 5P6756 is contained in the following ISP capsules:

River Bend Capsules SSP Capsules C, F, and H Specific surveillance data related to weld heat 5P6756 are presented in Appendix B-11 and the results are summarized below. Four capsules containing weld heat 5P6756 have been tested. The Charpy V-notch surveillance results are as follows:

Table 2-15 T30 Shift Results for Weld Heat 5P6756 Cu Ni Fluence Capsule 17 2 T30 (°F)

(wt%) (wt%) (10 n/cm , E > 1 MeV)

River Bend 183° 11.6 53.7 SSP F 19.364 61.9 0.06 0.93 SSP H 15.766 63.7 SSP C 2.93 23.6 The results given in Appendix B-11 show a fitted chemistry factor (CF) of (( {E})), as compared to a value of 82.0°F from the chemistry tables in Reg. Guide 1.99, Rev. 2. The maximum scatter in the fitted data is well within the 1-sigma value of 28°F for welds as given in Reg. Guide 1.99, Rev. 2.

Conclusions and Recommendations Because the representative weld material is not the same heat number as the target weld in the Brunswick 2 vessel, the utility should use the chemistry factor from the Regulatory Guide 1.99, Rev. 2 tables to determine the projected ART value for the target vessel weld. Recommended guidelines for evaluation of ISP surveillance data are provided in Section 3 of this Data Source Book.

2-11

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations A-3 Plate Heat: B0673-1 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for plate heat B0673-1 are listed in Table A-3-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets.

Table A-3-1 ISP Capsules Containing Plate Heat B0673-1 17 Fluence (E> 1 MeV, 10 Capsule 2 Reference n/cm )

Unirradiated Baseline Data --

Duane Arnold 288° 5.09 References A-3-1 and A-3-2 Duane Arnold 36° 11.7 SSP Capsule F 18.699 Reference A-3-3 Duane Arnold 108° 26.3 Reference A-3-2 The CVN test data for each set taken from the references noted above are presented in Tables A-3-7 through A-3-11. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanh curve plots for each data set have been generated using CVGRAPH, Version 5 [A-3-4] and the plots are provided in Figures A-3-1 through A-3-5.

Best Estimate Chemistry Table A-3-2 details the best estimate average chemistry values for plate heat B0673-1 surveillance material. Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate.

Table A-3-2 Best Estimate Chemistry of Available Data Sets for Plate Heat B0673-1 Cu (wt%) Ni (wt%) P (wt%) S (wt%) Si (wt%) Specimen ID Source 0.15 0.7 0.006 -- 0.07 ETJ 0.15 0.69 0.006 -- 0.06 ETK 0.14 0.62 0.010 -- 0.01 EB4 Reference A-3-1 0.141 0.62 0.014 -- 0.02 EBA 0.145 0.65 0.010 -- 0.09 EBE 0.15 0.61 0.011 -- 0.18 Baseline CMTR Reference A-3-1 0.15 0.65 0.010 -- 0.07 Best Estimate Average Calculation of Chemistry Factor (CF):

The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S. NRC Regulatory Guide 1.99, Revision 2 [A-3-5], Table 2 (base metal), is:

CF(B0673-1) = 111.25°F A-3-1

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Effects of Irradiation The radiation induced transition temperature shifts for heat B0673-1 are shown in Table A-3-3.

The T30 [30 ft-lb Transition Temperature], T50 [50 ft-lb Transition Temperature], and T35mil

[35 mil Lateral Expansion Temperature] have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures. The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented).

Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (T30) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table A-3-4 compares the predicted shift with the measured T30 (°F) taken from Table A-3-3.

Comparison of Actual vs. Predicted Decrease in USE Table A-3-5 compares the actual percent decrease in upper shelf energy (USE) to the predicted decrease. The predicted decrease is estimated from USNRC Regulatory Guide 1.99, Rev. 2, Figure 2; the measured percent decrease is calculated from the values presented in Table A-3-3.

A-3-2

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Table A-3-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Plate Heat B0673-1 T30, 30 ft-lb T50, 50 ft-lb T35mil, 35 mil Lateral CVN Upper Shelf Energy Material Capsule Transition Temperature Transition Temperature Expansion Temperature (USE)

Identity ID Unirrad Irrad T30 Unirrad Irrad T50 Unirrad Irrad T35mil Unirrad Irrad Change

(°F) (°F) (°F) (°F) (°F) (°F) (°F) (°F) (°F) (ft-lb) (ft-lb) (ft-lb) 288° -35.5 6.3 41.8 -7.3 42.4 49.7 -23.6 18.6 42.2 158.1 158.8 0.7 DA1 and 36° -35.5 41.5 77.0 -7.3 70.7 78.0 -23.6 55.7 79.3 158.1 137.0 -21.1 SSP B0673-1 SSP F -35.5 37.9 73.4 -7.3 66.9 74.2 -23.6 57.8 81.4 158.1 133.0 -25.1 108° -35.5 58.8 94.3 -7.3 91.4 98.7 -23.6 87.1 110.7 158.1 131.3 -26.8 Table A-3-4 Comparison of Actual Versus Predicted Embrittlement for Plate Heat B0673-1 RG 1.99 Rev. 2 1 RG 1.99 Rev. 2 Fluence Measured Shift 2 Predicted Capsule Identity Material 18 2 Predicted Shift 2, 3 (x10 n/cm ) °F Shift+Margin

°F

°F DA 288° Plate Heat B0673-1 in Duane Arnold 0.509 41.8 32.9 65.8 DA 36° Plate Heat B0673-1 in Duane Arnold 1.17 77.0 50.0 84.0 SSP F Plate Heat B0673-1 in SSP 1.8699 73.4 61.6 95.6 DA 108° Plate Heat B0673-1 in Duane Arnold 2.63 94.3 70.8 104.8 Notes:

1. See Table A-3-3 T30.

2. Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each materials Cu/Ni content, and FF is Fluence Factor, f0.28-0.10 log f, where f = fluence (1019 n/cm2, E > 1.0 MeV).

3. Margin = 2(i2 + 2), where i = the standard deviation on initial RTNDT (which is taken to be 0ºF), and is the standard deviation on RTNDT (28ºF for welds and 17ºF for base materials, except that need not exceed 0.50 times the mean value of RTNDT). Thus, margin is defined as 34°F for plate materials and 56°F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.

A-3-3

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Table A-3-5 Comparison of Actual Versus Predicted Percent Decrease in Upper Shelf Energy (USE) for Plate Heat B0673-1 RG 1.99 Rev. 2 Fluence Cu Content Measured Decrease in Capsule Identity Material 18 2 1 Predicted Decrease (x10 n/cm ) (wt%) USE (%) 2 in USE (%)

3 DA 288° Plate Heat B0673-1 in Duane Arnold 0.509 0.15 -- 11.9 DA 36° Plate Heat B0673-1 in Duane Arnold 1.17 0.15 13.3 14.4 SSP F Plate Heat B0673-1 in SSP 1.8699 0.15 15.9 16.1 DA 108° Plate Heat B0673-1 in Duane Arnold 2.63 0.15 17.0 17.5 Notes:

1. See Table A-3-3, (Change in USE)/(Unirradiated USE).

2. Calculated using equations in Regulatory Guide 1.162 [A-3-6] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2.

3. Less than zero.

A-3-4

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [A-3-7]. The following evaluation is based on the available surveillance data for irradiated plate heat B0673-1. The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation.

Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment.

Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.

Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are presented in this sub-appendix. Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met.

Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of RTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 17°F for plates. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82

[A-3-8].

For plate material B0673-1, there are 4 surveillance capsule data sets currently available.

The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these RTNDT values about this line is less than 17°F for plates. Figure A-3-6 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2.

The scatter of RTNDT values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table A-3-6.

A-3-5

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Table A-3-6 Best Fit Evaluation for Surveillance Plate Heat B0673-1

<17°F Measured Best Fit Scatter (Base Metal)

Fitted CF RTNDT Material Capsule FF RTNDT of RTNDT <28°F

(°F) (30 ft-lb)

(°F) (°F) (Weld

(°F) metal)

(( {E})) `` 288° {E}))

B0673-1 0.290 41.8 (( ``(( {E})) `` Yes

(( {E})) `` {E}))

36° 0.436 77.0 (( ``(( {E})) `` Yes

(( {E})) `` {E}))

SSP F 0.553 73.4 (( ``(( {E})) Yes

(( {E})) `` {E}))

108° 0.637 94.3 (( `` (( {E})) Yes Table A-3-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, plate heat B0673-1 meets this criterion.

Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within + / - 25°F.

BWRVIP-78 [A-3-9] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater. Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.

Few ISP capsules contain correlation monitor material. Generally, this criterion is not applicable.

For plate heat B0673-1, these criteria are satisfied (or not applicable). The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist.

A-3-6

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Table A-3-7 Unirradiated Charpy V-Notch Results for Surveillance Plate B0673-1 (LT)

Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear ED4 -100 6.5 7.0 0 ED1 -80 4.2 5.0 0 ECT -40 9.0 14.0 10 EDK -40 24.0 30.0 5 ED7 -30 38.0 35.0 5 EDT -30 49.0 30.0 5 ED6 -20 47.0 43.0 10 ED5 -10 43.0 43.0 20 ECP 0 56.5 49.0 25 ECM 40 98.5 73.0 40 ECL 120 134.5 73.0 80 ECK 200 158.5 93.0 85 EDY 300 163.5 81.0 90 EDA 400 No Break No Break No Break Table A-3-8 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 288 Deg Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear EBU -60 4.0 4.0 0 EBP -20 15.0 19.0 0 EBT 10 15.5 26.0 40 EC1 20 49.5 45.0 40 EBK 40 60.0 49.0 40 EBJ 120 101.5 70.0 70 EBL 200 144.5 95.0 90 EBY 400 160.0 98.0 90 A-3-7

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Table A-3-9 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 36 Deg Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear EBD -50 5.0 5.0 1 EB1 0 18.5 15.0 41 EB2 13 27.7 24.0 10 EB3 25 13.7 13.0 27 EBC 32 15.4 23.0 24 EB6 40 15.4 16.0 32 EB4 49 59.2 48.0 32 EB5 81 51.5 43.0 44 EBA 120 92.9 69.0 78 EB7 202 127.8 82.0 100 EBE 250 142.8 84.0 100 EBB 400 140.5 94.0 100 Table A-3-10 Charpy V-Notch Results for B0673-1 (LT) in SSP Capsule F Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear EDJ 0 12.5 9.0 0 ECU 30 25.5 22.0 20 EDD 50 24.5 21.0 20 ECY 50 34.5 26.0 30 EDM 70 71.5 54.0 45 EDP 150 103.5 78.0 75 EDB 175 113.5 82.0 85 ED2 200 139.0 89.0 100 ECJ 300 134.5 91.0 100 ECE 400 125.5 85.0 100 A-3-8

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Table A-3-11 Charpy V-Notch Results for B0673-1 (LT) in Duane Arnold 108° Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear ECB -1.3 4.2 5.0 4.2 ECC 35.8 23.88 17.3 10.4 EC3 69.1 42.06 30.4 17.6 EC7 128.7 63.71 48.5 38.6 ECD 160.5 111.06 76.2 67.2 ECA 191.5 110.36 76.0 84.1 EC4 252.0 129.48 91.0 100.0 EC5 400.8 133.11 92.9 100.0 A-3-9

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Tanh Curve Fits of CVN Test Data for Plate Heat B0673-1 Figure A-3-1 Charpy Energy Data for Plate B0673-1 (LT) Unirradiated A-3-10

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-1 Charpy Energy Data for Plate B0673-1 (LT) Unirradiated (Continued)

A-3-11

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-2 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 288° Capsule A-3-12

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-3 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 36° Capsule A-3-13

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-3 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 36° Capsule (Continued)

A-3-14

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-4 Charpy Energy Data for Plate B0673-1 (LT) in SSP Capsule F A-3-15

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-4 Charpy Energy Data for Plate B0673-1 (LT) in SSP Capsule F (Continued)

A-3-16

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations Figure A-3-5 Charpy Energy Data for Plate B0673-1 (LT) in Duane Arnold 108° Capsule A-3-17

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations

((

{E}))

Figure A-3-6 Fitted Surveillance Results for Plate Heat B0673-1 A-3-18

EPRI PROPRIETARY LICENSED MATERIAL ISP Plate Heat Evaluations References A-3-1. GE Nuclear Energy, Duane Arnold RPV Surveillance Materials Testing and Analysis, GE-NE-B1100716-01, July 1997.

A-3-2. BWRVIP-279NP: BWR Vessel and Internals Project, Testing and Evaluation of the Duane Arnold 108° Capsule. EPRI, Palo Alto, CA: 2014. 3002003134.

A-3-3. BWRVIP-111NP, Revision 1: BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance Program Capsules E, F and I. EPRI, Palo Alto, CA:

2010. 1021554.

A-3-4. CVGRAPH, Hyperbolic Tangent Curve Fitting Program, Developed by ATI Consulting, Version 5.0.2, Revision 1, 3/26/02.

A-3-5. Radiation Embrittlement of Reactor Vessel Materials, USNRC Regulatory Guide 1.99, Revision 2, May 1988.

A-3-6. Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels, USNRC Regulatory Guide 1.162, February 1996.

A-3-7. K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998.

A-3-8. ASTM E-185, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials, July 1982.

A-3-9. BWR Vessel and Internals Project: BWR Integrated Surveillance Program Plan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-114228.

A-3-19

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations B-11 Weld Heat: 5P6756 Summary of Available Charpy V-Notch Test Data The available Charpy V-notch test data sets for weld heat 5P6756 are listed in Table B-11-1. The source documents for the data are provided, and the capsule designation and fluence values are also provided for irradiated data sets.

Table B-11-1 ISP Capsules Containing Weld Heat 5P6756 17 2 Capsule Fluence (E> 1 MeV, 10 n/cm ) Reference Unirradiated Baseline Data -- Reference B-11-1 River Bend 183° 11.6 Reference B-11-2 SSP Capsule F 19.364 Reference B-11-3 SSP Capsule H 15.766 Reference B-11-1 SSP Capsule C 2.93 Reference B-11-12 The CVN test data for each set taken from the references noted above are presented in Tables B-11-7 through B-11-11. The BWRVIP ISP uses the hyperbolic tangent (tanh) function as a statistical curve-fit tool to model the transition temperature toughness data. Tanh curve plots for each data set have been generated using CVGRAPH, Version 5 [Reference B-11-4] and the plots are provided in Figures B-11-1 through B-11-5.

Best Estimate Chemistry Table B-11-2 details the best estimate average chemistry values for weld heat 5P6756 surveillance material. Chemical compositions are presented in weight percent. If there are multiple measurements on a single specimen, those are first averaged to yield a single value for that specimen, and then the different specimens are averaged to determine the heat best estimate.

Table B-11-2 Best Estimate Chemistry of Available Data Sets for Weld Heat 5P6756 Cu (wt%) Ni (wt%) P (wt%) S (wt%) Si (wt%) Specimen ID Source 0.06 0.93 0.013 0.015 0.37 TP2-72 0.04 0.92 0.009 -- -- TP2-72 Reference B-11-5 0.05 0.93 0.011 0.015 0.37 Average TP2-72 0.067 0.93 0.00659 -- 0.42 W-6 Reference B-11-2 0.06 0.93 0.009 0.015 0.40 Best Estimate Average B-155

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Calculation of Chemistry Factor (CF):

The Chemistry Factor (CF) associated with the best estimate chemistry, as determined from U.S.

