RS-14-265, Response to Request for Additional Information Regarding Request for Withholding Information from Public Disclosure by Electric Power Research Institute, Inc

Response to Request for Additional Information Regarding Request for Withholding Information from Public Disclosure by Electric Power Research Institute, Inc

ML14255A348
Person / Time
Site:	LaSalle
Issue date:	09/11/2014
From:	Gullott D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-14-265
Download: ML14255A348 (43)

Text

4300 Winfield Road Warrenville. IL 60555 Amminw Exelon Generation 630 657 2000 Office RS-14-265 10 CFR 50.90 September 11,2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Unit 1 Facility Operating License No. NPF-11 NRC Docket No. 50-373

Subject:

Response to Request for Additional Information Regarding Request for Withholding Information from Public Disclosure by Electric Power Research Institute, Inc.

References:

1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "License Amendment Request to Revise Reactor Coolant System (RCS) Pressure and Temperature (PIT) Curves for LaSalle County Station, Unit 1," dated December 20, 2013

2) Letter from B. Purnell (U. S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "LaSalle County Station, Unit 1 Request by Electric Power Research Institute, Inc. to Withhold Information from Public Disclosure (TAG No. MF3270)," dated August 27, 2014 In Reference 1, Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) to Facility Operating License No. NPF-11 for LaSalle County Station (LSCS),

Unit 1. Specifically, the proposed change would revise the reactor coolant system (RCS) pressure and temperature (PIT) curves contained in Technical Specifications (TS) 3.4.11, "RCS Pressure and Temperature (PIT) Limits," Figures 3.4.11-1 through 3.4.11-3. The EGC LAR included two copies of an affidavit executed by Electric Power Research Institute, Inc.

(EPRI), requesting that some information contained in Attachments 4, 5, 6, and 7 of the LAR be withheld from public disclosure pursuant to 10 CFR 2.390.

In Reference 2, the U. S. Nuclear Regulatory Commission (NRC) requested additional information to complete its review of the EPRI request for withholding information from public disclosure. Attachments 1 through 3 provide the requested information.

With the response to Reference 2, it was determined that the information previously identified in Reference 1 as proprietary to EPRI is now considered non-proprietary. The revised non-proprietary LSCS Unit 1 Pressure / Temperature Limits Report provided in Attachment 2 of this submittal supersedes the EPRI proprietary version of the report provided in Attachment 4,

September 11,2014 U. S. Nuclear Regulatory Commission Page 2 , of Reference 1 and the non-proprietary version of the report provided in of Reference 1. The revised non-proprietary response to Grand Gulf Nuclear Station (GGNS) request for additional information (RAI) #6 provided in Attachment 3 of this submittal supersedes the EPRI proprietary response to GGNS RAI #6 provided in Attachment 6, , of Reference 1 and the EPRI non-proprietary response to GGNS RAI #6 provided in of Reference 1. The content of the PIT limits report and RAI response has not been revised; however, the basis for withholding the information has changed.

EGO has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration that was previously provided to the NRC in Attachment 1 of Reference 1. The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the additional information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environment assessment needs to be prepared in connection with the proposed amendment.

There are no regulatory commitments contained within this letter.

Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630) 657-2815.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 11th day of September 2014.

Respectfully, David M. Gullott Manager Licensing Exelon Generation Company, LLC Attachments:

1) Response to Request for Additional Information

2) Revised LaSalle County Station Unit 1 Pressure / Temperature Limits Report (Non-Proprietary)

3) Revised Exelon Response to GGNS RAI #6 (Non-Proprietary) cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency Division of Nuclear Safety

ATTACHMENT 1 Response to Request for Additional Information By letter dated December 20, 2013, Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) to revise the reactor coolant system (RCS) pressure and temperature (PIT) curves contained in Technical Specifications (TS) 3.4.11, "RCS Pressure and Temperature (PIT) Limits," Figures 3.4.11-1 through 3.4.11-3 for LaSalle County Station (LSCS),

Unit 1. The EGC LAR included two copies of an affidavit dated April 2, 2013, executed by Neil Wilmshurst of Electric Power Research Institute, Inc. (EPRI), requesting that some information contained in Attachments 4, 5, 6, and 7 of the LAR be withheld from public disclosure pursuant to 10 CFR 2.390.

By letter dated August 27, 2014, the U. S. Nuclear Regulatory Commission (NRC) requested additional information to complete its review of the EPRI request for withholding information from public disclosure. Attachments 1 through 3 provide the requested information.

NRC Question RAI-1:

By letter dated November 18, 2011, EPRI submitted Technical Report 1022850, "BWRVIP-250NP: BWR Vessel and Internals Project Testing and Evaluation of the LaSalle Unit 1 120° Surveillance Capsule," dated October 2011. EPRI's letter states "the enclosed report is non-proprietary and is available to the public by request to EPRI." This report is publicly available in ADAMS under Accession No. ML11326A290.

The NRC staff notes that most of the information EPRI requests to be withheld from public disclosure in its April 2, 2013, affidavit was made publicly available by EPRI in Technical Report 1022850.

Provide a response to the following:

a. Explain how EPRI has held the information in confidence when it has been made publicly available by EPRI.

b. Explain how this is a type of information normally held in confidence when it has been made publicly available by EPRI.

c. Explain how release of this information would cause substantial harm to EPRI when EPRI has previously made this information available to the public.

EGC Response to NRC Question RAI-1:

EPRI agrees that some of the information requested to be withheld from public disclosure was previously published in the non-proprietary Technical Report 1022850. Therefore, the following information previously identified as proprietary has been revised to be non-proprietary:

Page 1 of 3

ATTACHMENT 1 Response to Request for Additional Information

• The ISP plate and weld heat numbers and corresponding %Cu and %Ni values listed in Attachment 4, Enclosure 3, Appendix B Table B-4.

• The ISP plate and weld heat numbers and corresponding %Cu and %Ni values listed in Attachment 6, Enclosure 5, GGNS RAI #6.

• The tables listing Best Estimate Chemistry for plate Heat C6345-1 and weld Heat 1P3571 listed in Attachment 6, Enclosure 5, GGNS RAI#6 NRC Question RAI-2:

By email dated January 31, 2011 (ADAMS Accession No. ML110310390), NRC staff issued a request for additional information (RAI) to Grand Gulf Nuclear Station, Unit 1 (GGNS), regarding its PIT limits. As noted in Exelon's application, the staff has requested that future applicants for PIT limit changes include a response to this GGNS RAI. In Attachment 6 of the application, Exelon provided the LSCS, Unit 1, responses to this GGNS RAI.

The NRC staff notes that a publicly available version of the February 23, 2011, GGNS RAI response is available in ADAMS under Accession No. ML110540540. The public information from GGNS appears to be of a similar type to some of the information which EPRI is requesting to be withheld from the public.