NRC Regulatory Guide 1.99, Revision 2 [Reference B-11-6], Table 1 (weld metal), is:

CF(5P6756) = 82.0°F Effects of Irradiation The radiation induced transition temperature shifts for heat 5P6756 are shown in Table B-11-3.

The T30 [30 ft-lb Transition Temperature], T50 [50 ft-lb Transition Temperature], and T35mil

[35 mil Lateral Expansion Temperature] index temperatures have been determined for each Charpy data set, and each irradiated set is compared to the baseline (unirradiated) index temperatures. The change in Upper Shelf Energy (USE) is also shown. The unirradiated and irradiated values are taken from the CVGRAPH fits presented at the back of this sub-appendix (only CVN energy fits are presented).

Comparison of Actual vs. Predicted Embrittlement A predicted shift in the 30 ft-lb transition temperature (T30) is calculated for each irradiated data set using the Reg. Guide 1.99, Rev. 2, Regulatory Position 1.1 method. Table B-11-4 compares the predicted shift with the measured T30 (°F) taken from Table B-11-3.

Decrease in USE Table B-11-5 shows the actual percent decrease in upper shelf energy (USE). The measured percent decrease is calculated from the values presented in Table B-11-3.

B-156

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Table B-11-3 Effect of Irradiation (E>1.0 MeV) on the Notch Toughness Properties of Weld Heat 5P6756 T50, 50 ft-lb T30, 30 ft-lb T35mil, 35 mil Lateral CVN Upper Shelf Energy Transition Material Capsule Transition Temperature Expansion Temperature (USE)

Temperature Identity ID Unirrad Irrad T30 Unirrad Irrad T50 Unirrad Irrad T35mil Unirrad Irrad Change

(°F) (°F) (°F) (°F) (°F) (°F) (°F) (°F) (°F) (ft-lb) (ft-lb) (ft-lb) 183° -67.1 -13.4 53.7 -21.3 33.1 54.4 -20.3 11.4 31.7 104.4 84.4 -20.0 RB1 and SSP F -67.1 -5.2 61.9 -21.3 39.5 60.8 -20.3 31.7 52.0 104.4 79.3 -25.1 SSP 5P6756 SSP H -67.1 -3.4 63.7 -21.3 22.3 43.6 -20.3 12.5 32.8 104.4 84.6 -19.8 SSP C -67.1 -43.5 23.6 -21.3 0.7 22.0 -20.3 -17.4 2.9 104.4 110.7 6.3 Table B-11-4 Comparison of Actual Versus Predicted Embrittlement for Weld Heat 5P6756 RG 1.99 Rev. 2 1 RG 1.99 Rev. 2 Capsule Fluence Measured Shift 2 Predicted Material 18 2 Predicted Shift 2, 3 Identity (x10 n/cm ) °F Shift+Margin

°F

°F RB 183° Weld Heat 5P6756 in River Bend 1.16 53.7 36.7 73.3 SSP Capsule F Weld Heat 5P6756 in SSP Capsule F 1.9364 61.9 46.1 92.2 SSP Capsule H Weld Heat 5P6756 in SSP Capsule H 1.5766 63.7 42.2 84.3 SSP Capsule C Weld Heat 5P6756 in SSP Capsule C 0.293 23.6 17.8 35.5 Notes:

1. See Table B-11-3, T30.

2. Predicted shift = CF x FF, where CF is a Chemistry Factor taken from tables from USNRC Reg. Guide 1.99, Rev. 2, based on each materials Cu/Ni content, and FF is Fluence Factor, f0.28-0.10 log f, where f = fluence (1019 n/cm2, E > 1.0 MeV).

3. Margin = 2(i2 + 2), where i = the standard deviation on initial RTNDT (which is taken to be 0ºF), and is the standard deviation on RTNDT (28ºF for welds and 17ºF for base materials, except that need not exceed 0.50 times the mean value of RTNDT). Thus, margin is defined as 34°F for plate materials and 56°F for weld materials, or margin equals shift (whichever is less), per Reg. Guide 1.99, Rev. 2.

B-157

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Table B-11-5 Percent Decrease in Upper Shelf Energy (USE) for Weld Heat 5P6756 Measured RG 1.99 Rev. 2 Capsule Fluence Cu Content Material 18 2 Decrease in Predicted Decrease in Identity (x10 n/cm ) (wt%) 1 2 USE (%) USE (%)

RB 183° Weld Heat 5P6756 in River Bend 1.16 0.06 19.2 12.0 SSP Capsule F Weld Heat 5P6756 in SSP Capsule F 1.9364 0.06 24.0 13.6 SSP Capsule H Weld Heat 5P6756 in SSP Capsule H 1.5766 0.06 19.0 12.9 3

SSP Capsule C Weld Heat 5P6756 in SSP Capsule C 0.293 0.06 -- 8.7 Notes:

1. See Table B-11-3, (Change in USE)/(Unirradiated USE).

2. Calculated using equations in Regulatory Guide 1.162 [B-11-7] that accurately model the Charpy upper shelf energy decrease curves in Regulatory Guide 1.99, Revision 2

3. Value less than zero.

B-158

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Credibility of Surveillance Data The credibility of the surveillance data is determined according to the guidance of Regulatory Guide 1.99, Rev. 2 and 10 CFR 50.61, as supplemented by the NRC staff [Ref. B-11-8]. The following evaluation is based on the available surveillance data for irradiated weld heat 5P6756.

The applicability of this evaluation to a particular BWR plant must be confirmed on a plant-by-plant basis to verify there are no plant-specific exceptions to the following evaluation.

Per Regulatory Guide 1.99, Revision 2 and 10 CFR 50.61, there are 5 criteria for the credibility assessment.

Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

In order to satisfy this criterion, the representative surveillance material heat number must match the material in the vessel.

Criterion 2: Scatter in the plots of Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.

Plots of Charpy energy versus temperature for the unirradiated and irradiated condition are presented in this sub-appendix. Based on engineering judgment, the scatter in these plots is small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy. Hence, this criterion is met.

Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of RTNDT values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28°F for welds. Even if the fluence range is large (two or more orders of magnitude), the scatter should not exceed twice that value. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82

[Reference B-11-9].

For weld material 5P6756, there are 4 surveillance capsule data sets currently available. The functional form of the least squares fit method as described in Regulatory Position 2.1 is utilized to determine a best-fit line for this data and to determine if the scatter of these RTNDT values about this line is less than 28°F for welds. Figure B-11-6 presents the best-fit line as described in Regulatory Position 2.1 utilizing the shift prediction routine from CVGRAPH, Version 5.0.2.

The scatter of RTNDT values about the functional form of the best-fit line drawn as described in Regulatory Position 2.1 is presented in Table B-11-6.

B-159

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Table B-11-6 Best Fit Evaluation for Surveillance Weld Heat 5P6756

<17°F Measured Best Fit Fitted Scatter of (Base Metal)

Material Capsule FF RTNDT RTNDT CF (°F) RTNDT (°F) <28°F (30 ft-lb) (°F) (°F)

(Weld metal)

RB 183 0.447 53.70 (( {E})) (( {E})) Yes SSP F 0.562 61.90 (( {E})) (( {E}))

Yes 5P6756 (( {E}

))

SSP H 0.514 63.70 (( {E})) (( {E}))

Yes SSP C 0.217 23.6 (( {E})) (( {E}))

Yes Table B-11-6 indicates that the scatter is within acceptable range for credible surveillance data. Therefore, weld heat 5P6756 meets this criterion.

Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within + / - 25°F.

BWRVIP-78 [Reference B-11-10] established the similarity of BWR plant environments in the BWR fleet. The annulus between the wall and the core shroud in the region of the surveillance capsules contains a mix of water returning from the core and feedwater. Depending on feedwater temperature, this annulus region is between 525°F and 535°F. This location of specimens with respect to the reactor vessel beltline is designed so that the reactor vessel wall and the specimens experience equivalent operating conditions such that the temperature will not differ by more than 25°F. Any plant-specific exceptions to this generic analysis should be evaluated.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the database for that material.

Few ISP capsules contain correlation monitor material. Generally, this criterion is not applicable.

For weld heat 5P6756, these criteria are satisfied (or not applicable). The surveillance data are nominally credible because the scatter criterion is met. Prior to application of the data, a plant should verify that no plant-specific exceptions to these criteria exist.

B-160

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Table B-11-7 Unirradiated Charpy V-Notch Results for Surveillance Weld 5P6756 Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear 1 -100 7.5 0.0 14 2 -80 22.0 13.5 16 3 -60 43.0 27.5 26 4 -60 32.5 23.0 29 5 -40 47.0 30.5 34 6 -20 54.5 40.5 28 7 0 53.5 35.5 51 8 20 72.5 52.0 69 9 40 75.5 56.0 72 10 60 70.0 55.0 66 11 60 88.0 66.0 90 12 100 102.0 78.0 100 13 180 102.0 77.0 100 14 300 106.0 78.5 100 15 400 107.5 78.0 100 Table B-11-8 Charpy V-Notch Results for 5P6756 in RB 183° Capsule Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear W2 -42.52 21.43 20 21.5 W5 -41.98 36.74 33 28.7 W8 11.3 25.95 24 31.6 W6 11.48 27.43 23 31.8 W1 37.04 68.18 52.5 66.1 W10 37.22 48.05 41 55.6 W4 69.62 63.52 53.5 62.7 W9 69.98 66.41 58 79.3 W11 127.76 79.78 72 100 W3 131.18 80.22 71 93.3 W12 159.26 77.2 65.5 97.1 W7 199.76 96.33 78 100 B-161

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Table B-11-9 Charpy V-Notch Results for 5P6756 in SSP Capsule F Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear FP272G -60 15.0 8.0 15 FP272H -30 7.5 2.0 15 FP272C 0 37.5 26.0 45 FP272J 0 39.5 29.0 45 FP272I 50 55.0 44.0 65 FP272A 70 55.5 45.0 70 FP272B 150 78.0 66.0 95 FP272D 200 79.5 63.0 100 FP272E 300 80.0 74.0 100 FP272F 400 79.5 69.0 100 Table B-11-10 Charpy V-Notch Results for 5P6756 in SSP Capsule H Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear 30004 -25 9.5 10.0 10 30005 300 88.0 64.0 100 30006 200 82.0 73.0 98 30007 0 38.5 31.0 15 30008 50 66.5 53.0 80 30009 100 77.0 54.0 98 30010 150 81.0 56.0 99 30011 250 89.5 65.0 100 30012 25 53.0 43.0 50 30013 400 90.0 68.0 100 Table B-11-11 Charpy V-Notch Results for 5P6756 in SSP CapsuleC Spec ID Temp (°F) CVN (ft-lb) LE (mils) %Shear CP2-72-6 -80.14 14.11 12.0 14.2 CP2-72-5 -50.44 22.46 21.0 22.8 CP2-72-9 -40.36 38.92 32.0 26.5 CP2-72-8 -20.20 36.38 32.0 33.8 CP2-72-10 0.14 54.52 44.0 47.9 CP2-72-7 19.58 60.79 49.0 54.8 CP2-72-1 67.28 77.81 59.0 76.8 CP2-72-2 149.18 102.51 71.5 100 CP2-72-3 300.38 112.54 81.0 100 CP2-72-4 399.74 117.01 70.0 100 B-162

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Tanh Curve Fits of CVN Test Data for Weld Heat 5P6756 Figure B-11-1 Charpy Energy Data for Weld 5P6756 Unirradiated B-163

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-1 Charpy Energy Data for Weld 5P6756 Unirradiated (Continued)

B-164

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-2 Charpy Energy Data for Weld 5P6756 in RB 183° Capsule B-165

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-2 Charpy Energy Data for Weld 5P6756 in RB 183° Capsule (Continued)

B-166

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-3 Charpy Energy Data for Weld 5P6756 in SSP Capsule F B-167

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-3 Charpy Energy Data for Weld 5P6756 in SSP Capsule F (Continued)

B-168

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-4 Charpy Energy Data for Weld 5P6756 in SSP Capsule H B-169

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-4 Charpy Energy Data for Weld 5P6756 in SSP Capsule H (Continued)

B-170

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-5 Charpy Energy Data for Weld 5P6756 in SSP Capsule C B-171

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations Figure B-11-5 Charpy Energy Data for Weld 5P6756 in SSP Capsule C (Continued)

B-172

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations

((

{E}))

Figure B-11-6 Fitted Surveillance Results for Weld Heat 5P6756 B-173

EPRI PROPRIETARY LICENSED MATERIAL ISP Weld Heat Evaluations References B-11-1. BWRVIP-87NP, Revision 1: BWR Vessel and Internals Project Testing and Evaluation of BWR Supplemental Surveillance Program Capsules D, G, and H. EPRI, Palo Alto and BWRVIP: 2010. 1021553.

B-11-2. River Bend 183 Degree Surveillance Capsule Report, M.P. Manahan Sr., MPM Report Number MPM-1202971, January 2003.

B-11-3. BWRVIP-111NP, Revision 1: BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance Program Capsules E, F and I. EPRI, Palo Alto, CA: 2010. 1021554.

B-11-4. CVGRAPH, Hyperbolic Tangent Curve Fitting Program, Developed by ATI Consulting, Version 5.0.2, Revision 1, 3/26/02.

B-11-5. Progress Report on Phase 2 of the BWR Owners Group Supplemental Surveillance Program, T.A. Caine, S. Ranganath, and S.J. Stark, GE Nuclear Energy, GE-NE-523-99-0792, January 1992.

B-11-6. Radiation Embrittlement of Reactor Vessel Materials, USNRC Regulatory Guide 1.99, Revision 2, May 1988.

B-11-7. Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels, USNRC Regulatory Guide 1.162, February 1996.

B-11-8. K. Wichman, M. Mitchell, and A. Hiser, USNRC, Generic Letter 92-01 and RPV Integrity Workshop Handouts, NRC/Industry Workshop on RPV Integrity Issues, February 12, 1998.

B-11-9. ASTM E-185, Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, American Society for Testing and Materials, July 1982.

B-11-10. BWR Vessel and Internals Project: BWR Integrated Surveillance Program Plan (BWRVIP-78). EPRI, Palo Alto, CA and BWRVIP: 1999. TR-114228.

B-11-11. Not used.

B-11-12. BWRVIP-169NP: BWR Vessel and Internals Project, Testing and Evaluation of BWR Supplemental Surveillance Program (SSP) Capsules A, B, and C. EPRI, Palo Alto, CA: 2010. 1021556.

B-174

RA-18-0163 Enclosure 5 Structural Integrity Calculation No. 1700147.302, Revision 0, Brunswick Nuclear Plant Unit 1 and 2 Updated P-T Curve Calculation for 54 EFPY

File No.: 1700147.302 Project No.: 1700147 CALCULATION PACKAGE Quality Program: Nuclear Commercial PROJECT NAME:

Brunswick P-T Curves CONTRACT NO.:

03021365 00021 CLIENT: PLANT:

Duke Energy Brunswick Nuclear Plant (BNP)

CALCULATION TITLE:

Brunswick Nuclear Plant Unit 1 and 2 Updated P-T Curve Calculation for 54 EFPY Project Manager Document Affected Preparer(s) & Checker(s)

Revision Description Approval Revision Pages Signatures & Date Signature & Date 0 1 - 43 Initial Issue Responsible Engineer A A-5 B B-30 Stephen Parker Heather Jackson 11/17/2017 11/17/2017 Responsible Verifier Heather Jackson 11/17/2017 Page 1 of 43 F0306-01R2

Table of Contents

1.0 INTRODUCTION

......................................................................................................... 4 2.0 METHODOLOGY ........................................................................................................ 4 3.0 ASSUMPTIONS ......................................................................................................... 10 4.0 DESIGN INPUTS ....................................................................................................... 11 4.1 BNP Unit 1 ...................................................................................................... 12 4.2 BNP Unit 2 ...................................................................................................... 13 5.0 CALCULATIONS ...................................................................................................... 15 5.1 Pressure Test (Curve A) .................................................................................. 15 5.2 Normal Operation - Core Not Critical (Curve B) ........................................... 15 5.3 Normal Operation - Core Critical (Curve C) .................................................. 16 5.3.1 BNP Unit 1 ...................................................................................................... 16 5.3.2 BNP Unit 2 ...................................................................................................... 17

6.0 CONCLUSION

S ......................................................................................................... 17

7.0 REFERENCES

............................................................................................................ 18 APPENDIX A P - T CURVE INPUT LISTING .................................................................. A-1 APPENDIX B SUPPORTING CALCULATIONS .............................................................. B-1 File No.: 1700147.302 Page 2 of 43 Revision: 0 F0306-01R2

List of Tables Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves. ..................... 9 Table 2: BNP Unit 1 Beltline Region, Curve A, for 54 EFPY...................................................... 20 Table 3: BNP Unit 1 Bottom Head Region, Curve A, for 54 EFPY ............................................. 21 Table 4: BNP Unit 1 Non-Beltline Region, Curve A, for 54 EFPY ............................................. 22 Table 5: BNP Unit 1, Beltline Region, Curve B, for 54 EFPY ..................................................... 23 Table 6: BNP Unit 1 Bottom Head Region, Curve B for 54 EFPY .............................................. 24 Table 7: BNP Unit 1 Non-Beltline Region, Curve B, for 54 EFPY ............................................. 25 Table 8: BNP Unit 1 Beltline Region, Curve C, for 54 EFPY ..................................................... 26 Table 9: BNP Unit 1 Bottom Head Region, Curve C for 54 EFPY .............................................. 27 Table 10: BNP Unit 1 Non-Beltline Region, Curve C, for 54 EFPY ........................................... 28 Table 11: BNP Unit 2 Beltline Region, Curve A, for 54 EFPY.................................................... 29 Table 12: BNP Unit 2 Bottom Head Region, Curve A, for 54 EFPY ........................................... 30 Table 13: BNP Unit 2 Non-Beltline Region, Curve A, for 54 EFPY ........................................... 31 Table 14: BNP Unit 2, Beltline Region, Curve B, for 54 EFPY ................................................... 32 Table 15: BNP Unit 2 Bottom Head Region, Curve B for 54 EFPY ............................................ 33 Table 16: BNP Unit 2 Non-Beltline Region, Curve B, for 54 EFPY............................................ 34 Table 17: BNP Unit 2 Beltline Region, Curve C, for 54 EFPY .................................................... 35 Table 18: BNP Unit 2 Bottom Head Region, Curve C for 54 EFPY ............................................ 36 Table 19: BNP Unit 2 Non-Beltline Region, Curve C, for 54 EFPY............................................ 37 List of Figures Figure 1: BNP Unit 1 P-T Curve A (Hydrostatic Pressure and Leak Test), 54 EFPY.................. 38 Figure 2: BNP Unit 1 P-T Curve B (Normal Operation - Core Not Critical), 54 EFPY .............. 39 Figure 3: BNP Unit 1 P-T Curve C (Normal Operation - Core Critical), 54 EFPY ..................... 40 Figure 4: BNP Unit 2 P-T Curve A (Hydrostatic Pressure and Leak Test), 54 EFPY.................. 41 Figure 5: BNP Unit 2 P-T Curve B (Normal Operation - Core Not Critical), 54 EFPY .............. 42 Figure 6: BNP Unit 2 P-T Curve C (Normal Operation - Core Critical), 54 EFPY ..................... 43 File No.: 1700147.302 Page 3 of 43 Revision: 0 F0306-01R2

1.0 INTRODUCTION

This calculation updates the pressure-temperature (P-T) limit curves for the beltline, bottom head, and non-beltline regions of the Brunswick Nuclear Plant (BNP) Unit 1 and Unit 2 reactor pressure vessels (RPV). The P-T curves are developed for 54 effective full power years (EFPY) of operation. The P-T curves are prepared using the methods documented in the Boiling Water Reactor Owners Group (BWROG) Licensing Topical Report (LTR), Pressure Temperature Limits Report Methodology for Boiling Water Reactors [1]. This LTR satisfies the requirements of 10CFR50 Appendix G [2] and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Nonmandatory Appendix G [3].

2.0 METHODOLOGY A full set of P-T curves, applicable to the following plant conditions, are prepared:

1. Pressure Test (Curve A),

2. Normal Operation - Core Not Critical (Curve B), and

3. Normal Operation - Core Critical (Curve C).

For each plant condition above, separate curves are provided for each of the following three regions of the RPV as well as a composite curve for the entire RPV:

1. The beltline region,

2. The bottom head region,

3. The non-beltline region, including the top head flange,

4. Composite curve (bounding curve for all regions)

In some cases, a region may contain more than one component which is considered for development of the associated P-T curve. For BNP Units 1 and 2, the curve for each vessel region identified above is composed from the bounding P-T limits determined for the following components:

1. Beltline:

a. Beltline shell

b. Instrument nozzle, N16

2. Non-beltline

a. Feedwater (FW) nozzle

b. 10CFR50 Appendix G limits [2]

3. Bottom Head:

a. Bottom head penetrations Consequently, separate curves are prepared for each component considered for each region, then a bounding curve is drawn from the individual curves. Complete sets of P-T curves, as identified above, are provided for 54 EFPY of operation for the limiting Service Level A/B (Normal/Upset) thermal transient.

File No.: 1700147.302 Page 4 of 43 Revision: 0 F0306-01R2

The methodology for calculating P-T curves, described below, is taken from Reference [1] unless specified otherwise.

The P-T curves are calculated by means of an iterative procedure, in which the following steps are performed:

Step 1: A fluid temperature, T, is assumed. The P-T curves are calculated considering a postulated flaw with a 6:1 aspect ratio that extends 1/4 of the way through the vessel wall. The temperature at the postulated flaw tip is conservatively assumed equal to the coolant temperature.

Step 2: The static fracture toughness, KIc, is computed using the following equation from [3]:

K Ic = 33.2 + 20.734 exp[0.02(T ART )] (1)

Where: KIc = the lower bound static initiation critical fracture toughness (ksiin).

T = the metal temperature at the tip of the postulated 1/4 through-wall flaw (°F).

ART = the Adjusted Reference Temperature (ART) for the limiting material in the RPV region under consideration (°F).

Step 3: The allowable stress intensity factor due to pressure, KIp, is calculated as:

K Ic K It K Ip = (2)

SF Where: KIp = the allowable stress intensity factor due to membrane (pressure) stress (ksiin).

KIc = the lower bound static fracture toughness calculated in Eq. (1)

(ksiin).

KIt = the thermal stress intensity factor (ksiin) from through wall thermal gradients.

SF = the ASME Code recommended safety factor, based on the reactor condition. For hydrostatic and leak test conditions (i.e., P-T Curve A), SF = 1.5. For normal operation, both core non-critical and core critical (i.e., P-T Curves B and C), SF = 2.0.

When calculating values for Curve A, the thermal stress intensity factor is neglected (KIt = 0),

since the hydrostatic leak test is performed at or near isothermal conditions (typically, the rate of temperature change is 25°F/hr or less).

File No.: 1700147.302 Page 5 of 43 Revision: 0 F0306-01R2

For Curve B and Curve C calculations, KIt is computed in different ways based on the evaluated region. For the RPV shell in the beltline region and the bottom head shell, the use of Paragraph G-2214.3 of the ASME Code [3] to compute KIt for the cool-down rate corresponding to the limiting transient would be excessively conservative. The limiting Service Level A/B transient is the safety relief valve (SRV) blowdown transient, which has a maximum cool-down rate during the transient of 954°F/hr, although for the majority of the transient, the cool-down rate is 100°F/hr. P-T curves are developed for normal operating conditions, and Technical Specifications limit operation to 100°F/hr. Additionally, for some BWRs, the SRV blowdown event is explicitly classified in the RPV thermal cycles as an Emergency condition. However, this was not the case for the SRV blowdown event at Brunswick. For conservatism, the SRV blowdown event was selected for evaluation as the limiting Service Level A/B transient. In this case, the thermal stress intensity factors for the limiting transient through the RPV shell plate [5] are obtained from the stress distribution output of a plant specific finite element analysis (FEA) and explained in Section 5.1, using the linear elastic fracture mechanics (LEFM) solution incorporated into ASME XI, Nonmandatory Appendix G, Paragraph G-2214.3 (b) [3]. A polynomial curve-fit is determined for the through-wall stress distribution due to the limiting transient at the bounding time point (i.e. the time point corresponding to the largest KIt) using the following LEFM solution for KIt [1]:

K It = a [1.0359C0t + 0.6322C1t + 0.4753C 2t + 0.3855C3t ]

(3)

Where, a = 1/4 through-wall postulated flaw depth, a = 1/4 t (in).

t = thickness of the RPV shell or bottom head shell (in).

C0t, C1t, = thermal stress polynomial coefficients, obtained C2t, C3t from a curve fit of the extracted stresses from a transient FEA

[5].

The thermal stress polynomial coefficients are based on the assumed polynomial form of (x ) = C0 + C1 ( x / a) + C 2 ( x / a) 2 + C3 ( x / a) 3 . In this equation, x represents the radial distance in inches from the inside surface to any point on the crack face. These calculations are performed in Reference [5] and the value of KIt for the beltline shell region is obtained directly from Table 4 of that reference.

For the bottom head region, it is noted that the bottom head plates differ in thickness from the beltline shell plates. Further, the bottom head center plates differ in thickness from the side plates. Dimensions are summarized in Section 4.0. The thermal stress intensity factor for the BNP bottom head is scaled to account for the difference in thickness and is based on the KIt obtained using Eq. (3) for the beltline shell. The scaling factor is determined using the relationship between stress intensity factor and wall thickness given in Paragraph G-2214.3 of the ASME Section XI, Nonmandatory Appendix G [3]. The bottom head thickness found to File No.: 1700147.302 Page 6 of 43 Revision: 0 F0306-01R2

produce the most limiting P-T curve is used for each curve, as discussed in Sections 5.1, 5.2, and 5.3.

For the FW and instrument nozzles, KIt is obtained from the stress distribution output of plant-specific FEA with computation of KIt as described in References [4] and [5]. A polynomial curve-fit is determined for the through-wall stress distribution at the bounding time point. The linear elastic fracture mechanics (LEFM) solution for KIt is obtained from Reference [1]:

2a a2 4a 3 K It = a 0.723C0t + 0.551 C1t + 0.462 C 2t + 0.408 C3t 2 3 (4)

Where: a = 1/4 through-wall postulated flaw depth, a = 1/4 t (in).

t = thickness of the cross-section through the nozzle at the limiting path near the inner blend radius (in).

C0t,C1t, = thermal stress polynomial coefficients, obtained from a curve-C2t,C3t fit of the extracted stresses from a transient FEA [4, 5].

The thermal stress polynomial coefficients are based on the assumed polynomial form of (x ) = C0 + C1 x + C2 x 2 + C3 x3 . In this equation, x represents the radial distance in inches from the inside surface to any point on the crack face.

These calculations are performed in Reference [4] for the FW nozzle and [5] for the instrument nozzle, and the values of KIt are obtained directly from Table 4 of these references.

Step 4: The allowable internal pressure of the RPV is calculated differently for each evaluation region.

For the beltline region, with the exception of nozzles, the allowable pressure is determined as follows:

K Ip t Pallow = (5)

M m Ri Where: Pallow = the allowable RPV internal pressure (psig).

KIp = the allowable stress intensity factor due to membrane (pressure) stress, as defined in Eq. (2) (ksiin).

t = the RPV wall thickness (in).

Mm = the membrane correction factor for an inside surface axial flaw:

Mm = 1.85 for t < 2 Mm = 0.926 t for 2 t 3.464 Mm = 3.21 for t > 3.464.

Ri = the inner radius of the RPV, per region (in).

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For the bottom head region, the allowable pressure is calculated with the following equation:

2 K Ip t Pallow = (6)

SCF M m Ri Where: SCF = conservative stress concentration factor to account for bottom head penetration discontinuities; SCF = 3.0 per Reference [1].

Pallow, KIp, t, Mm and Ri are defined in Eq. (5).

After comparison of the pressure effects due to different bottom head shell thicknesses in the center plate and side plates, the thinner plates are found to generate a lower and, therefore, more restrictive allowable pressure. However, the effect of bottom head thickness on KIt must also be considered (Step 3). The bottom head thickness found to produce the most limiting P-T curve is used for each curve, as discussed in Sections 5.1, 5.2, and 5.3.

For the FW and instrument nozzles, the allowable pressure is determined from a ratio of the allowable and applied stress intensity factors. The applied factor can be determined from a FEA that determines the stresses due to the internal pressure on the nozzle and RPV. The methodology for this approach is as follows:

K Ip Pref Pallow = (7)

K Ip app Where: Pref = RPV internal pressure at which the FEA stress coefficients (Eq.

(8)) are determined (psi).

KIp-app = the applied pressure stress intensity factor (ksiin).

Pallow and KIp are defined as in Eq. (5).

The applied pressure stress intensity factors for the FW and instrument nozzles is determined using a polynomial curve-fit approximation for the through-wall pressure stress distribution from a plant-specific FEA with computation of KIp-app as described in References [4] and [5], and the LEFM solution given in Eq. (8) [1]:

2a a2 4a 3 K Ip app = a 0.723C0t + 0.551 C1t + 0.462 C 2t + 0.408 C3t (8) 2 3 Where: a = 1/4 through-wall postulated flaw depth, a = 1/4 t (in).

t = thickness of the cross-section through the limiting nozzle inner blend radius corner (in).

C0p,C1p, = pressure stress polynomial coefficients, obtained from a curve-C2p,C3p fit of the extracted stresses from a FEA [4, 5].

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These calculations are performed in References [4] and [5] and the values of KIp-app are obtained directly from Table 4 of these references.

Step 5: Steps 1 through 4 are repeated in order to generate a series of P-T points; the fluid temperature is incremented with each repetition. Calculations proceed in this iterative manner to an upper limit pressure of 1,300 psig. This value bounds expected pressures.