Provide a response to the following:

a. Explain how the information requested to be withheld is of a different type than the information contained in the GGNS RAI response.

b. Explain how this is a type of information normally held in confidence when it appears that similar information has been made public.

c. Explain how release of this information would cause substantial harm to EPRI when it appears that similar information has been made public.

EGC Response to NRC Question RAI-2:

EPRI agrees that some of the information requested to be withheld from public disclosure is of a similar type to information provided as non-proprietary by Grand Gulf Nuclear Station.

Therefore, the following information previously identified as proprietary has been revised to be non-proprietary:

• The table listing the Target Vessel and ISP Representative Materials listed in Attachment 6, Enclosure 5, GGNS RAI#6

• The AG 1.99 calculated chemistry factors associated with the LSCS plate listed in Attachment 6, Enclosure 5, GGNS RAI#6 Page 2 of 3

ATTACHMENT 1 Response to Request for Additional Information NRC Question RAI-3:

The application indicates that guidance contained in NRC Regulatory Guide (RG) 1.99, "Radiation Embrittlement of Reactor Vessel Materials," Revision 2, dated May 1988 (ADAMS Accession No. ML003740284), was used to derive certain values. EPRI has requested that some of these values be withheld from public disclosure. However, the NRC staff notes that the input used to derive these parameters appears to be publicly available in EPRI Technical Report 1022850.

Provide a response to the following:

a. Explain how release of this information would cause substantial harm to EPRI when it appears that the values can be derived from publicly available methods in RG 1.99 using information made public by EPRI.

b. Provide an estimate of the amount of effort and money it took to derive these values given that the information and methods are publicly available.

EGC Response to NRC Question RAI-3:

As discussed in responses to RAI-1 and RAI-2, EPRI agrees that some of the information requested to be withheld from public disclosure should be revised to be non-proprietary. EPRI agrees that when the methodology of RG 1.99 is applied to the newly non-proprietary information, the resultant values are non-proprietary. Therefore, the following information previously identified as proprietary has been revised to be non-proprietary:

• The RG 1.99 calculated chemistry factors associated with the Best Estimate Chemistry values, and the EPRI fitted chemistry factors for plate Heat C6345-1 and weld Heat 1P3571 listed in Attachment 6, Enclosure 5, GGNS RAI#6

• The calculation of the adjusted surveillance chemistry factor listed in Attachment 6, Enclosure 5, GGNS RAI#6 Page 3 of 3

ATTACHMENT 2 Revised LaSalle County Station Unit 1 Pressure / Temperature Limits Report (Non-Proprietary)

LaSalle County Station, Unit 1 33 pages follow

EPRI Non-Proprietary Information ATTACHMENT 5 LaSalle County Station Unit 1 Pressure / Temperature Limits Report (NON-PROPRIETARY)

Page 1 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Table of Contents Section Page 1.0 Purpose 3 2.0 Applicability 3 3.0 Methodology 4 4.0 Operating Limits 5 5.0 Discussion 6 6.0 References 10 Figure 1 Bottom Head and Composite (Upper Vessel & Beltline) Pressure Test P/T Curves [Curve A] up to 32 EPY [20°F/hr or less coolant heatup/cooldown] 12 Figure 2 Bottom Head and Composite (Upper Vessel & Beltline) Core Not Critical P/T Curves [Curve B] up to 32 EFPY [100°F/hr or less coolant heatup/cooldown] 13 Figure 3 Composite Core Critical P/T Curves [Curve C] up to 32 EFPY [100°F or less coolant heatup/cooldown] 14 Table 1 LSCS Unit 1 P/T Curve Values for 32 EFPY 15 Appendix A: Reactor Vessel Material Surveillance Program 20 Appendix B: LSCS Unit 1 Reactor Pressure Vessel P/T Curve Supporting Plant-Specific Information 21 Appendix C: LSCS Unit 1 Reactor Pressure Vessel P/T Curve Checklist 30 Page 2 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits 1.0 Purpose LaSalle County Station (LSCS) is a participant in the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP),

currently administrated by Electric Power Research Institute (EPRI). The 1200 capsule was removed from Unit 1 in February 2010 in accordance with the BWRVIP protocol of the ISP. Based on testing performed on the specimens, the limiting beltline material shift value for Unit 1 is increased, and consequently, results in an increase in the Adjusted Reference Temperature (ART) which is the initial Reference Temperature of Nil-Ductility Transition (RTNDT) plus the change in RTNIDT (ARTNDT) plus margin. As a result, the Unit 1 P/T curves are non-conservative for 32 Effective Full Power Years (EFPY).

The purpose of this Pressure and Temperature Limits Amendment Request is to incorporate the ISP results into revised operating limits relating to:

1. Reactor Coolant System (RCS) Pressure versus Temperature limits during Heatup, Cooldown and Hydrostatic/Class 1 Leak Testing;

2. RCS Heatup and Cooldown rates;

3. Reactor Pressure Vessel (RPV) to RCS coolant AT requirements during Recirculation Pump startups;

4. RPV bottom head coolant temperature to RPV coolant temperature AT requirements during Recirculation Pump startups;

5. RPV head flange bolt-up temperature limits.

This report has been prepared in accordance with the Final Safety Evaluation for Boiling Water Reactors Owners' Group Licensing Topical Report (LTR) NEDC-33178P, General Electric Methodology for Development of Reactor Pressure Vessel Pressure -Temperature Curves (Reference 6.2) 2.0 Applicability This report is applicable to the LSCS Unit 1 RPV for up to 32 EFPY.

The following Technical Specification is affected by the information contained in this report:

TS 3.4.11 RCS Pressure and Temperature (P/T) Limits Page 3 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits 3.0 Methodology The limits in this report were derived from the NRC-approved GEH LTR methodology (Reference 6.2), using the specific revisions listed below:

1. The neutron fluence was calculated using a combination of NRC approved methods. The first thirteen cycles of fluence were calculated in accordance with BWRVIP-126: BWR Vessel and Internals Project, RAMA Fluence Methodology Software, Version 1.0, EPRI, Palo Alto, CA: 2003, Technical Report 1007823, as approved by the NRC in Reference 6.1.a.

The fluence subsequent to cycle 13 was calculated in accordance with the General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation, NEDC-32983P-A, Revision 2, January 2006, approved in Reference 6.1.b.

2. The pressure and temperature limits were calculated per GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves, NEDC-33178P-A, Revision 1, June 2009, approved in Reference 6.2. The calculation is documented in Reference 6.4.

3. The ISP data from the LaSalle Unit 1 ISP capsule at 120° is contained in BWRVIP-250NP, "Testing and Evaluation of the LaSalle Unit 1 120 0 Surveillance Capsule", EPRI, Palo Alto, CA: 2011, Technical Report 1022850 (Reference 6.3). BWRVIP-250NP was transmitted to the NRC in Reference 6.5. The analysis of this data is documented in Reference 6.9 and in Attachment 7 of this submittal. The results of this testing and analysis, including the revised chemistry factor, are shown in Table B-4 of this submittal.

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

• ISP data

• Application of GEH Topical Report for P/T Curves As mentioned above LSCS Unit 1 participates in the BWRVIP ISP. Unit 1 is a host plant and has removed and tested the 120° capsule. This is the second capsule removed and tested from the LSCS Unit 1 vessel. The 300° capsule Page 4 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits was removed in 1994 and tested (Reference 6.7). The third capsule remains in the vessel, and is a Future ISP (E) Capsule, or an Extended Life Capsule, as classified by BWRVIP-86, Revision 1 (Reference 6.8).

The adjusted reference temperature (ART) values for 32 EFPY included in Appendix B are developed considering the latest ISP published surveillance data available that is representative of the applicable materials in Unit 1. The surveillance data used in the Unit 1 ART calculations is obtained from actual Unit 1 RPV test specimens. The ISP weld material has the limiting ART, and is considered in development of the P/T curves.

4.0 Operating Limits The pressure/temperature (P/T) curves provided in this report represent steam dome pressure versus minimum vessel metal temperature and incorporate the appropriate non-beltline limits and irradiation embrittlement effects in the beltline region.

Complete P/T curves were developed for 32 EFPY. The P/T curves are provided in Figures 1 through 3, and a tabulation of the curves is included in Table 1.

The operating limits for pressure and temperature are required for three categories of operation: (a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatup/cooldown (core not critical), referred to as Curve B; and (c) core critical operation, referred to as Curve C.

Other temperature limits applicable to the RPV are:

• Heatup and Cooldown rate limit during pressure testing (Figure 1:

Curve A): 5 20 °F/hour.

• Normal Operating Heatup and Cooldown rate limit (Figure 2: Curve B Core Not Critical and Figure 3: Curve C Core Critical): 100 °F/hour.

• RPV bottom head coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: 5_ 145 °F.

• Recirculation loop coolant temperature to RPV coolant temperature AT limit during Recirculation Pump startup: 5_ 50 °F.

• RPV flange and adjacent shell temperature limit: 72 °F.

Page 5 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits 5.0 Discussion The fluence must be calculated in accordance with fluence methodologies that comply with Regulatory Guide 1.190, and have been approved by the NRC.

GEH currently has an approved fluence methodology, which is the basis for the existing P/T curves. The BWRVIP analyses are performed using the Radiation Analysis Modeling Application (RAMA) fluence methodology, which is also an NRC approved methodology, but is not the current licensing basis for LaSalle.

The NRC has issued a Safety Evaluation Report for the RAMA methodology (Reference 6.1.a), which contains three conditions that must be met in order to use the methodology:

1. For plants that are similar in core, shroud and downcomer-vessel geometry to that of the Susquehanna and Hope Creek plants, the RAMA Methodology can be applied without a bias for the calculation of vessel fluence;

a. Susquehanna, Hope Creek and LaSalle all contain 764 fuel assemblies, have a shroud with an outside diameter of 207 inches, and have 20 jet pumps in the downcomer area. Therefore, the RAMA methodology can be applied at LaSalle without bias.

2. For plants (or plant groups) with a different geometry than that of the Susquehanna or Hope Creek plants, a plant-specific application for RPV neutron fluence is required to establish the value of a bias, and

a. Since LaSalle is similar to Susquehanna, this condition is not applicable.

3. Relevant benchmarking will be required for shroud and reactor internals applications.

a. LaSalle is using the RAMA methodology for evaluation of the reactor pressure vessel, not the shroud or the internals of the reactor, so this condition is not applicable.

Therefore, the use of the RAMA methodology is endorsed by the NRC and all conditions of their approval have been met.

The computer codes described in References 6.1.a, 6.1.b, and 6.2 were used in the development of the P/T curves for LSCS Unit 1.

Page 6 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits The method for determining the Initial Reference Temperature of Nil-Ductility Transition (RTNDT) for all vessel materials is defined in Section 4.1.2 of Reference 6.2. Initial RTNDT values for all vessel materials considered are presented in Tables B-1, B-2, and B-3 of this report.

For LSCS Unit 1, the surveillance data from the LaSalle 1200 capsule (Reference 6.3), which contained weld heat 1P3571, was utilized in this analysis. The limiting surveillance material, weld heat 1P3571, was considered using Procedure 1 as defined in Appendix I of Reference 6.2. This procedure was used because the vessel material and the surveillance material are identical heats.

For LSCS Unit 1, there are six (6) thickness discontinuities in the vessel:

Discontinuities one through four (1-4) are associated with the Bottom Head Lower to Upper Torus and Bottom Head to Support Skirt; discontinuity 5 is between the Bottom Head to Shell #1, and discontinuity 6 is between Shell #1 and Shell #2.

• The temperature requirement to bound discontinuities 1 through 4 is 113.53°F for the heatup/cooldown transient. The maximum RTNDT for the bottom head is 10°F, and the P/T curves defined in Section 4.3 of Reference 6.2 are based upon a temperature (appropriate for this location) of 137.9°F at 1050 psig.

• The temperature requirement to bound discontinuity 5 is 116.24°F for the heatup/cooldown transient. The maximum RTNDT for the bottom head and Shell #1 is 23°F, and the P/T curves defined in Section 4.3 of Reference 6.2 are based upon a temperature (appropriate for this location) of 137.9°F at 1050 psig.

• The temperature requirement to bound discontinuity 6 is 140.24°F for the heatup/cooldown transient. The maximum RTNDT for Shell #1 and Shell #2 is 80°F, and the P/T curves defined in Section 4.3 of Reference 6.2 are based upon a temperature (appropriate for this location) of 188.1°F at 1050 psig.

Therefore, the temperatures used in the development of the P/T curves bound the temperatures associated with the thickness discontinuities.

The adjusted reference temperature (ART) of the limiting beltline material is used to adjust the beltline P/T curves to account for irradiation effects. Regulatory Page 7 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Guide 1.99, Revision 2 (RG 1.99) provides the methods for determining the ART.

The RG 1.99 methods for determining the limiting material and adjusting the P/T curves using ART are discussed in this section.

The vessel beltline copper and nickel values, except for weld EAIB on the Low Pressure Coolant Injection (LPCI or N6) nozzles, were obtained from Certified Material Test Reports (CMTRs). The copper content of weld EAIB in the N6 nozzles was based on BWR fleet and RVID data for SMAW materials using 83 unique data points and Mean +2cr methodology. With the exception of weld 1P3571, the copper and nickel values were used with Tables 1 and 2 of RG 1.99 to determine a chemistry factor (CF) per Paragraph 1.1 of RG 1.99 for welds and plates respectively. For weld 1P3571, the adjusted CF was calculated using the fitted chemistry factor obtained from Reference 6.9. The water level instrumentation (WLI or N12) nozzle is fabricated from Alloy 600 material that does not require evaluation for fracture toughness, and was evaluated using the limiting material properties (chemistry and initial RTNDT) of the adjoining plate heats.