Step 6: Table 1 summarizes the minimum temperature requirements contained in 10CFR50, Appendix G [2, Table 1], which are applicable to the material highly stressed by the main closure flange bolt preload (non-beltline curve). Additional minimum temperature requirements for bolt-up are included as shown in Table 1 below.

Table 1: Summary of Minimum Temperature Requirements for P-T Limit Curves.

Pressure Curve Minimum Metal Temperature P-T Limits Range Maximum of: ASME Appendix G [3]

RTNDT,max, requirements P < 20% Ph

60°F [1],

A

TSDM ASME Appendix G [3]

P > 20% Ph RTNDT,max + 90°F requirements Maximum of: ASME Appendix G [3]

RTNDT,max, requirements P < 20% Ph

60°F [1],

B

TSDM ASME Appendix G [3]

P > 20% Ph RTNDT,max + 120°F requirements Maximum of: ASME Appendix G [3]

RTNDT,max + 60°F, requirements + 40°F P < 20% Ph

60°F [1],

C

TSDM Maximum of: ASME Appendix G [3]

P > 20% Ph

RTNDT,max + 160°F, requirements + 40°F

TISHT Where: Ph is the pre-service hydrotest pressure, 1563 psig [6]

RTNDT,max is the maximum RTNDT of the vessel materials highly stressed by the bolt preload.

TSDM is the temperature used in the shutdown margin evaluation TISHT is the temperature at which the full in-service hydrotest pressure (1100 psig) [8] is allowed per Curve A Note that the minimum bolt-up temperature of 60°F, is used here, consistent with the position given in Reference [1]. Further, some utilities specifically request that the minimum moderator File No.: 1700147.302 Page 9 of 43 Revision: 0 F0306-01R2

temperature used in the plant shutdown margin evaluation be applied as a minimum bolt-up temperature requirement; therefore, it is also included in Table 1 above. An additional 60°F margin above that recommended in 10CFR50, Appendix G [2, Table 1], has been commonly applied in the BWR industry. For the BNP closure flange material, the minimum temperature would be 76°F for Unit 1 (i.e. RTNDT,max of 16°F + 60°F) [10, Table 7-1; 11, 12] and 70°F for Unit 2 (i.e. RTNDT,max of 10°F + 60°F) [19, Table 6-1]. For Curves A and B, this 60°F margin is only a recommendation. Consequently, for Curves A and B, the minimum temperature for Unit 1 was set to 70°F for consistency with Unit 2 and with past work. These values are consistent with the minimum temperature limits and minimum bolt-up temperature in the current docketed P-T curves [6] (approved by the NRC in Reference [7]). These values also bound the lowest service temperatures (LST) for ferritic non-RPV components of the reactor coolant pressure boundary (RCPB), per the component design specifications [23], thereby addressing the NRC condition in the final Safety Evaluation for Reference [1],

Step 7: Uncertainty in the RPV pressure and metal temperature measurements is incorporated by adjusting the P-T curve pressure and temperature using the following equations:

TP T = T + U T (9)

PP T = Pallow PH U P (10)

Where: TP-T = The allowable coolant (metal) temperature (°F).

UT = The coolant temperature instrument uncertainty (°F).

PP-T = The allowable reactor pressure (psig).

PH = The pressure head to account for the water in the RPV (psig).

Can be calculated from the following expression: PH = h .

= Water density at ambient temperature (lbm/in3).

h = Elevation of full height water level in RPV (in).

UP = The pressure instrument uncertainty (psig).

Steps 1 through 7, above, are implemented for all components, in all regions, for each heat-up/cool-down rate, and at all EFPY.

3.0 ASSUMPTIONS The 10CFR50 Appendix G [2] and ASME Code [3] requirements and methods are considered to be supported in their respective technical basis documentation. Therefore, the assumptions inherent in the ASME B&PV Code methods utilized for this evaluation are not specifically identified and justified in this calculation. Only those assumptions specific to this calculation are identified and justified here. The following assumptions are used in preparation of the BNP P-T curves:

1. The full-vessel height is used in the calculation of the static head contributed by the coolant in the RPV.

This assumption is conservative in that the static head at the non-beltline regions is slightly lower than that of the bottom head curve; however, the difference in static head is small. Therefore, the File No.: 1700147.302 Page 10 of 43 Revision: 0 F0306-01R2

added complexity in considering different static head values for each region of the vessel is not considered beneficial.

2. The FW nozzle is the bounding non-beltline component of the RPV.

This assumption is made because:

a. The geometric discontinuity caused by the nozzle penetration in the RPV shell causes a stress concentration which results in larger pressure induced stresses than would be calculated in the shell regions of the RPV.

b. The FW nozzle experiences more severe thermal transients than most of the other nozzles because of the feedwater injection temperature, which causes larger thermal stresses than are experienced in the shell region of the RPV.

c. Although some other nozzles can experience thermal transients, which would cause thermal stresses larger than those calculated for the shell regions of the RPV, and some nozzles are larger diameter than the FW nozzle, which could result in a slightly larger KIp, the combined stresses from the applied thermal and pressure loads are considered to bound all other non-beltline discontinuities [1].

3. Application of a SCF = 3.0 to the membrane pressure stress in the bottom head bounds the effect of the bottom head penetrations on the stress field in this region of the vessel.

Bottom head penetrations will create geometric discontinuities into the bottom head hemisphere resulting in high localized stresses. This effect must be considered in calculating the stress intensity factor from internal pressure. Rather than performing a plant-specific analysis, SI applies a conservative SCF for a circular hole in a flat plate subjected to a uniaxial load to the membrane stress in the shell caused by the internal pressure. The assumption of SCF = 3.0 is conservative because:

a. It applies a peak SCF to the membrane stress which essentially intensifies the stress through the entire shell thickness and along the entire crack face of the postulated flaw rather than intensifying the stress local to the penetration and considering the stress attenuation away from the penetration,

b. Review of SCFs for circular holes in plates subjected to an equi-bi-axial stress state as well as SCFs for arrays of circular holes in shells, shows that the SCF is likely closer to 2-2.5 rather than 3.0.

Consequently, the method utilized by SI is expedient, as intended, and conservatively bounds the expected effect of bottom head penetrations because a bounding SCF is used and applied as a membrane stress correction factor.

4.0 DESIGN INPUTS The design inputs, also included in Appendix A, used to develop the BNP Unit 1 and Unit 2 P-T curves are discussed below:

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4.1 BNP Unit 1

1. Limiting RTNDT and ART:

Non-beltline RTNDT: 60°F [10, Table 7-1]

(Bounding RTNDT for non-beltline region, excluding bottom head)

Non-beltline RTNDT: 16°F [10, Table 7-1; 11, 12]

(Bounding RTNDT for materials highly stressed by bolt preload)

Bottom Head RTNDT: 10°F [10, Table 7-1]

Beltline ART: 129.1°F [9, Table 1]

(The limiting ART value of all beltline materials including plates and welds, and is used for P-T limit curve calculations for each EFPY)

Instrument (N16) Nozzle ART: 131.0°F [9, Table 1]

(ART based on bounding fluence at location of N16 nozzles and chemistry of N16 nozzle forgings)

2. Minimum Bolt-Up Temperature:

Shutdown Margin Temperature: 70°F [8]

Bolt-Up Temperature: 70°F (Step 6 of Section 2.0 in the current document)

3. RPV Dimensions:

Full vessel height: 829.75 inches [13]

(Used to calculate maximum water head during pressure test and conservatively applied for normal operation as well. For the BNP1 vessel, this corresponds to a pressure adjustment of 30.0 psig.)

RPV inside radius: 110.59375 inches [14]

RPV shell thickness: 5.496 inches [15] (minimum)

Bottom head inside radius: 110.59375 inches [14]

Bottom head shell thickness: 5.40 inches [15] (bottom head side plates, minimum thickness) 6.792 inches [15] (bottom head center plates, maximum thickness)

4. Maximum Heat-Up/Cool-Down Rate:

Shutdown: 100°F/hr [16]

SRV Blowdown: 954°F/hr [16, 17]

5. Stress Intensity Factors:

Vessel Shell:

SRV Blowdown Transient: 32.46 ksi-in0.5 [5, Table 4] (based on path length of 5.6875 inch)

Bottom Head Shell:

6.792 inch thickness:

Scaling Factor: 1.56 (Calculated as (6.792/5.6875)2.5)

SRV Blowdown: 50.59 ksi-in0.5 (Calculated as discussed in Step 3 of Section 2.0)

FW Nozzle [4, Table 4]:

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1 ksi Pressure: 73.74 ksi-in0.5 Shutdown (100°F/hr): 66.83 ksi-in0.5 SRV Blowdown Transient: 58.44 ksi-in0.5 Instrument (N16) Nozzle [5, Table 4]:

1 ksi Pressure: 55.42 ksi-in0.5 Shutdown (100°F/hr): 3.75 ksi-in0.5 SRV Blowdown Transient: 15.13 ksi-in0.5

6. Design Pressure: 1250 psig [18, Table 1-3, C]

7. Hydro-test pressure:

Pre-Service: 1563 psig [18, Tables 5-11, 5.3.3-2] (i.e. 1.25*Design pressure)

In-Service: 1100 psig [8]

(conservatively assumed for P-T curve development; test pressure may range from 1030-1070 psig)

8. Instrument uncertainties [20, Section 3]:

Pressure: 15 psig Temperature: 10°F

9. Applicable ASME XI Code Year [3]: 2007 Edition through the 2008 Addenda [8]

4.2 BNP Unit 2

1. Limiting RTNDT and ART:

Non-beltline RTNDT: 60°F [19, Table 6-1]

(Bounding RTNDT for non-beltline region, excluding bottom head.)

Non-beltline RTNDT: 10°F [19, Table 6-1]

(Bounding RTNDT for materials highly stressed by bolt preload)

Bottom Head RTNDT: 40°F [19, Table 6-1]

Beltline ART: 103.4°F [9, Table 2]

(The limiting ART value of all beltline materials including plates and welds, and is used for P-T limit curve calculations for each EFPY)

Instrument (N16) Nozzle ART: 123.4°F [9, Table 2]

(ART based on bounding fluence at location of N16 nozzles and chemistry of N16 nozzle forgings)

2. Minimum Bolt-Up Temperature:

Shutdown Margin Temperature: 70°F [8]

Bolt-Up Temperature: 70°F (Step 6 of Section 2.0 in the current document)

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3. RPV Dimensions:

Full vessel height: 829.75 inches [13]

(Used to calculate maximum water head during pressure test and conservatively applied for normal operation as well. For the BNP2 vessel, this corresponds to a pressure adjustment of 30.0 psig.)

RPV inside radius: 110.3125 inches [21]

RPV shell thickness: 5.466 inches [22] (minimum)

Bottom head inside radius: 110.3125 inches [21]

Bottom head shell thickness: 5.42 inches [22] (bottom head side plates) 6.870 inches [22] (bottom head center plates)

4. Maximum Heat-Up/Cool-Down Rate:

Shutdown: 100°F/hr [16]

SRV Blowdown: 954°F/hr [16, 17]

5. Stress Intensity Factors:

Vessel Shell:

SRV Blowdown Transient: 32.46 ksi-in0.5 [5, Table 4] (based on path length of 5.6875 inch)

Bottom Head Shell:

6.870 inch thickness:

Scaling Factor: 1. 60 (Calculated as (6.870/5.6875)2.5)

SRV Blowdown: 52.05 ksi-in0.5 (Calculated as discussed in Step 3 of Section 2.0)

FW Nozzle [4, Table 4]:

1 ksi Pressure: 73.74 ksi-in0.5 Shutdown (100°F/hr): 66.83 ksi-in0.5 SRV Blowdown Transient: 58.44 ksi-in0.5 Instrument (N16) Nozzle [5, Table 4]:

1 ksi Pressure: 55.42 ksi-in0.5 Shutdown (100°F/hr): 3.75 ksi-in0.5 SRV Blowdown Transient: 15.13 ksi-in0.5

6. Design Pressure: 1250 psig [18, Table 1-3, C]

7. Hydro-test pressure:

Pre-Service: 1563 psig [18, Tables 5-11, 5.3.3-2] (i.e. 1.25*Design pressure)

In-Service: 1100 psig [8]

(conservatively assumed for P-T curve development; test pressure may range from 1030-1070 psig)

8. Instrument uncertainties [20, Section 3]:

Pressure: 15 psig File No.: 1700147.302 Page 14 of 43 Revision: 0 F0306-01R2

Temperature: 10°F

9. Applicable ASME XI Code Year [3]: 2007 Edition through the 2008 Addenda [8]

5.0 CALCULATIONS The P-T curves in this calculation were developed using an Excel spreadsheet, which is independently verified for use on a project-specific basis in accordance with SIs Nuclear QA program. P-T limits are calculated from 0 to 1300 psig. Supporting calculations for all curves are included in Appendix B.

5.1 Pressure Test (Curve A)

The minimum bolt-up temperature of 70°F minus instrument uncertainty (10°F) is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (KIc) is calculated for all regions using Eq. (1). The resulting value of KIc, along with a safety factor of 1.5 is used in Eq. (2) to calculate the pressure stress intensity factor (KIp). The allowable RPV pressure is calculated for the beltline, bottom head and non-beltline regions using Eq. (5, 6, and 7), as appropriate.

For the bottom head, calculation of the allowable RPV internal pressure using both the minimum thickness and maximum thickness for each unit revealed that the thinner side plates are more limiting with respect to the resulting P-T limits for Curve A. For the non-beltline region (feedwater nozzle /

upper vessel), the additional constraints specified in Step 6 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtained from Eq. (9 and 10), respectively.

Since the thermal stress intensity factor is taken as zero for Curve A, the cool-down rate does not affect the results for Curve A.

Values for the composite beltline region curves for 54 EFPY are listed in Table 2 for BNP Unit 1 and Table 11 for BNP Unit 2. Additionally, more detailed data for the composite beltline are provided in Appendix B. Data for the composite bottom head region curve for all EFPY is listed in Table 3 for BNP Unit 1 and Table 12 for BNP Unit 2. Data for the composite non-beltline (feedwater nozzle / upper vessel) region curve, including the 10CFR50 Appendix G [2] limits, for all EFPY is listed in Table 4 for BNP Unit 1 and Table 13 for BNP Unit 2. The data for each region is plotted, and the resulting composite Curve A for 54 EFPY are provided in Figure 1 for BNP Unit 1 and Figure 4 for BNP Unit 2.

Additional data and curves for each region are included in Appendix B.

5.2 Normal Operation - Core Not Critical (Curve B)

The minimum bolt-up temperature of 70°F minus coolant temperature instrument uncertainty (10°F) is applied to all regions as the initial temperature in the iterative calculation process. The static fracture toughness (KIc) is calculated for all regions using Eq. (1). The thermal stress intensity factor (KIt) is calculated for the beltline plate region using Eq. (3) and the output of plant-specific FEA. For the bottom head, considering the effect of thickness on both the allowable RPV internal pressure and KIt, the maximum thickness center plates are more limiting with respect to the resulting P-T limits for Curve B.