The P/T curves for the non-beltline region were conservatively developed for a Boiling Water Reactor Product Line 6 (BWR/6) with nominal inside diameter of 251 inches. The analysis is considered appropriate for LSCS Unit 1 because the plant-specific geometric values are bounded by the generic analysis for the large BWR/6. The generic value was adapted to the conditions at LSCS using plant-specific RTNDT values for the reactor pressure vessel.

The peak RPV ID fluence used in the P/T curve evaluation for Unit 1 at 32 EFPY is 8.34E17 n/cm2. The fluence values were calculated using methods that comply with the guidelines of RG 1.190, (as discussed in References 6.1.a and 6.1. b).

The fluence is adjusted for the lower plates and associated welds based upon an attenuation factor of 0.45; hence, the peak ID surface fluence for these components is 3.76E17 n/cm2.

The fluence is adjusted for the N6 nozzle (LPCI nozzle) based upon an attenuation factor of 0.376; hence the peak ID surface fluence used for this component is 3.14E17 n/cm2.

Page 8 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits The same method is applied to the N12 nozzle (Instrumentation nozzle), which has an attenuation factor of 0.287, resulting in a peak ID surface fluence of 2.39E17 n/cm2.

The P/T curves for the heatup and cooldown operating conditions at a given EFPY apply for both the 1/4T and 3/4T locations. When combining pressure and thermal stresses, it is usually necessary to evaluate stresses at the 1/4T location (inside surface flaw) and the 3/4T location (outside surface flaw). This is because the thermal gradient tensile stress of interest is in the inner wall during cooldown and the outer wall during heatup. However, as a conservative simplification, the thermal gradient stress at the 1/4T location is assumed to be tensile for both heatup and cooldown. This results in the approach of applying the maximum tensile stress at the 1/4T location. This approach is conservative because irradiation effects cause the allowable toughness, K1,., at 1/4T to be less than that at 3/4T for a given metal temperature. This approach causes no operational difficulties, since the BWR is at steam saturation conditions during normal operation, well above the heatup/cooldown curve limits.

For the core not critical curve (Curve B) and the core critical curve (Curve C), the P/T curves specify a coolant heatup and cooldown temperature rate of 100°F/hr for which the curves are applicable. However, the core not critical and the core critical curves were also developed to bound transients defined on the RPV thermal cycle diagram and the nozzle thermal cycle diagrams. For the hydrostatic pressure and leak test curve (Curve A), a coolant heatup and cooldown temperature rate of 20°F/hr must be maintained. The P/T limits and corresponding heatup/cooldown rates of either Curve A or B may be applied while achieving or recovering from test conditions. Curve A applies during pressure testing and when the limits of Curve B cannot be maintained.

For LSCS Unit 1, weld 1P3571 is the limiting material for the beltline region for 32 EFPY. The initial RTNDT for weld 1P3571 is -30°F. The generic pressure test P/T curve is applied to the LSCS Unit 1 beltline curve by shifting the P vs. (T - RTNDT) values to reflect the ART value of 116°F for 32 EFPY. Using the fluence discussed above, the P/T curves are beltline limited above 610 psig for Curve A, and above 440 psig for Curve B.

In order to ensure that the limiting vessel discontinuity has been considered in the development of the P/T curves, the methods in Sections 4.3.2.1 and 4.3.2.2 Page 9 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits of Reference 6.2 for the non-beltline and beltline regions, respectively, are applied.

6.0 References 6.1.a Letter from William. H. Bateman (U.S. NRC) to Bill Eaton (BWRVIP),

"Safety Evaluation of Proprietary EPRI Reports BWRVIP-114, 115, 117, and 121 and TWE-PSE-001-R-001", dated May 13, 2005.

6.1.b Final Safety Evaluation Regarding Removal of Methodology Limitations for NEDC-32983P-A, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation (TAC NO. MC3788), November 17, 2005.

6.2 Final Safety Evaluation for Boiling Water Reactors Owners' Group Licensing Topical Report NEDC-33178P, General Electric Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves (TAC NO. MD2693),

April 27, 2009.

6.3 BWRVIP-250NP, "Testing and Evaluation of the LaSalle Unit 1 120 0 Surveillance Capsule", EPRI, Palo Alto, CA: 2011, Technical Report 1022850.

6.4 "Pressure-Temperature Limits Report for Exelon Nuclear, LaSalle County Station Unit 1", 0000-0148-2850-R2, Revision 2, January 2013.

6.5 Letter 2011-206 from Dave Czufin, Chairman, BWR Vessels and Internals Project, to Document Control Desk, Project No. 704 BWRVIP-250NP: BWR Vessel and Internals Project, Testing and Evaluation of the LaSalle Unit 1 120° Surveillance Capsule, EPIR Technical Report 1022850, October 2011.

6.6 Letter RA13-002 from Peter J. Karaba, Site Vice President, LaSalle County Station, to Document Control Desk, Evaluation of LaSalle County Station Unit 1 120° Capsule Surveillance Data, January 10, 2013 6.7 "LaSalle Unit 1 RPV Surveillance Materials Testing and Analysis", GE-NE-523-A166-1294, Revision 1, June 1995, as filed in L-002872.

6.8 BWRVIP-86, Revision 1, "Updated BWR Integrated Surveillance Program (ISP) Implementation Plan", EPRI, Palo Alto, CA: 2008, Technical Report 1016575.

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EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits 6.9 BWRVIP Letter 2012-026, "Evaluation of the LaSalle Unit 1 120 0 Surveillance Capsule Data", to Ms. JoAnn Shields, Exelon Corporation from Bob Carter, EPRI, BWRVIP Assessment Task Manager, dated January 10, 2012.

6.10 BWRVIP-135, Revision 2, "Integrated Surveillance Program, Data Source Book and Plant Evaluations", Final Report, October 2009, Technical Report 1020231.

Page 11 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Figure 1 Bottom Head and Composite (Upper Vessel & Beltline) Pressure Test P/T Curves [Curve A] up to 32 EFPY [20°F/hr or less coolant heatup/cooldown]

1400 i

I t

1300 INITIAL RTNDT VALUES

/

1 ARE II -30°F FOR BELTLINE, 1200 42°F FOR UPPER VESSEL, AND 1100 1 47°F FOR BOTTOM HEAD 17) a 1000 LU BELTLINE CURVES 900 ADJUSTED AS SHOWN:

a_ EFPY SHIFT (°F) 32 146 w 800 co LU cc 700 0

HEATUP/COOLDOWN RATE OF COOLANT

• 600 -.- < 20°F/HR cc 1-E 500 BOTTOM -

HEAD LU 68°F cc 400 ---1 co LU a_

• 300 -1 312 PSIG FLANGE REGION UPPER VESSEL AND 200 BELTLINE LIMITS 72°F 100 BOTTOM HEAD CURVE 0

0 25 50 75 100 125 150 175 200 225 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)

Page 12 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Figure 2 Bottom Head and Composite (Upper Vessel & Beltline) Core Not Critical PIT Curves [Curve 6] up to 32 EFPY [100°F/hr or less coolant heatup/cooldown]

1400 1300 INITIAL RTND, VALUES 1200 ARE

-30°F FOR BELTLINE, 42°F FOR UPPER VESSEL, AND 1100 47°F FOR BOTTOM HEAD 17) a 1000 LU 900 BELTLINE CURVES a ADJUSTED AS SHOWN:

0 EFPY SHIFT (°F) 32 146 Lu 800 LU ce 700 0

HEATUP/COOLDOWN RATE OF COOLANT 600 < 100°F/HR 2 500 LU re 3

ci) 400 LU re BOTTOM

a. HEAD 312 PSIG 300 68°F 200 UPPER VESSEL AND BELTLINE LIMITS FLANGE REGION 100 72°F BOTTOM HEAD CURVE 0

0 25 50 75 100 125 150 175 200 225 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)

Page 13 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Figure 3 Composite Core Critical PIT Curves [Curve C] up to 32 EFPY

[100°F/hr or less coolant heatup/cooldown]

1400 -

INITIAL RTNDT VALUES 1300 ARE

-30°F FOR BELTLINE, 42°F FOR UPPER 1200 VESSEL, AND 47°F FOR BOTTOM HEAD 1100 ri) l000 BELTLINE CURVE ADJUSTED AS SHOWN.

EFPY SHIFT (°F) uJ 32 146 900 a-0

-J 800 HEATUP/COOLDOWN co Lii RATE OF COOLANT

< 100°F/HR re 700 0

• 600 g 500 re co) 400 a_

300 312 PSIG 200

.BELTLINE AND NON-100 Minimum Vessel BELTLINE LIMITS Temperature 72°F 0

0 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTOR VESSEL METAL TEMPERATURE (°F)

Page 14 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits TABLE 1. LSCS Unit 1 Composite P/T Curve Values for 32 EFPY Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE AT HEAD BELTLINE AT LIMITING 32 EFPY 32 EFPY 32 EFPY PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (°F) (°F) (°F) (°F) (°F) 0 68.0 72.0 68.0 72.0 72.0 10 68.0 72.0 68.0 72.0 72.0 20 68.0 72.0 68.0 72.0 72.0 30 68.0 72.0 68.0 72.0 72.0 40 68.0 72.0 68.0 72.0 72.0 50 68.0 72.0 68.0 72.0 73.1 60 68.0 72.0 68.0 72.0 82.0 70 68.0 72.0 68.0 72.0 89.2 80 68.0 72.0 68.0 72.0 95.2 90 68.0 72.0 68.0 72.0 100.3 100 68.0 72.0 68.0 72.0 104.8 110 68.0 72.0 68.0 72.0 108.9 120 68.0 72.0 68.0 72.7 112.7 130 68.0 72.0 68.0 76.2 116.2 140 68.0 72.0 68.0 79.4 119.4 150 68.0 72.0 68.0 82.2 122.2 160 68.0 72.0 68.0 84.9 124.9 170 68.0 72.0 68.0 87.5 127.5 180 68.0 72.0 68.0 89.9 129.9 190 68.0 72.0 68.0 92.2 132.2 200 68.0 72.0 68.0 94.3 134.3 210 68.0 72.0 68.0 96.3 136.3 220 68.0 72.0 68.0 98.3 138.3 230 68.0 72.0 68.0 100.1 140.1 240 68.0 72.0 68.0 101.9 141.9 250 68.0 72.0 68.0 103.6 143.6 260 68.0 72.0 68.0 105.2 145.2 270 68.0 72.0 68.0 106.8 146.8 280 68.0 72.0 68.0 108.3 148.3 290 68.0 72.0 68.0 109.8 149.8 300 68.0 72.0 68.0 111.2 151.2 310 68.0 72.0 68.0 112.5 152.5 Page 15 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits TABLE 1. LSCS Unit 1 Composite P/T Curve Values for 32 EFPY Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE AT HEAD BELTLINE AT LIMITING 32 EFPY 32 EFPY 32 EFPY PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (°F) (°F) (°F) (°F) (°F) 312.5 68.0 72.0 68.0 112.9 152.9 312.5 68.0 102.0 68.0 132.0 172.0 320 68.0 102.0 68.0 132.0 172.0 330 68.0 102.0 68.0 132.0 172.0 340 68.0 102.0 68.0 132.0 172.0 350 68.0 102.0 68.0 132.0 172.0 360 68.0 102.0 68.0 132.0 172.0 370 68.0 102.0 68.0 132.0 172.0 380 68.0 102.0 68.0 132.0 172.0 390 68.0 102.0 68.0 132.0 172.0 400 68.0 102.0 68.0 132.0 172.0 410 68.0 102.0 68.0 132.0 172.0 420 68.0 102.0 68.0 132.0 172.0 430 68.0 102.0 68.0 132.0 172.0 440 68.0 102.0 68.0 132.0 172.0 450 68.0 102.0 68.0 133.7 173.7 460 68.0 102.0 68.0 135.3 175.3 470 68.0 102.0 69.6 136.9 176.9 480 68.0 102.0 72.1 138.4 178.4 490 68.0 102.0 74.4 139.9 179.9 500 68.0 102.0 76.6 141.3 181.3 510 68.0 102.0 78.8 142.7 182.7 520 68.0 102.0 80.8 144.0 184.0 530 68.0 102.0 82.8 145.3 185.3 540 68.0 102.0 84.7 146.6 186.6 550 68.0 102.0 86.5 147.9 187.9 560 68.0 102.0 88.3 149.1 189.1 570 68.0 102.0 90.0 150.3 190.3 580 68.0 102.0 91.6 151.5 191.5 590 68.0 102.0 93.2 152.6 192.6 600 68.0 102.0 94.8 153.7 193.7 610 68.0 102.0 96.3 154.8 194.8 Page 16 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits TABLE 1. LSCS Unit 1 Composite P/T Curve Values for 32 EFPY Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE AT HEAD BELTLINE AT LIMITING 32 EFPY 32 EFPY 32 EFPY PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (°F) (°F) (°F) (°F) (°F) 620 68.0 104.3 97.7 155.9 195.9 630 68.0 106.4 99.1 156.9 196.9 640 68.0 108.5 100.5 157.9 197.9 650 68.0 110.5 101.8 158.9 198.9 660 68.0 112.4 103.1 159.9 199.9 670 68.0 114.3 104.4 160.9 200.9 680 68.0 116.1 105.7 161.8 201.8 690 68.0 117.8 106.9 162.7 202.7 700 68.0 119.4 108.0 163.6 203.6 710 68.7 121.1 109.2 164.5 204.5 720 70.1 122.6 110.3 165.4 205.4 730 71.5 124.1 111.4 166.3 206.3 740 72.8 125.6 112.5 167.1 207.1 750 74.1 127.0 113.6 168.0 208.0 760 75.4 128.4 114.6 168.8 208.8 770 76.6 129.8 115.6 169.6 209.6 780 77.8 131.1 116.6 170.4 210.4 790 79.0 132.4 117.6 171.2 211.2 800 80.2 133.6 118.5 171.9 211.9 810 81.3 134.8 119.5 172.7 212.7 820 82.4 136.0 120.4 173.4 213.4 830 83.5 137.2 121.3 174.2 214.2 840 84.5 138.3 122.2 174.9 214.9 850 85.6 139.4 123.0 175.6 215.6 860 86.6 140.5 123.9 176.3 216.3 870 87.6 141.6 124.7 177.0 217.0 880 88.5 142.6 125.6 177.7 217.7 890 89.5 143.6 126.4 178.4 218.4 900 90.4 144.6 127.2 179.0 219.0 910 91.4 145.6 128.0 179.7 219.7 920 92.3 146.6 128.7 180.3 220.3 930 93.1 147.5 129.5 181.0 221.0 Page 17 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits TABLE 1. LSCS Unit 1 Composite P/T Curve Values for 32 EFPY Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE AT HEAD BELTLINE AT LIMITING 32 EFPY 32 EFPY 32 EFPY PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (OF) (°F) (°F) (°F) (°F) 940 94.0 148.4 130.3 181.6 221.6 950 94.9 149.3 131.0 182.2 222.2 960 95.7 150.2 131.7 182.9 222.9 970 96.6 151.1 132.5 183.5 223.5 980 97.4 152.0 133.2 184.1 224.1 990 98.2 152.8 133.9 184.7 224.7 1000 99.0 153.6 134.6 185.3 225.3 1010 99.7 154.5 135.2 185.8 225.8 1020 100.5 155.3 135.9 186.4 226.4 1030 101.3 156.1 136.6 187.0 227.0 1035 101.6 156.5 136.9 187.3 227.3 1040 102.0 156.8 137.2 187.5 227.5 1050 102.7 157.6 137.9 188.1 228.1 1055 103.1 158.0 138.2 188.4 228.4 1060 103.4 158.4 138.5 188.6 228.6 1070 104.2 159.1 139.1 189.2 229.2 1080 104.9 159.8 139.8 189.7 229.7 1090 105.6 160.6 140.4 190.3 230.3 1100 106.2 161.3 141.0 190.8 230.8 1105 106.6 161.6 141.3 191.0 231.0 1110 106.9 162.0 141.6 191.3 231.3 1120 107.6 162.7 142.2 191.8 231.8 1130 108.2 163.4 142.8 192.3 232.3 1140 108.9 164.0 143.3 192.8 232.8 1150 109.5 164.7 143.9 193.3 233.3 1160 110.1 165.4 144.5 193.8 233.8 1170 110.8 166.0 145.0 194.3 234.3 1180 111.4 166.7 145.6 194.8 234.8 1190 112.0 167.3 146.1 195.3 235.3 1200 112.6 167.9 146.7 195.8 235.8 1210 113.2 168.5 147.2 196.2 236.2 1220 113.8 169.1 147.8 196.7 236.7 Page 18 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits TABLE 1. LSCS Unit 1 Composite P/T Curve Values for 32 EFPY Required Metal Temperature with Required Coolant Temperature Rate at 100 °F/hr for Curves B & C and 20 °F/hr for Curve A BOTTOM UPPER RPV & BOTTOM UPPER RPV &