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The thermal stress intensity factor for the bottom head region is scaled from the KIt obtained for the RPV shell to account for the increased thickness relative to the beltline region. The scaling factor is determined using the relationship between stress intensity factor and wall thickness given in Paragraph G-2214.3 of ASME Section XI, Nonmandatory Appendix G [3]. The thermal stress intensity factor is calculated for the FW and instrument nozzles using Eq. (4) and the output of plant-specific FEA.

The resulting values of KIc and KIt, along with a safety factor of 2.0, are used in Eq. (2) to calculate the pressure stress intensity factor (KIp). The allowable RPV pressure is calculated for the beltline, bottom head, and non-beltline regions using Eq. (5, 6, and 7), as appropriate. For the non-beltline (FW nozzle /

upper vessel) region, the additional constraints specified in Step 6 of Section 2.0 are applied. Final P-T limits for temperature and pressure are obtained from Eq. (9 and 10), respectively.

The data resulting from each P-T curve calculation is tabulated. Values for the composite beltline region at 54 EFPY are listed in Table 5 for BNP Unit 1 and Table 14 for BNP Unit 2. Data for the bottom head region are listed in Table 6 for BNP Unit 1 and Table 15 for BNP Unit 2. Data for the FW nozzle / upper vessel region are listed in Table 7 for BNP Unit 1 and Table 16 for BNP Unit 2. The data for each region is plotted, and the resulting data for composite Curve B are provided in Figure 2 for BNP Unit 1 and Figure 5 for BNP Unit 2. Additional data and curves for each region are included in Appendix B.

5.3 Normal Operation - Core Critical (Curve C) 5.3.1 BNP Unit 1 The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, with several exceptions. The initial evaluation temperature is calculated as the limiting non-beltline RTNDT that is highly stressed by the bolt preload (in this case, that of the closure flange region: 16°F per Section 3.0) plus 60°F, resulting in a minimum critical temperature of 76°F. When the pressure exceeds 20% of the pre-service system hydrostatic test pressure (20% of 1,563 psig = 313 psig), the P-T limits are specified as 40°F higher than the Curve B values. The minimum temperature above the 20% of the pre-service system hydrostatic test pressure is always greater than the reference temperature (RTNDT) of the closure region plus 160°F, or is taken as the minimum temperature required for the hydrostatic pressure test. As with Curve B, the maximum thickness bottom head center plates are used to establish P-T limits. The final Curve C values are taken as the absolute maximum between the regions of the beltline, the bottom head, and the non-beltline.

The data resulting from each P-T curve calculation is tabulated. Values for the composite beltline region at 54 EFPY are listed in Table 8. Data for the bottom head region are listed in Table 9. Data for the non-beltline (FW nozzle / upper vessel) region are listed in Table 10. The data for each region is plotted, and the resulting data for composite Curve C are provided in Figure 3. Additional data and curves for each region are included in Appendix B.

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5.3.2 BNP Unit 2 The pressure and temperature values for Curve C are calculated in a similar manner as Curve B, with several exceptions. The initial evaluation temperature is calculated as the limiting non-beltline RTNDT that is highly stressed by the bolt preload (in this case, that of the closure flange region: 10°F per Section 3.0) plus 60°F, resulting in a minimum critical temperature of 70°F. When the pressure exceeds 20% of the pre-service system hydrostatic test pressure (20% of 1,563 psig = 313 psig), the P-T limits are specified as 40°F higher than the Curve B values. The minimum temperature above the 20% of the pre-service system hydrostatic test pressure is always greater than the reference temperature (RTNDT) of the closure region plus 160°F, or is taken as the minimum temperature required for the hydrostatic pressure test. As with Curve B, the maximum thickness bottom head center plates are used to establish P-T limits. The final Curve C values are taken as the absolute maximum between the regions of the beltline, the bottom head, and the non-beltline.

The data resulting from each P-T curve calculation is tabulated. Values for the composite beltline region at 54 EFPY are listed in Table 17. Data for the bottom head region are listed in Table 18. Data for the non-beltline (FW nozzle / upper vessel) region are listed in Table 19. The data for each region is plotted, and the resulting data for composite Curve C are provided in Figure 6. Additional data and curves for each region are included in Appendix B.

6.0 CONCLUSION

S P-T curves are developed for BNP Unit 1 and Unit 2 using the methodology, assumptions, and design inputs defined in Sections 2.0, 3.0, and 4.0, respectively. P-T curves are developed for the beltline, bottom head, and non-beltline regions, considering limiting thermal transients at 54 EFPY, for the following plant conditions: Pressure Test (Curve A), Normal Operation - Core Not Critical (Curve B), and Normal Operation - Core Critical (Curve C). Tabulated pressure and temperature values are provided for all regions and EFPYs for BNP Unit 1 in Table 2 through Table 10 and for BNP Unit 2 in Table 11 through Table 19. The accompanying P-T curve plots are provided for BNP Unit 1 in Figure 1 through Figure 3 and for BNP Unit 2 in Figure 4 through Figure 6.

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7.0 REFERENCES

1. Licensing Topical Report (LTR) BWROG-TP-11-022-A (SIR-05-044), Revision 1, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors, August 2013, ADAMS Accession No. ML13277A557.

2. U. S. Code of Federal Regulations, Title 10, Energy, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix G, Fracture Toughness Requirements, (60 FR 65474, Dec.

19, 1995; 73 FR 5723, Jan. 2008; 78 FR 34248, Jun. 7, 2013; 78 FR 75450, Dec. 12, 2013).

3. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, Nonmandatory Appendix G, Fracture Toughness Criteria for Protection Against Failure, 2007 Edition including the 2008 Addenda.

4. SI Calculation No. 1700147.301, Revision 0, Feedwater Nozzle Fracture Mechanics Evaluation for Pressure-Temperature Limit Curve Development, November 17, 2017.

5. SI Calculation No. 1501581.303, Revision 0, Water Level Instrument Nozzle and Vessel Fracture Mechanics Evaluation for Pressure-Temperature Limit Curve Development, November 17, 2017.

6. Attachment 2 to Carolina Power & Light Letter No. BSEP 02-0121, dated June 26, 2002, SI Calculation No. CPL-54Q-303, Revision 1, Development of Updated P-T Curves For 32 EFPY, May 13, 2002 (ADAMS Accession No. ML021890061 and ML021890087).

7. U.S. NRC License Amendments and Safety Evaluation Report, Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendment Re: Pressure-Temperature Limit Curves (TAC Nos.

MB5579 and MB5580), dated June 18, 2003 (ADAMS Accession No. ML031690683).

8. SI Design Input Request, 1700147.201, Revision 0, May 9, 2017.

9. SI Calculation No. 1501581.301, Revision 0, Brunswick Nuclear Plant Unit 1 and 2 RPV Beltline ART Evaluation, November 17, 2017.

10. Structural Integrity Report No SIR-95-015, Revision 0, Brunswick Steam Electric Plant Unit 1 Reactor Pressure Vessel Material Evaluation and Estimation of Reference Temperatures of Use in Flaw Evaluation, March 21, 1995, SI File No. CPL-35Q-401.

11. SI Calculation No. CPL-42Q-302, Revision 1, Brunswick Units 1 and 2 Hydro Test P-T Curve Development, August 22, 1996.

12. Padish Co. Metallurgical Department Material Analysis Report, Part Number 68- 2471/73M2, 6 69, 2 pages, SI File No. CPL-42Q-214.

13. Chicago Bridge & Iron Company Drawing, Contract No. 68-2471/72, DWG No. 1, Revision 8, General Plan - Nozzles 18-4 ID x 69-1-3/4 Ins Heads Nuclear Reactor Vessel - Gen. Electric Co.

for Carolina Power Co. at Southport, North Carolina, October 20, 1971, SI File No. 1501581.201.

14. Carolina Power & Light Company Drawing No. 1-FP-85150, Revision A, Sheet 14, Main Vessel As-Built, March, 23, 1995, SI File No. CPL-35Q-259.

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15. Carolina Power & Light Company Drawing No. 1-FP-85150, Revision A, Sheet 12, Head and Shell Measurements, March 23, 1995, SI File No. CPL-35Q-264.

16. GE Drawing No. 729E762, Sheet 1, Revision 0, Reactor Thermal Cycles, SI File No.

1000723.208.

17. GE Certified Design Specification 25A5062, Revision 2, Reactor Vessel - Power Uprate, SI File No. 1700487.209.

18. Brunswick Updated Final Safety Analysis Report, Revision 24, Chapters 1 and 5, SI File No.

1700147.201.

19. Structural Integrity Report No SIR-95-130, Revision 1, Brunswick Steam Electric Plant Unit 2 Reactor Pressure Vessel Material Evaluation and Estimation of Reference Temperatures of Use in Flaw Evaluation, April 4, 1996, SI File No. CPL-35Q-407.

20. SI Calculation No. CPL-54Q-303, Revision 1, Development of Updated P-T Curves For 32 EFPY, May 13, 2002.

21. Carolina Power & Light Company Drawing No. 2-FP-85150, Revision A, Sheet 14, Main Vessel As-Built, March 23, 1995, SI File No. CPL-35Q-259.

22. Carolina Power & Light Company Drawing No. 2-FP-85150, Revision A, Sheet 12, Head and Shell Measurements, March 23, 1995, SI File No. CPL-35Q-264.

23. Piping Design Specifications:

a. United Engineers & Constructors Inc. Specification No. 9527-01-248-3, Specification for Reactor Coolant Pressure Boundary Piping for Carolina Power & Light Company, Brunswick Steam Electric Plant - Units 1 and 2, dated December 2, 1974. SI File No. 1700147.201.

b. GE Data Sheet No. 22A1295AJ, Design Requirements for Pressure Integrity of Piping and Equipment Pressure Parts - Data Sheet, Rev. 0. SI File No. 1700147.201.

c. GE System Design Specification No. 22A1295, Pressure Integrity of Piping and Equipment Pressure Parts, Rev. 4. SI File No. CPL-40Q-205.

File No.: 1700147.302 Page 19 of 43 Revision: 0 F0306-01R2

Table 2: BNP Unit 1 Beltline Region, Curve A, for 54 EFPY Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 414.7 100.2 464.6 118.8 514.6 132.4 564.5 143.1 614.4 151.9 664.3 159.3 714.3 165.8 764.2 171.6 814.1 176.7 864.0 181.4 914.0 185.7 963.9 189.6 1013.8 193.3 1063.7 196.7 1113.7 199.8 1163.6 202.8 1213.5 205.7 1263.4 208.3 1313.4 File No.: 1700147.302 Page 20 of 43 Revision: 0 F0306-01R2

Table 3: BNP Unit 1 Bottom Head Region, Curve A, for 54 EFPY Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 858.3 74.0 905.2 77.6 952.2 81.1 999.2 84.3 1046.2 87.3 1093.2 90.1 1140.2 92.8 1187.1 95.4 1234.1 97.8 1281.1 100.1 1328.1 File No.: 1700147.302 Page 21 of 43 Revision: 0 F0306-01R2

Table 4: BNP Unit 1 Non-Beltline Region, Curve A, for 54 EFPY Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 312.6 106.0 312.6 106.0 640.3 111.9 688.9 117.2 737.4 122.0 786.0 126.4 834.6 130.4 883.1 134.2 931.7 137.6 980.2 140.9 1028.8 143.9 1077.4 146.8 1125.9 149.5 1174.5 152.1 1223.1 154.5 1271.6 156.9 1320.2 File No.: 1700147.302 Page 22 of 43 Revision: 0 F0306-01R2

Table 5: BNP Unit 1, Beltline Region, Curve B, for 54 EFPY Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 23.1 99.7 71.5 118.3 120.0 131.8 168.4 142.4 216.9 151.1 265.3 158.6 313.7 165.0 362.2 170.8 410.6 175.9 459.1 180.6 507.5 184.8 556.0 188.8 604.4 193.5 652.3 197.8 700.3 201.7 748.2 205.4 796.1 208.8 844.0 212.0 892.0 215.0 939.9 217.8 987.8 220.5 1035.8 223.1 1083.7 225.5 1131.6 227.8 1179.6 230.0 1227.5 232.1 1275.4 234.2 1323.3 File No.: 1700147.302 Page 23 of 43 Revision: 0 F0306-01R2

Table 6: BNP Unit 1 Bottom Head Region, Curve B for 54 EFPY Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 285.6 74.9 334.7 79.3 383.9 83.4 433.0 87.2 482.1 90.7 531.3 94.0 580.4 97.1 629.5 100.0 678.7 102.7 727.8 105.3 776.9 107.8 826.0 110.2 875.2 112.4 924.3 114.6 973.4 116.6 1022.6 118.6 1071.7 120.5 1120.8 122.4 1170.0 124.1 1219.1 125.8 1268.2 127.5 1317.3 File No.: 1700147.302 Page 24 of 43 Revision: 0 F0306-01R2

Table 7: BNP Unit 1 Non-Beltline Region, Curve B, for 54 EFPY Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 103.2 0.0 110.4 42.2 116.7 84.4 122.2 126.6 127.3 168.9 131.8 211.1 136.0 253.3 138.7 282.9 141.3 312.6 141.3 312.6 198.5 1563.0 File No.: 1700147.302 Page 25 of 43 Revision: 0 F0306-01R2

Table 8: BNP Unit 1 Beltline Region, Curve C, for 54 EFPY Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 85.5 0.0 126.6 46.5 148.8 93.0 164.1 139.5 175.9 186.0 185.4 232.5 193.3 279.0 200.2 325.4 206.2 371.9 211.6 418.4 216.5 464.9 220.9 511.4 225.0 557.9 228.8 604.4 233.5 652.3 237.8 700.3 241.7 748.2 245.4 796.1 248.8 844.0 252.0 892.0 255.0 939.9 257.8 987.8 260.5 1035.8 263.1 1083.7 265.5 1131.6 267.8 1179.6 270.0 1227.5 272.1 1275.4 274.2 1323.3 File No.: 1700147.302 Page 26 of 43 Revision: 0 F0306-01R2

Table 9: BNP Unit 1 Bottom Head Region, Curve C for 54 EFPY Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 76.0 0.0 76.0 49.7 85.2 98.5 92.9 147.4 99.6 196.2 105.6 245.0 110.8 293.8 115.6 342.6 120.0 391.4 124.0 440.3 127.7 489.1 131.2 537.9 134.4 586.7 137.5 635.5 140.3 684.3 143.0 733.1 145.6 782.0 148.0 830.8 150.4 879.6 152.6 928.4 154.7 977.2 156.8 1026.0 158.7 1074.8 160.6 1123.7 162.5 1172.5 164.2 1221.3 165.9 1270.1 167.5 1318.9 File No.: 1700147.302 Page 27 of 43 Revision: 0 F0306-01R2

Table 10: BNP Unit 1 Non-Beltline Region, Curve C, for 54 EFPY Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 143.2 0.0 150.8 44.7 157.3 89.3 163.1 134.0 168.4 178.6 173.1 223.3 177.4 267.9 181.3 312.6 195.8 312.6 195.8 509.0 198.8 556.9 201.6 604.8 204.2 652.7 206.8 700.6 209.2 748.5 211.5 796.4 213.6 844.4 215.7 892.3 217.8 940.2 219.7 988.1 221.6 1036.0 223.4 1083.9 225.1 1131.8 226.8 1179.7 228.4 1227.6 230.0 1275.5 231.5 1323.5 File No.: 1700147.302 Page 28 of 43 Revision: 0 F0306-01R2

Table 11: BNP Unit 2 Beltline Region, Curve A, for 54 EFPY Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 424.6 96.7 474.1 114.0 523.6 126.8 573.1 137.0 622.6 145.5 672.1 152.7 721.6 159.1 771.1 164.7 820.6 169.7 870.1 174.3 919.6 178.5 969.0 182.4 1018.5 186.0 1068.0 189.3 1117.5 192.5 1167.0 195.4 1216.5 198.2 1266.0 200.8 1315.5 File No.: 1700147.302 Page 29 of 43 Revision: 0 F0306-01R2

Table 12: BNP Unit 2 Bottom Head Region, Curve A, for 54 EFPY Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 604.6 77.1 652.6 83.3 700.5 88.9 748.4 93.9 796.3 98.4 844.2 102.6 892.2 106.4 940.1 110.0 988.0 113.3 1035.9 116.4 1083.8 119.3 1131.7 122.1 1179.7 124.7 1227.6 127.2 1275.5 129.6 1323.4 File No.: 1700147.302 Page 30 of 43 Revision: 0 F0306-01R2

Table 13: BNP Unit 2 Non-Beltline Region, Curve A, for 54 EFPY Curve A - Pressure Test P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 312.6 100.0 312.6 100.0 596.7 106.6 645.1 112.5 693.4 117.7 741.7 122.4 790.0 126.7 838.3 130.7 886.6 134.4 934.9 137.8 983.2 141.1 1031.6 144.1 1079.9 146.9 1128.2 149.6 1176.5 152.2 1224.8 154.6 1273.1 156.9 1321.4 File No.: 1700147.302 Page 31 of 43 Revision: 0 F0306-01R2

Table 14: BNP Unit 2, Beltline Region, Curve B, for 54 EFPY Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 63.1 88.9 108.7 102.5 154.4 113.2 200.0 122.1 245.7 129.6 291.3 142.0 340.2 151.9 389.1 160.2 438.0 167.3 486.9 173.6 535.8 179.1 584.8 184.1 633.7 188.6 682.6 192.8 731.5 196.6 780.4 200.2 829.3 203.5 878.2 206.6 927.1 209.6 976.1 212.3 1025.0 215.0 1073.9 217.5 1122.8 219.8 1171.7 222.1 1220.6 224.3 1269.5 226.3 1318.4 File No.: 1700147.302 Page 32 of 43 Revision: 0 F0306-01R2

Table 15: BNP Unit 2 Bottom Head Region, Curve B for 54 EFPY Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 58.4 78.4 106.9 85.6 155.4 91.9 204.0 97.5 252.5 102.5 301.1 107.1 349.6 111.3 398.1 115.2 446.7 118.7 495.2 122.1 543.7 125.2 592.3 128.2 640.8 131.0 689.3 133.6 737.9 136.1 786.4 138.5 835.0 140.8 883.5 143.0 932.0 145.0 980.6 147.0 1029.1 149.0 1077.6 150.8 1126.2 152.6 1174.7 154.3 1223.2 156.0 1271.8 157.6 1320.3 File No.: 1700147.302 Page 33 of 43 Revision: 0 F0306-01R2

Table 16: BNP Unit 2 Non-Beltline Region, Curve B, for 54 EFPY Curve B - Core Not Critical P-T Curve P-T Curve Temperature Pressure

°F psi 103.2 0.0 111.3 48.4 118.4 96.9 124.5 145.3 130.0 193.8 134.1 233.4 137.8 273.0 141.3 312.6 141.3 312.6 198.5 1563.0 File No.: 1700147.302 Page 34 of 43 Revision: 0 F0306-01R2

Table 17: BNP Unit 2 Beltline Region, Curve C, for 54 EFPY Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 70.0 0.0 70.0 8.3 106.0 55.4 126.7 102.6 141.3 149.8 152.6 196.9 161.8 244.1 169.6 291.3 182.0 340.2 191.9 389.1 200.2 438.0 207.3 486.9 213.6 535.8 219.1 584.8 224.1 633.7 228.6 682.6 232.8 731.5 236.6 780.4 240.2 829.3 243.5 878.2 246.6 927.1 249.6 976.1 252.3 1025.0 255.0 1073.9 257.5 1122.8 259.8 1171.7 262.1 1220.6 264.3 1269.5 266.3 1318.4 File No.: 1700147.302 Page 35 of 43 Revision: 0 F0306-01R2

Table 18: BNP Unit 2 Bottom Head Region, Curve C for 54 EFPY Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F psi 97.5 0.0 108.2 48.8 116.9 97.7 124.4 146.5 130.9 195.4 136.6 244.2 141.8 293.1 146.4 341.9 150.7 390.8 154.6 439.6 158.3 488.4 161.7 537.3 164.8 586.1 167.8 635.0 170.7 683.8 173.3 732.7 175.9 781.5 178.3 830.3 180.6 879.2 182.8 928.0 184.9 976.9 186.9 1025.7 188.9 1074.6 190.7 1123.4 192.5 1172.3 194.3 1221.1 196.0 1269.9 197.6 1318.8 File No.: 1700147.302 Page 36 of 43 Revision: 0 F0306-01R2

Table 19: BNP Unit 2 Non-Beltline Region, Curve C, for 54 EFPY Curve C - Core Critical P-T Curve P-T Curve Temperature Pressure

°F Psi 143.2 0.0 150.8 44.7 157.3 89.3 163.1 134.0 168.4 178.6 173.1 223.3 177.4 267.9 181.3 312.6 188.1 312.6 188.1 397.4 191.6 445.9 194.9 494.5 197.9 543.1 200.8 591.7 203.6 640.2 206.1 688.8 208.6 737.4 211.0 785.9 213.2 834.5 215.3 883.1 217.4 931.6 219.4 980.2 221.3 1028.8 223.1 1077.3 224.9 1125.9 226.6 1174.5 228.2 1223.0 229.8 1271.6 231.4 1320.2 File No.: 1700147.302 Page 37 of 43 Revision: 0 F0306-01R2

Minimum bolt-up temperature = 70°F Figure 1: BNP Unit 1 P-T Curve A (Hydrostatic Pressure and Leak Test), 54 EFPY File No.: 1700147.302 Page 38 of 43 Revision: 0 F0306-01R2

Minimum bolt-up temperature = 70°F Minimum non-beltline temperature = 103.2°F Figure 2: BNP Unit 1 P-T Curve B (Normal Operation - Core Not Critical), 54 EFPY File No.: 1700147.302 Page 39 of 43 Revision: 0 F0306-01R2

Minimum criticality temperature = 76°F Minimum beltline temperature = 85.5°F Minimum non-beltline temperature = 143.2°F Figure 3: BNP Unit 1 P-T Curve C (Normal Operation - Core Critical), 54 EFPY File No.: 1700147.302 Page 40 of 43 Revision: 0 F0306-01R2

Minimum bolt-up temperature = 70°F Figure 4: BNP Unit 2 P-T Curve A (Hydrostatic Pressure and Leak Test), 54 EFPY File No.: 1700147.302 Page 41 of 43 Revision: 0 F0306-01R2

Minimum bolt-up temperature = 70°F Minimum non-beltline temperature = 103.2°F Figure 5: BNP Unit 2 P-T Curve B (Normal Operation - Core Not Critical), 54 EFPY File No.: 1700147.302 Page 42 of 43 Revision: 0 F0306-01R2

Minimum criticality temperature = 70°F Minimum bottom head temperature = 97.5°F Minimum non-beltline temperature = 143.2°F Figure 6: BNP Unit 2 P-T Curve C (Normal Operation - Core Critical), 54 EFPY File No.: 1700147.302 Page 43 of 43 Revision: 0 F0306-01R2

APPENDIX A P - T CURVE INPUT LISTING File No.: 1700147.302 Page A-1 of A-5 Revision: 0 F0306-01R1

Table A-1: BNP Stress Intensity Factors for Feedwater and N16 Nozzles Nozzle Applied Pressure, KIp-app Thermal, KIt Feedwater 73.74 66.83 Instrument (N16) 55.42 15.13 KI in units of ksi-in0.5 Table A-2: BNP Unit 1 P-T Curve Input Listing P-T Curve Inputs General Parameters English Unit System for Tables and Plots 10 Temperature Instrument Uncertainty Adjustment (°F) 15 Pressure Instrument Uncertainty Adjustment (psig) 62.4 Water Density (lbm/ft3) 829.75 Full-Vessel Water Height (in) 1.5 Safety Factor for Curve A 2 Safety Factor for Curves B and C 70 Bolt-up Temperature (°F) 16 ART of Closure Flange Region (°F) 10 Default Temperature Increment for Tables (°F) 50 Default Pressure Increment for Composite Tables (psig) 0 Starting Pressure for Curves (psig) 14.7 Atmospheric Pressure Adjustment (psi) 1563 Preservice hydrotest pressure (psi) 1100 In-service hydrotest pressure (psi) 195.8 Maximum in-service hydrotest temperature (°F)

Beltline Parameters 129.1 Adjusted Reference Temperature, 54 EFPY (°F) 110.5938 Vessel Radius (in) 5.496 Vessel Thickness (in) 954 Heat-up / Cool-down Rate (°F/hr)

Generic Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 10 Specific Temperature Increment for Tables (°F)

File No.: 1700147.302 Page A-2 of A-5 Revision: 0 F0306-01R1

P-T Curve Inputs Limiting Beltline (N16) Nozzle Parameters 131 Adjusted Reference Temperature (°F) 55.42 Applied Pressure Stress Intensity Factor (ksi*in^0.5) 15.13 Applied Thermal Stress Intensity Factor (ksi*in^0.5)

No Scale KIT based on Saturation Temperature?

100 Minimum Transient Temperature (°F) 550 Maximum Transient Temperature (°F) 1000 Reference Pressure for Thermal Transient (psig)

Specific Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 10 Specific Temperature Increment for Tables (°F)

Bottom Head Parameters 10 Adjusted Reference Temperature (°F) 110.5938 Vessel Radius (in) 5.4 Vessel Thickness (in) 954 Heat-up / Cool-down Rate (°F/hr) 3 Stress Concentration Factor Generic Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 4 Specific Temperature Increment for Tables (°F)

Non-Beltline (Feedwater Nozzle) Parameters 60 Adjusted Reference Temperature (°F) 73.74 Applied Pressure Stress Intensity Factor (ksi*in^0.5) 66.83 Applied Thermal Stress Intensity Factor (ksi*in^0.5) 0 Minimum Thermal Stress Intensity Factor (ksi*in^0.5)

No Scale KIT based on Saturation Temperature?

100 Minimum Transient Temperature (°F) 550 Maximum Transient Temperature (°F) 1000 Reference Pressure for Thermal Transient (psig)

Generic Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 4 Specific Temperature Increment for Tables (°F)

File No.: 1700147.302 Page A-3 of A-5 Revision: 0 F0306-01R1

Table A-3: BNP Unit 2 P-T Curve Input Listing P-T Curve Inputs General Parameters English Unit System for Tables and Plots 10 Temperature Instrument Uncertainty Adjustment (°F) 15 Pressure Instrument Uncertainty Adjustment (psig) 62.4 Water Density (lbm/ft3) 829.75 Full-Vessel Water Height (in) 1.5 Safety Factor for Curve A 2 Safety Factor for Curves B and C 70 Bolt-up Temperature (°F) 10 ART of Closure Flange Region (°F) 10 Default Temperature Increment for Tables (°F) 50 Default Pressure Increment for Composite Tables (psig) 0 Starting Pressure for Curves (psig) 14.7 Atmospheric Pressure Adjustment (psi) 1563 Preservice hydrotest pressure (psi) 1100 In-service hydrotest pressure (psi) 188.1 Maximum in-service hydrotest temperature (°F)

Beltline Parameters 103.4 Adjusted Reference Temperature, 54 EFPY (°F) 110.3125 Vessel Radius (in) 5.466 Vessel Thickness (in) 954 Heat-up / Cool-down Rate (°F/hr)

Generic Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 4 Specific Temperature Increment for Tables (°F)

File No.: 1700147.302 Page A-4 of A-5 Revision: 0 F0306-01R1

P-T Curve Inputs Limiting Beltline (N16) Nozzle Parameters 123.4 Adjusted Reference Temperature (°F) 55.42 Applied Pressure Stress Intensity Factor (ksi*in^0.5) 15.13 Applied Thermal Stress Intensity Factor (ksi*in^0.5)

No Scale KIT based on Saturation Temperature?

100 Minimum Transient Temperature (°F) 550 Maximum Transient Temperature (°F) 1000 Reference Pressure for Thermal Transient (psig)

Specific Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 10 Specific Temperature Increment for Tables (°F)

Bottom Head Parameters 40 Adjusted Reference Temperature (°F) 110.3125 Vessel Radius (in) 5.42 Vessel Thickness (in) 954 Heat-up / Cool-down Rate (°F/hr) 3 Stress Concentration Factor Generic Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 4 Specific Temperature Increment for Tables (°F)

Non-Beltline (Feedwater Nozzle) Parameters 60 Adjusted Reference Temperature (°F) 73.74 Applied Pressure Stress Intensity Factor (ksi*in^0.5) 66.83 Applied Thermal Stress Intensity Factor (ksi*in^0.5) 0 Minimum Thermal Stress Intensity Factor (ksi*in^0.5)

No Scale KIT based on Saturation Temperature?