HEAD BELTLINE AT HEAD BELTLINE AT LIMITING 32 EFPY 32 EFPY 32 EFPY PRESSURE CURVE A CURVE A CURVE B CURVE B CURVE C (PSIG) (°F) (OF) (°F) (°F) (°F) 1230 114.3 169.7 148.3 197.2 237.2 1240 114.9 170.3 148.8 197.6 237.6 1250 115.5 170.9 149.3 198.1 238.1 1260 116.0 171.5 149.8 198.5 238.5 1270 116.6 172.1 150.3 199.0 239.0 1280 117.1 172.6 150.8 199.4 239.4 1290 117.7 173.2 151.3 199.9 239.9 1300 118.2 173.8 151.8 200.3 240.3 1310 118.7 174.3 152.3 200.7 240.7 1320 119.3 174.9 152.8 201.2 241.2 1330 119.8 175.4 153.2 201.6 241.6 1340 120.3 175.9 153.7 202.0 242.0 1350 120.8 176.4 154.2 202.4 242.4 1360 121.3 177.0 154.6 202.8 242.8 1370 121.8 177.5 155.1 203.2 243.2 1380 122.3 178.0 155.5 203.6 243.6 1390 122.8 178.5 156.0 204.0 244.0 1400 123.3 179.0 156.4 204.4 244.4 Page 19 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Appendix A: Reactor Vessel Material Surveillance Program In accordance with 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, the first surveillance capsule was removed from the LSCS Unit 1 reactor vessel in Spring 1994. The 300° surveillance capsule contained flux wires for neutron fluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel materials within the core beltline region. The flux wires and test specimens removed from the capsule were tested according to ASTM E 185-82. The methods and results of testing were documented in Reference 6.7, and the irradiated Charpy data results were within the predicted values using Regulatory Guide 1.99 Revision 2. The flux wire results were used to estimate 32 EFPY fluence, and the resulting estimate was approximately 6% lower than the previous estimate of 32 EFPY fluence.

In accordance with 10 CFR 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements, the second surveillance capsule was removed from the LSCS Unit 1 reactor vessel in February 2010, during refueling outage (RFO) 13. The 120° surveillance capsule also contained flux wires for neutron fluence measurement, Charpy V-Notch impact test specimens and uniaxial tensile test specimens fabricated using materials from the vessel materials within the core beltline region. The flux wires and test specimens removed from the capsule were tested according to ASTM E 185-82.

The methods and results of testing are presented in References 6.3 and 6.9, as required by 10 CFR 50, Appendices G and H. These test results necessitated the revision to the Unit 1 P/T curves. The need for revised curves was communicated to the NRC in Reference 6.6.

As described in the LSCS Updated Final Safety Analysis Report (UFSAR)

Section 5.3.1.6.1, Compliance with "Reactor Vessel Material Surveillance Program Requirements" and UFSAR Table 5.2-12, "Reactor Vessel Material Surveillance Program Withdrawal Schedule", the remaining surveillance capsule is slated to be removed as defined by the Integrated Surveillance Program (Reference 6.8).

Page 20 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Appendix B: LSCS Unit 1 Reactor Pressure Vessel PIT Curve Supporting Plant-Specific Information Page 21 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Figure B-1: LSCS Unit 1 Reactor Pressure Vessel TOP HEAD TOP HEAD FLANGE SHELL FLANGE r SHELL #5

/

0 / 0 r

y

,, . y. yiwzymz, .

Pe SHELL #4 e

oee oee ee 0 ,

• .... 1 SHELL #3

. LPCI NOZZLE GIRTH r AXIAL WELDS 3-308 i TOP OF ACTIVE FUEL WELD V Nsri

/ 0 (TAF) 366 31.*

SHELL #2 AXIAL WELDS 4-308 GIRTH WELD BOTTOM OF SHELL #1 z zrzrzrzzrzy/z/zrzzzzrzrzizzrzrzrzzi,,,;

ACTIVE FUEL (BAF) 216 31" /

/

• '. 0 0 0 0

AXIAL WELDS 2-307 BOTTOM HEAD SUPPORT SKIRT Page 22 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Table B-1: LSCS Unit 1 Initial RTNDT Values for RPV Materials PI Plate and Flange Materials TEST DROP ENERGY (Ts.-60) IN I NOT RT NDT COMPONENT HEAT TEMP. =, WEIGHT

(*F) ( NOT 1°' '

PLATES & FORGINGS:

Top Head & Flange:

Vessel Flange, 308-02 2V-659 ATF-112 10 70 68 97 -20 10 10 Closure Flange, 319-02 ACT-USS-4P-1997 Ser.118 10 92 110 91 -20 10 10 Dome, 319-05 07434-1 10 65 76 67 -20 -10 -10 Upper Torus, 319-04 C7434-1 10 65 76 67 -20 -10 -10 Lower Torus. 319-03 C7376-2 10 65 74 73 -20 -10 -10 Shell Courses:

Upper Shell 05987-1 10 63 55 35 10 -10 10 305-04 C5987-2 10 76 79 51 -20 -10 -10 06003-2 40 65 49 50 12 10 12 Upper Int. Shell 05996-2 10 62 71 66 -20 -10 -10 305-04 C5979-2 10 64 63 49 -18 -10 -10 05996-1 10 65 60 77 -20 -10 -10 Middle Shell A5333-1 10 56 67 53 -20 -10 -10 305-03 90078-1 10 73 49 70 -18 -10 -10 06123-2 10 77 60 73 -20 -10 -10 Low-Int. Shell 06345-1 10 109 88 77 -20 -40 -20 305-02 C6318-1 10 80 66 72 -20 -20 -20 C6345-2 10 93 94 67 -20 -40 -20 Lower Shell 05978-1 40 53 48 48 14 10 14 305-01 C5978-2 40 62 60 41 28 -10 23*

C5979-1 40 73 92 65 10 -10 10 Bottom Head:

Bottom Head Dome, 306-17 06003-3 40 36 39 40 38 40 47" Lower Torus C5540-1 10 54 78 82 -20 -10 -10 306-18 C5328-1 40 64 51 51 10 -10 10 C5328-2 40 55 62 59 10 -10 10 Upper Torus C5505-2 10 63 96 73 -20 -10 -10 306-19 C5445-3 10 70 67 70 -20 -10 -10 Support Skirt:

309-08 5P2003 Ser.201 10 81 74 103 -20 40 40 309-06 81042-3 10 70 61 68 -20 10 10 309-04 C7159-4 40 28 25 34 60 60 60 STUDS: LST Closure Head Studs, 32-01 14716 10 45 43 43 70 Closure Nut/Washers, 326-02/03 24632 10 38 36 39 70

• Value of RTNDT was obtained from semi curve-fit calculation using CMTR data.

• Value of RT50 is obtained from curve-fit of CMTR data NOTE [1]: These are minimum Charpy values.

Page 23 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Table B-2: LSCS Unit 1 Initial RTNDT Values for RPV Materials [1]

Nozzles and Stabilizer Bracket TEST DROP CHARPY ENERGY (150T-60) rc INDT COMPONENT HEAT TEMP. WEIGHT (FT-LB) (°F) CT)

(°F) NDT NOZZLES:

Recirc. Outlet Nozzle AV5840-0K9380 10 73 84 65 -20 0 0 314-02 AV5840-0K9381 10 56 84 80 -20 10 10 Recirc. Inlet Nozzle Q2C114VW-175W 10 30 30 43 20 40 40 314-07 Q2Q6VW-175W 10 34 36 39 12 40 40 Steam Outlet Nozzles AV4276-919074 10 44 62 42 -4 30 30 316-07 AV4279-9I9236 10 84 55 80 -20 30 30 AV4442-9J9176 10 93 97 82 -20 30 30 AV4274-9H9176 10 69 100 71 -20 30 30 Feedwater Nozzle, 316-02 Q2Q14VVV-174W-1/6 10 48 72 60 -16 40 40 Core Spray Nozzle AV4067-9H9168 10 79 70 71 -20 30 30 316-12 AV4068-9H9169 10 45 35 76 10 30 30 RHR/LPC1 Nozzles, 316-17 Q2Q22W-569F-1/3 10 44 44 37 6 10 10 CDR Hydro Return Nozzle, 315-10 AV3142-9G9640 10 34 30 44 20 30 30 Jet Pump Nozzles, 314-12 AV3138-9F-92316/C 10 116 90 96 -20 30 30 Closure Head Inst. Nozzle, 318-07 Q2Q23W-346J-1A 10 35 47 31 18 30 30 Vent Nozzle, 318-02 Q2Q24W-345J 10 78 109 122 -20 10 10 Drain Nozzle, 315-14 Q1Q1VW-738T 10 39 25 32 30 30 30 Stabilizer Bracket, 324-19 C4943-3 10 36 35 36 10 10 10 NOTE [1]: These are minimum Charpy values.