100 Minimum Transient Temperature (°F) 550 Maximum Transient Temperature (°F) 1000 Reference Pressure for Thermal Transient (psig)

Generic Type of Static Pressure Head Addition 829.75 Specific Water Height for Static Pressure Head Addition (in)

Specific Type of Temperature Increment for Tables 4 Specific Temperature Increment for Tables (°F)

File No.: 1700147.302 Page A-5 of A-5 Revision: 0 F0306-01R1

APPENDIX B SUPPORTING CALCULATIONS File No.: 1700147.302 Page B-1 of B-30 Revision: 0 F0306-01R1

Table B-1: BNP Unit 1, Beltline Region, Curve A Calculations, for 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 38.4 25.6 70.0 0.0 60.0 38.4 25.6 70.0 541.2 70.0 39.6 26.4 80.0 558.7 80.0 41.0 27.3 90.0 580.2 90.0 42.7 28.5 100.0 606.5 100.0 44.8 29.9 110.0 638.5 110.0 47.4 31.6 120.0 677.7 120.0 50.5 33.7 130.0 725.5 130.0 54.3 36.2 140.0 783.9 140.0 59.0 39.3 150.0 855.2 150.0 64.7 43.1 160.0 942.3 160.0 71.7 47.8 170.0 1048.8 170.0 80.2 53.5 180.0 1178.7 180.0 90.6 60.4 190.0 1337.5 File No.: 1700147.302 Page B-2 of B-30 Revision: 0 F0306-01R1

Table B-2: BNP Unit 1, Instrument Nozzle, Beltline Region, Curve A Calculations, for 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 38.2 25.5 70.0 0.0 60.0 38.2 25.5 70.0 414.7 70.0 39.3 26.2 80.0 428.0 80.0 40.7 27.1 90.0 444.3 90.0 42.3 28.2 100.0 464.3 100.0 44.4 29.6 110.0 488.6 110.0 46.8 31.2 120.0 518.3 120.0 49.8 33.2 130.0 554.6 130.0 53.5 35.7 140.0 598.9 140.0 58.0 38.7 150.0 653.0 150.0 63.5 42.3 160.0 719.1 160.0 70.2 46.8 170.0 799.9 170.0 78.4 52.3 180.0 898.5 180.0 88.4 59.0 190.0 1019.0 190.0 100.7 67.1 200.0 1166.1 200.0 115.6 77.1 210.0 1345.8 Table B-3: BNP Unit 1, Bottom Head Region, Curve A Calculations, 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 89.6 59.7 70.0 0.0 60.0 89.6 59.7 70.0 858.3 64.0 94.3 62.8 74.0 905.6 68.0 99.3 66.2 78.0 956.9 72.0 104.8 69.9 82.0 1012.4 76.0 110.8 73.9 86.0 1072.6 80.0 117.3 78.2 90.0 1137.8 84.0 124.3 82.9 94.0 1208.4 88.0 131.9 87.9 98.0 1284.9 92.0 140.1 93.4 102.0 1367.8 File No.: 1700147.302 Page B-3 of B-30 Revision: 0 F0306-01R1

Table B-4: BNP Unit 1, FW Nozzle / Non-Beltline, Curve A Calculations, 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 53.9 36.0 70.0 0.0 60.0 53.9 36.0 70.0 442.6 64.0 55.7 37.1 74.0 458.3 68.0 57.5 38.4 78.0 475.2 72.0 59.6 39.7 82.0 493.5 76.0 61.8 41.2 86.0 513.3 80.0 64.1 42.8 90.0 534.8 84.0 66.7 44.5 94.0 558.1 88.0 69.5 46.3 98.0 583.4 92.0 72.5 48.3 102.0 610.7 96.0 75.8 50.5 106.0 640.3 100.0 79.3 52.9 110.0 672.4 104.0 83.2 55.5 114.0 707.1 108.0 87.4 58.2 118.0 744.8 112.0 91.9 61.2 122.0 785.5 116.0 96.7 64.5 126.0 829.7 120.0 102.0 68.0 130.0 877.6 124.0 107.8 71.8 134.0 929.4 128.0 114.0 76.0 138.0 985.5 132.0 120.7 80.5 142.0 1046.4 136.0 128.0 85.3 146.0 1112.3 140.0 135.9 90.6 150.0 1183.6 144.0 144.4 96.3 154.0 1261.0 148.0 153.7 102.5 158.0 1344.7 File No.: 1700147.302 Page B-4 of B-30 Revision: 0 F0306-01R1

Table B-5: BNP Unit 1, Beltline Region, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 38.4 3.0 70.0 0.0 60.0 38.4 3.0 70.0 23.1 70.0 39.6 3.5 80.0 36.3 80.0 41.0 4.3 90.0 52.4 90.0 42.7 5.1 100.0 72.1 100.0 44.8 6.2 110.0 96.1 110.0 47.4 7.4 120.0 125.5 120.0 50.5 9.0 130.0 161.3 130.0 54.3 10.9 140.0 205.1 140.0 59.0 13.3 150.0 258.6 150.0 64.7 16.1 160.0 324.0 160.0 71.7 19.6 170.0 403.8 170.0 80.2 23.9 180.0 501.3 180.0 90.6 29.1 190.0 620.3 190.0 103.3 35.4 200.0 765.7 200.0 118.8 43.2 210.0 943.4 210.0 137.8 52.7 220.0 1160.3 220.0 160.9 64.2 230.0 1425.3 File No.: 1700147.302 Page B-5 of B-30 Revision: 0 F0306-01R1

Table B-6: BNP Unit 1, Instrument Nozzle, Beltline Region, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 38.2 11.5 70.0 0.0 60.0 38.2 11.5 70.0 163.3 70.0 39.3 12.1 80.0 173.3 80.0 40.7 12.8 90.0 185.5 90.0 42.3 13.6 100.0 200.5 100.0 44.4 14.6 110.0 218.7 110.0 46.8 15.8 120.0 241.0 120.0 49.8 17.4 130.0 268.2 130.0 53.5 19.2 140.0 301.4 140.0 58.0 21.4 150.0 342.0 150.0 63.5 24.2 160.0 391.6 160.0 70.2 27.6 170.0 452.2 170.0 78.4 31.7 180.0 526.1 180.0 88.4 36.7 190.0 616.5 190.0 100.7 42.8 200.0 726.8 200.0 115.6 50.2 210.0 861.6 210.0 133.9 59.4 220.0 1026.2 220.0 156.1 70.5 230.0 1227.3 230.0 183.4 84.1 240.0 1472.9 File No.: 1700147.302 Page B-6 of B-30 Revision: 0 F0306-01R1

Table B-7: BNP Unit 1, Bottom Head Region, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 89.6 19.5 70.0 0.0 60.0 89.6 19.5 70.0 285.6 64.0 94.3 21.8 74.0 325.4 68.0 99.3 24.4 78.0 368.6 72.0 104.8 27.1 82.0 415.3 76.0 110.8 30.1 86.0 465.9 80.0 117.3 33.3 90.0 520.8 84.0 124.3 36.8 94.0 580.2 88.0 131.9 40.6 98.0 644.5 92.0 140.1 44.7 102.0 714.2 96.0 149.0 49.2 106.0 789.7 100.0 158.6 54.0 110.0 871.5 104.0 169.1 59.2 114.0 960.2 108.0 180.4 64.9 118.0 1056.2 112.0 192.7 71.0 122.0 1160.2 116.0 205.9 77.7 126.0 1272.8 120.0 220.3 84.9 130.0 1394.9 File No.: 1700147.302 Page B-7 of B-30 Revision: 0 F0306-01R1

Table B-8: BNP Unit 1, FW Nozzle / Non-Beltline, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 93.2 73.5 3.3 103.2 0.0 97.2 76.8 5.0 107.2 22.9 101.2 80.5 6.8 111.2 47.5 105.2 84.4 8.8 115.2 74.2 109.2 88.7 10.9 119.2 103.1 113.2 93.3 13.2 123.2 134.4 117.2 98.3 15.7 127.2 168.4 121.2 103.7 18.4 131.2 205.1 125.2 109.6 21.4 135.2 244.9 129.2 115.9 24.6 139.2 288.1 133.2 122.8 28.0 143.2 334.8 137.2 130.3 31.7 147.2 385.4 141.2 138.4 35.8 151.2 440.3 145.2 147.2 40.2 155.2 499.7 149.2 156.6 44.9 159.2 564.0 153.2 166.9 50.0 163.2 633.7 157.2 178.1 55.6 167.2 709.2 161.2 190.1 61.6 171.2 791.1 165.2 203.2 68.2 175.2 879.7 169.2 217.4 75.3 179.2 975.7 173.2 232.7 82.9 183.2 1079.7 177.2 249.3 91.2 187.2 1192.3 181.2 267.3 100.2 191.2 1314.4 File No.: 1700147.302 Page B-8 of B-30 Revision: 0 F0306-01R1

Table B-9: BNP Unit 1, Beltline Region, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 35.5 36.4 2.0 85.5 0.0 45.5 37.1 2.3 95.5 8.1 55.5 38.0 2.7 105.5 18.0 65.5 39.0 3.3 115.5 30.0 75.5 40.3 3.9 125.5 44.7 85.5 41.9 4.7 135.5 62.7 95.5 43.8 5.7 145.5 84.7 105.5 46.1 6.8 155.5 111.5 115.5 49.0 8.3 165.5 144.3 125.5 52.5 10.0 175.5 184.3 135.5 56.8 12.2 185.5 233.2 145.5 62.0 14.8 195.5 293.0 155.5 68.4 17.9 205.5 365.9 165.5 76.1 21.8 215.5 455.0 175.5 85.6 26.6 225.5 563.8 185.5 97.3 32.4 235.5 696.7 195.5 111.4 39.5 245.5 859.0 205.5 128.8 48.2 255.5 1057.3 215.5 149.9 58.7 265.5 1299.5 225.5 175.8 71.7 275.5 1595.3 File No.: 1700147.302 Page B-9 of B-30 Revision: 0 F0306-01R1

Table B-10: BNP Unit 1, Instrument Nozzle, Beltline Region, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 26.0 35.7 10.3 76.0 0.0 26.0 35.7 10.3 76.0 141.0 36.0 36.3 10.6 86.0 146.0 46.0 37.0 10.9 96.0 152.2 56.0 37.8 11.3 106.0 159.8 66.0 38.9 11.9 116.0 169.0 76.0 40.1 12.5 126.0 180.3 86.0 41.6 13.2 136.0 194.1 96.0 43.5 14.2 146.0 211.0 106.0 45.8 15.3 156.0 231.5 116.0 48.6 16.7 166.0 256.6 126.0 52.0 18.4 176.0 287.3 136.0 56.1 20.5 186.0 324.8 146.0 61.2 23.0 196.0 370.6 156.0 67.4 26.1 206.0 426.5 166.0 75.0 29.9 216.0 494.8 176.0 84.2 34.5 226.0 578.2 186.0 95.5 40.2 236.0 680.0 196.0 109.3 47.1 246.0 804.5 206.0 126.1 55.5 256.0 956.4 216.0 146.7 65.8 266.0 1142.0 226.0 171.8 78.3 276.0 1368.7 File No.: 1700147.302 Page B-10 of B-30 Revision: 0 F0306-01R1

Table B-11: BNP Unit 1, Bottom Head Region, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 26.0 61.8 5.6 76.0 0.0 26.0 61.8 5.6 76.0 49.7 30.0 64.1 6.8 80.0 69.9 34.0 66.7 8.1 84.0 91.8 38.0 69.5 9.5 88.0 115.4 42.0 72.5 11.0 92.0 141.1 46.0 75.8 12.6 96.0 168.9 50.0 79.3 14.4 100.0 199.0 54.0 83.2 16.3 104.0 231.6 58.0 87.4 18.4 108.0 266.9 62.0 91.9 20.6 112.0 305.1 66.0 96.7 23.1 116.0 346.6 70.0 102.0 25.7 120.0 391.5 74.0 107.8 28.6 124.0 440.1 78.0 114.0 31.7 128.0 492.8 82.0 120.7 35.1 132.0 549.9 86.0 128.0 38.7 136.0 611.7 90.0 135.9 42.7 140.0 678.7 94.0 144.4 46.9 144.0 751.2 98.0 153.7 51.6 148.0 829.8 102.0 163.8 56.6 152.0 915.0 106.0 174.6 62.0 156.0 1007.2 110.0 186.4 67.9 160.0 1107.1 114.0 199.2 74.3 164.0 1215.4 118.0 213.0 81.2 168.0 1332.6 File No.: 1700147.302 Page B-11 of B-30 Revision: 0 F0306-01R1

Table B-12: BNP Unit 1, FW Nozzle / Non-Beltline, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 93.2 73.5 3.3 143.2 0.0 97.2 76.8 5.0 147.2 22.9 101.2 80.5 6.8 151.2 47.5 105.2 84.4 8.8 155.2 74.2 109.2 88.7 10.9 159.2 103.1 113.2 93.3 13.2 163.2 134.4 117.2 98.3 15.7 167.2 168.4 121.2 103.7 18.4 171.2 205.1 125.2 109.6 21.4 175.2 244.9 129.2 115.9 24.6 179.2 288.1 133.2 122.8 28.0 183.2 334.8 137.2 130.3 31.7 187.2 385.4 141.2 138.4 35.8 191.2 440.3 145.2 147.2 40.2 195.2 499.7 149.2 156.6 44.9 199.2 564.0 153.2 166.9 50.0 203.2 633.7 157.2 178.1 55.6 207.2 709.2 161.2 190.1 61.6 211.2 791.1 165.2 203.2 68.2 215.2 879.7 169.2 217.4 75.3 219.2 975.7 173.2 232.7 82.9 223.2 1079.7 177.2 249.3 91.2 227.2 1192.3 181.2 267.3 100.2 231.2 1314.4 File No.: 1700147.302 Page B-12 of B-30 Revision: 0 F0306-01R1

Table B-13: BNP Unit 2, Beltline Region, Curve A Calculations, for 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 41.9 27.9 70.0 0.0 60.0 41.9 27.9 70.0 594.4 64.0 42.6 28.4 74.0 605.5 68.0 43.4 28.9 78.0 617.5 72.0 44.3 29.5 82.0 630.4 76.0 45.2 30.1 86.0 644.5 80.0 46.2 30.8 90.0 659.7 84.0 47.3 31.5 94.0 676.2 88.0 48.4 32.3 98.0 694.1 92.0 49.7 33.1 102.0 713.5 96.0 51.1 34.1 106.0 734.5 100.0 52.6 35.0 110.0 757.2 104.0 54.2 36.1 114.0 781.8 108.0 55.9 37.3 118.0 808.5 112.0 57.8 38.6 122.0 837.4 116.0 59.9 39.9 126.0 868.7 120.0 62.1 41.4 130.0 902.6 124.0 64.5 43.0 134.0 939.3 128.0 67.1 44.7 138.0 979.1 132.0 69.9 46.6 142.0 1022.2 136.0 73.0 48.7 146.0 1068.8 140.0 76.3 50.9 150.0 1119.4 144.0 79.9 53.3 154.0 1174.2 148.0 83.8 55.9 158.0 1233.6 152.0 88.0 58.7 162.0 1297.8 156.0 92.6 61.7 166.0 1367.5 File No.: 1700147.302 Page B-13 of B-30 Revision: 0 F0306-01R1

Table B-14: BNP Unit 2, Instrument Nozzle, Beltline Region, Curve A Calculations, for 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 39.0 26.0 70.0 0.0 60.0 39.0 26.0 70.0 424.6 70.0 40.3 26.9 80.0 440.1 80.0 41.9 27.9 90.0 459.1 90.0 43.8 29.2 100.0 482.3 100.0 46.2 30.8 110.0 510.6 110.0 49.1 32.7 120.0 545.2 120.0 52.6 35.0 130.0 587.4 130.0 56.9 37.9 140.0 639.0 140.0 62.1 41.4 150.0 702.0 150.0 68.5 45.7 160.0 779.0 160.0 76.3 50.9 170.0 873.0 170.0 85.9 57.2 180.0 987.8 180.0 97.5 65.0 190.0 1128.1 190.0 111.8 74.5 200.0 1299.4 200.0 129.1 86.1 210.0 1508.6 File No.: 1700147.302 Page B-14 of B-30 Revision: 0 F0306-01R1

Table B-15: BNP Unit 2, Bottom Head Region, Curve A Calculations, 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 64.1 42.8 70.0 0.0 60.0 64.1 42.8 70.0 604.6 64.0 66.7 44.5 74.0 630.7 68.0 69.5 46.3 78.0 659.0 72.0 72.5 48.3 82.0 689.6 76.0 75.8 50.5 86.0 722.8 80.0 79.3 52.9 90.0 758.7 84.0 83.2 55.5 94.0 797.7 88.0 87.4 58.2 98.0 839.8 92.0 91.9 61.2 102.0 885.5 96.0 96.7 64.5 106.0 935.0 100.0 102.0 68.0 110.0 988.6 104.0 107.8 71.8 114.0 1046.7 108.0 114.0 76.0 118.0 1109.6 112.0 120.7 80.5 122.0 1177.8 116.0 128.0 85.3 126.0 1251.6 120.0 135.9 90.6 130.0 1331.6 File No.: 1700147.302 Page B-15 of B-30 Revision: 0 F0306-01R1

Table B-16: BNP Unit 2, FW Nozzle / Non-Beltline, Curve A Calculations, 54 EFPY Curve A - Pressure Test Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 53.9 36.0 70.0 0.0 60.0 53.9 36.0 70.0 442.6 64.0 55.7 37.1 74.0 458.3 68.0 57.5 38.4 78.0 475.2 72.0 59.6 39.7 82.0 493.5 76.0 61.8 41.2 86.0 513.3 80.0 64.1 42.8 90.0 534.8 84.0 66.7 44.5 94.0 558.1 88.0 69.5 46.3 98.0 583.4 92.0 72.5 48.3 102.0 610.7 96.0 75.8 50.5 106.0 640.3 100.0 79.3 52.9 110.0 672.4 104.0 83.2 55.5 114.0 707.1 108.0 87.4 58.2 118.0 744.8 112.0 91.9 61.2 122.0 785.5 116.0 96.7 64.5 126.0 829.7 120.0 102.0 68.0 130.0 877.6 124.0 107.8 71.8 134.0 929.4 128.0 114.0 76.0 138.0 985.5 132.0 120.7 80.5 142.0 1046.4 136.0 128.0 85.3 146.0 1112.3 140.0 135.9 90.6 150.0 1183.6 144.0 144.4 96.3 154.0 1261.0 148.0 153.7 102.5 158.0 1344.7 File No.: 1700147.302 Page B-16 of B-30 Revision: 0 F0306-01R1

Table B-17: BNP Unit 2, Beltline Region, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 41.9 4.7 70.0 0.0 60.0 41.9 4.7 70.0 63.1 64.0 42.6 5.1 74.0 71.4 68.0 43.4 5.5 78.0 80.4 72.0 44.3 5.9 82.0 90.1 76.0 45.2 6.4 86.0 100.7 80.0 46.2 6.9 90.0 112.1 84.0 47.3 7.4 94.0 124.5 88.0 48.4 8.0 98.0 137.9 92.0 49.7 8.6 102.0 152.4 96.0 51.1 9.3 106.0 168.1 100.0 52.6 10.1 110.0 185.2 104.0 54.2 10.9 114.0 203.6 108.0 55.9 11.7 118.0 223.6 112.0 57.8 12.7 122.0 245.3 116.0 59.9 13.7 126.0 268.8 120.0 62.1 14.8 130.0 294.2 124.0 64.5 16.0 134.0 321.8 128.0 67.1 17.3 138.0 351.6 132.0 69.9 18.7 142.0 383.9 136.0 73.0 20.3 146.0 418.9 140.0 76.3 21.9 150.0 456.9 144.0 79.9 23.7 154.0 497.9 148.0 83.8 25.7 158.0 542.5 152.0 88.0 27.8 162.0 590.7 156.0 92.6 30.1 166.0 642.9 160.0 97.5 32.5 170.0 699.5 164.0 102.9 35.2 174.0 760.8 168.0 108.7 38.1 178.0 827.2 172.0 115.0 41.2 182.0 899.1 176.0 121.8 44.7 186.0 977.1 180.0 129.1 48.3 190.0 1061.5 184.0 137.1 52.3 194.0 1152.9 188.0 145.8 56.7 198.0 1252.0 192.0 155.2 61.4 202.0 1359.3 File No.: 1700147.302 Page B-17 of B-30 Revision: 0 F0306-01R1

Table B-18: BNP Unit 2, Instrument Nozzle, Beltline Region, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 39.0 12.0 70.0 0.0 60.0 39.0 12.0 70.0 170.7 70.0 40.3 12.6 80.0 182.4 80.0 41.9 13.4 90.0 196.6 90.0 43.8 14.4 100.0 214.0 100.0 46.2 15.5 110.0 235.2 110.0 49.1 17.0 120.0 261.2 120.0 52.6 18.7 130.0 292.8 130.0 56.9 20.9 140.0 331.5 140.0 62.1 23.5 150.0 378.8 150.0 68.5 26.7 160.0 436.5 160.0 76.3 30.6 170.0 507.0 170.0 85.9 35.4 180.0 593.1 180.0 97.5 41.2 190.0 698.3 190.0 111.8 48.3 200.0 826.8 200.0 129.1 57.0 210.0 983.7 210.0 150.4 67.6 220.0 1175.3 220.0 176.3 80.6 230.0 1409.4 File No.: 1700147.302 Page B-18 of B-30 Revision: 0 F0306-01R1

Table B-19: BNP Unit 2, Bottom Head Region, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 60.0 64.1 6.0 70.0 0.0 60.0 64.1 6.0 70.0 58.4 64.0 66.7 7.3 74.0 80.4 68.0 69.5 8.7 78.0 104.3 72.0 72.5 10.2 82.0 130.1 76.0 75.8 11.9 86.0 158.1 80.0 79.3 13.6 90.0 188.5 84.0 83.2 15.6 94.0 221.4 88.0 87.4 17.7 98.0 257.0 92.0 91.9 19.9 102.0 295.5 96.0 96.7 22.3 106.0 337.3 100.0 102.0 25.0 110.0 382.6 104.0 107.8 27.9 114.0 431.6 108.0 114.0 31.0 118.0 484.8 112.0 120.7 34.3 122.0 542.3 116.0 128.0 38.0 126.0 604.6 120.0 135.9 41.9 130.0 672.2 124.0 144.4 46.2 134.0 745.3 128.0 153.7 50.8 138.0 824.6 132.0 163.8 55.9 142.0 910.4 136.0 174.6 61.3 146.0 1003.4 140.0 186.4 67.2 150.0 1104.2 144.0 199.2 73.6 154.0 1213.3 148.0 213.0 80.5 158.0 1331.5 File No.: 1700147.302 Page B-19 of B-30 Revision: 0 F0306-01R1

Table B-20: BNP Unit 2, FW Nozzle / Non-Beltline, Curve B Calculations, for 54 EFPY Curve B - Core Not Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 93.2 73.5 3.3 103.2 0.0 97.2 76.8 5.0 107.2 22.9 101.2 80.5 6.8 111.2 47.5 105.2 84.4 8.8 115.2 74.2 109.2 88.7 10.9 119.2 103.1 113.2 93.3 13.2 123.2 134.4 117.2 98.3 15.7 127.2 168.4 121.2 103.7 18.4 131.2 205.1 125.2 109.6 21.4 135.2 244.9 129.2 115.9 24.6 139.2 288.1 133.2 122.8 28.0 143.2 334.8 137.2 130.3 31.7 147.2 385.4 141.2 138.4 35.8 151.2 440.3 145.2 147.2 40.2 155.2 499.7 149.2 156.6 44.9 159.2 564.0 153.2 166.9 50.0 163.2 633.7 157.2 178.1 55.6 167.2 709.2 161.2 190.1 61.6 171.2 791.1 165.2 203.2 68.2 175.2 879.7 169.2 217.4 75.3 179.2 975.7 173.2 232.7 82.9 183.2 1079.7 177.2 249.3 91.2 187.2 1192.3 181.2 267.3 100.2 191.2 1314.4 File No.: 1700147.302 Page B-20 of B-30 Revision: 0 F0306-01R1

Table B-21: BNP Unit 2, Beltline Region, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 20.0 37.1 2.3 70.0 0.0 20.0 37.1 2.3 70.0 8.3 30.0 38.0 2.8 80.0 18.2 40.0 39.0 3.3 90.0 30.3 50.0 40.3 3.9 100.0 45.1 60.0 41.9 4.7 110.0 63.1 70.0 43.8 5.7 120.0 85.2 80.0 46.2 6.9 130.0 112.1 90.0 49.1 8.3 140.0 145.0 100.0 52.6 10.1 150.0 185.2 110.0 56.9 12.2 160.0 234.3 120.0 62.1 14.8 170.0 294.2 130.0 68.5 18.0 180.0 367.4 140.0 76.3 21.9 190.0 456.9 150.0 85.9 26.7 200.0 566.1 160.0 97.5 32.5 210.0 699.5 170.0 111.8 39.6 220.0 862.4 180.0 129.1 48.3 230.0 1061.5 190.0 150.4 59.0 240.0 1304.6 File No.: 1700147.302 Page B-21 of B-30 Revision: 0 F0306-01R1

Table B-22: BNP Unit 2, Instrument Nozzle, Beltline Region, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 20.0 35.8 10.3 70.0 0.0 20.0 35.8 10.3 70.0 141.7 30.0 36.4 10.6 80.0 147.0 40.0 37.1 11.0 90.0 153.3 50.0 38.0 11.4 100.0 161.2 60.0 39.0 12.0 110.0 170.7 70.0 40.3 12.6 120.0 182.4 80.0 41.9 13.4 130.0 196.6 90.0 43.8 14.4 140.0 214.0 100.0 46.2 15.5 150.0 235.2 110.0 49.1 17.0 160.0 261.2 120.0 52.6 18.7 170.0 292.8 130.0 56.9 20.9 180.0 331.5 140.0 62.1 23.5 190.0 378.8 150.0 68.5 26.7 200.0 436.5 160.0 76.3 30.6 210.0 507.0 170.0 85.9 35.4 220.0 593.1 180.0 97.5 41.2 230.0 698.3 190.0 111.8 48.3 240.0 826.8 200.0 129.1 57.0 250.0 983.7 210.0 150.4 67.6 260.0 1175.3 220.0 176.3 80.6 270.0 1409.4 File No.: 1700147.302 Page B-22 of B-30 Revision: 0 F0306-01R1

Table B-23: BNP Unit 2, Bottom Head Region, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 47.5 57.3 2.6 97.5 0.0 51.5 59.3 3.6 101.5 17.2 55.5 61.5 4.7 105.5 35.8 59.5 63.8 5.9 109.5 55.9 63.5 66.4 7.2 113.5 77.8 67.5 69.2 8.6 117.5 101.4 71.5 72.2 10.1 121.5 127.1 75.5 75.4 11.7 125.5 154.8 79.5 78.9 13.4 129.5 184.9 83.5 82.7 15.3 133.5 217.4 87.5 86.9 17.4 137.5 252.7 91.5 91.3 19.6 141.5 290.9 95.5 96.2 22.1 145.5 332.4 99.5 101.4 24.7 149.5 377.2 103.5 107.1 27.5 153.5 425.8 107.5 113.2 30.6 157.5 478.4 111.5 119.9 33.9 161.5 535.5 115.5 127.1 37.5 165.5 597.2 119.5 135.0 41.5 169.5 664.1 123.5 143.4 45.7 173.5 736.6 127.5 152.6 50.3 177.5 815.1 131.5 162.6 55.3 181.5 900.2 135.5 173.3 60.6 185.5 992.4 139.5 185.0 66.5 189.5 1092.2 143.5 197.6 72.8 193.5 1200.3 147.5 211.3 79.6 197.5 1317.5 File No.: 1700147.302 Page B-23 of B-30 Revision: 0 F0306-01R1

Table B-24: BNP Unit 2, FW Nozzle / Non-Beltline, Curve C Calculations, for 54 EFPY Curve C - Core Critical Gage Fluid P-T Curve P-T Curve KIc KIp Temperature Temperature Pressure

°F ksi*in^0.5 ksi*in^0.5 °F psi 93.2 73.5 3.3 143.2 0.0 97.2 76.8 5.0 147.2 22.9 101.2 80.5 6.8 151.2 47.5 105.2 84.4 8.8 155.2 74.2 109.2 88.7 10.9 159.2 103.1 113.2 93.3 13.2 163.2 134.4 117.2 98.3 15.7 167.2 168.4 121.2 103.7 18.4 171.2 205.1 125.2 109.6 21.4 175.2 244.9 129.2 115.9 24.6 179.2 288.1 133.2 122.8 28.0 183.2 334.8 137.2 130.3 31.7 187.2 385.4 141.2 138.4 35.8 191.2 440.3 145.2 147.2 40.2 195.2 499.7 149.2 156.6 44.9 199.2 564.0 153.2 166.9 50.0 203.2 633.7 157.2 178.1 55.6 207.2 709.2 161.2 190.1 61.6 211.2 791.1 165.2 203.2 68.2 215.2 879.7 169.2 217.4 75.3 219.2 975.7 173.2 232.7 82.9 223.2 1079.7 177.2 249.3 91.2 227.2 1192.3 181.2 267.3 100.2 231.2 1314.4 File No.: 1700147.302 Page B-24 of B-30 Revision: 0 F0306-01R1

Figure B-1: BNP Unit 1 (Hydrostatic Pressure and Leak Test) P-T Curve A, 54 EFPY Note: BL is Beltline, BN is Beltline Nozzle, BH is Bottom Head, and FWN is Feedwater Nozzle File No.: 1700147.302 Page B-25 of B-30 Revision: 0 F0306-01R1

Figure B-2: BNP Unit 1 P-T Curve B (Normal Operation - Core Not Critical), 54 EFPY Note: BL is Beltline, BN is Beltline Nozzle, BH is Bottom Head, and FWN is Feedwater Nozzle File No.: 1700147.302 Page B-26 of B-30 Revision: 0 F0306-01R1

Figure B-3: BNP Unit 1 P-T Curve C (Normal Operation - Core Critical), 54 EFPY Note: BL is Beltline, BN is Beltline Nozzle, BH is Bottom Head, and FWN is Feedwater Nozzle File No.: 1700147.302 Page B-27 of B-30 Revision: 0 F0306-01R1

Figure B-4: BNP Unit 2 (Hydrostatic Pressure and Leak Test) P-T Curve A, 54 EFPY Note: BL is Beltline, BN is Beltline Nozzle, BH is Bottom Head, and FWN is Feedwater Nozzle File No.: 1700147.302 Page B-28 of B-30 Revision: 0 F0306-01R1

Figure B-5: BNP Unit 2 P-T Curve B (Normal Operation - Core Not Critical), 54 EFPY Note: BL is Beltline, BN is Beltline Nozzle, BH is Bottom Head, and FWN is Feedwater Nozzle File No.: 1700147.302 Page B-29 of B-30 Revision: 0 F0306-01R1

Figure B-6: BNP Unit 2 P-T Curve C (Normal Operation - Core Critical), 54 EFPY Note: BL is Beltline, BN is Beltline Nozzle, BH is Bottom Head, and FWN is Feedwater Nozzle File No.: 1700147.302 Page B-30 of B-30 Revision: 0 F0306-01R1

v t e Letter Sequence Response to RAI
EPID:L-2018-LLA-0094, TSTF-419 (Approved, Closed)
Initiation Request Acceptance... Supplement Administration Questions 10 August 2018 31 August 2018 Answers 27 September 2018 11 December 2018 Results Approval Other: ML18130A826
MONTHYEAR2018-05-29 [Table View]

RA-18-0163, Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report

Text

Subject:

References:

Enclosures:

Subject:

1.0 INTRODUCTION

6.0 CONCLUSION

7.0 REFERENCES

1.0 INTRODUCTION

6.0 CONCLUSION

7.0 REFERENCES

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