Page 24 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Table B-3: LSCS Unit 1 Initial RTNDT Values for RPV Materials 111 Welds TEST DROP CHARPY ENERGY (T50 T-60) rc I Nor COMPONENT HEAT TEMP. WEIGHT (FT-LB) (°F) (°F)

(°F) NDT WELDS:

Vertical Welds:

2-307 Bottom Shell Long Seams 21935-1092-3889 10 97 90 83 -50 -50 -50 1-308 Upper Shell Long Seams 2-308 Upper Inter. Shell Long Seams 1-308 Upper Shell Long Seams 12008-1092-3889 10 97 90 83 -50 -50 -50 2-307 Bottom Shell Long Seams 1-308 Upper Shell Long Seams 305424-1092-3889 10 82 87 92 -50 -50 -50 3-308 Middle Shell Long Seams 3-308 Middle Shell Long Seams IP3571-1092-3958 10 40 46 46 -30 -50 -30 4-308 Lower Inter. Shell Long Seams 305414-1092-3947 10 82 66 80 -50 -50 -50 4-308 Lower Inter. Shell Long Seams 12008-1092-3947 10 92 91 92 -50 -50 -50 1-319 Closure Head Seg. Lower Torus FOAA 10 125 124 130 -50 -50 -50 2-319 Closure Head Seg. Upper Torus 1-319 Closure Head Seg. Lower Torus EAIB 10 118 129 107 -50 -50 -50 Girth Welds:

3-306 Bottom Hd. Build up for sup. Skirt 305414-1092-3951 10 66 61 62 -50 -50 -50 5-306 Bottom Hd. Dome to Side Seg, 6-306 Bottom Hd. Low. To Up Side Seg.

6-306 Bottom Hd. Low. To Up Side Seg. 305424-1092-3889 10 82 87 92 -50 -50 -50 4-307 Inlay in Bot. Sd for Core Sup Attch.

9-307 Bottom Head to Lower Shell 10120-0091-3458 10 124 130 122 -50 -50 -50 3-319 Close. Hd. Torus to Close. Hd. Fig.

9-307 Bottom Head to Lower Shell 51874-0091-3458 10 89 64 87 -50 -50 -50 3-319 Close. Hd. Torus to Close. Hd. Fig.

6-308 Upper Vessel Shell Girth Seam 9-307 Bottom Head to Lower Shell 51912-0091-3490 10 93 84 92 -50 -50 -50 6-308 Upper Vessel Shell Girth Seam 10137-0091-3999 10 101 108 107 -50 -50 -50 15-308 Flange to Upper Shell 6-308 Upper Vessel Shell Girth Seam 5P5622-0091-0831 -20 95 87 86 -80 -so -ao 6-308 Upper Vessel Shell Girth Seam 2P5755-0091-0831 -10 81 80 82 -70 -70 -70 6-308 Upper Vessel Shell Girth Seam 6329637-0091-3458 10 103 65 88 -50 -50 -50 6-308 Upper Vessel Shell Girth Seam 6329637-0091-3999 10 101 108 103 -50 -50 -50 15-308 Flange to Upper Shell 5-319 Closure Hd, Upper Torus to Dome 4-309 Support Skirt Forging to Bot Hd. 90099-0091-3977 10 96 97 89 -50 -50 -50 4-309 Support Skirt Forging to Bot. Hd. 90136-0091-3998 10 110 109 107 -50 -50 -50 1-313 Up. Assy to Lower Closing Seams 4P6519-0091-0145 0 98 101 102 -60 -60 -60 1-313 Up. Assy to Lower Closing Seams 4P6519-0091-0842 0 46 59 48 -52 -80 -52 1-313 Up. Assy to Lower Closing Seams 4P6519-0091-0653 -40 57 63 73 -100 -60 -60 4-319 Close. Hd. Upper Torus to Lower 606L40-0091-3489 10 96 95 77 -50 -50 -50 NOTE [1]: These are minimum Charpy values.

Page 25 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Table B-3 continued: LSCS Unit 1 Initial RTNDT Values for RPV Materials [1]

Welds Drop Test Heat or Heat! Flux Charpy Energy (T50r60) Weight RTNor Component Temp

/Lot (ft-lb) (°F) NDT (°F)

(°F)

(°F)

Beltline Nozzle Welds N6 LPCI Nozzle Weld ABEA 10 101 117 98 -50 - -50 N6 LPCI Nozzle Weld FAGA 10 120 117 116 -50 -50 N6 LPCI Nozzle Weld CCJA 10 95 98 96 -50 - -50 N6 LPCI Nozzle Weld FOAA 10 125 124 130 -50 - -50 N6 LPCI Nozzle Weld EAIB 10 111 88 84 -50 - -50 NOTE [1]: These are minimum Charpy values.

Page 26 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Table B-4: LSCS Unit 1 Beltline Adjusted Reference Temperatures, 32 EFPY Lower Plate and Welds 2-307 & 1.313 Thickness in inches= 7 13 32 EFPY Peak I D. licence = 3 76E+17 nice 32 EFPY Peak 1/4 T fiuence = 2.45E+17 nice Lower-Intermediate Plates and Welds 4-308 Thickness in inches= 6 13 32 EFPY Peak ID uence = 8.34E+17 nice 32 EFPY Peak 1/4 T licence = 5 77E+17 nice Middle Plates and Welds 3-308 & 6-308 Thickness in inches= 6.13 32 EFPY Peak ID uence = 6 22E+17 nice 32 EFPY Peak 1/4 T fluence = 4 31E+17 nice NO LPCI Nozzle Thickness in inches= 6.13 32 EFPY Peak ID uence = 3.14E+17 n/ce 32 EFPY Peak 1/4 T fiuence = 217E+17 nice N12 Water Level Instrumentation Nozzle Thickness in inches= 6 13 32 EFPY Peak I.D licence = 2.39E+17 nice 32 EFPY Peak 1/4 T fiuence = 1 65E+17 nice Initial Peak 1/4 T 32 EFPY 32 EFPY 32 EFPY COMPONENT HEAT %Cu %NI CF RINDT Fluenoe Fluenoeili G RTNor

• so Margin Shift ART

°F Won 2 n/Øm 2 *F °F °F °F I

PLATES:

Lower Shell Assembly 307-04 G-5603-1 C5978-1 011 0.58 74 14 376E217 245E-+17 14 7 14 00.

29 43 G-5603-2 C5978.2 0.11 059 74 23 3766+17 2 45E+17 14 7 14 29 52 G-5603-3 C5976-1 012 066 84 10 3 76E+17 245E.17 16 8 16 33 43 Lower-Intermediate Shell Assembly 308-06 0000 00 G-5604-1 C6345.1 015 0.49 104 -20 8 34E+17 5776+17 33 16 33 66 46 G-5604-2 C6318-1 012 051 81 -20 8.34E+17 5.77E+17 26 13 26 51 31 G-5604-3 C6345-2 0.15 0.51 105 -20 8 34E+17 5776+17 33 17 33 66 46 Middle Shell Assembly 308-06 G-5605-1 A5333-1 0.12 054 82 -10 6 22E+17 4 31E+17 22 11 22 44 34 G-5605-2 60078-1 0.15 050 105 -10 6.22E+17 4 31E+17 28 14 28 56 46 G-5605.3 C6123-2 0.13 0.68 93 -10 6 22E+17 4.31E+17 25 13 25 50 40 WELDS:

Girth 1-313 4P6519 0.131 006 64 -52 3 76E+17 2.45E+17 12 0 6 12 25 -27 6-308 6329637 0 205 0 105 98 -50 6 22E+17 4316=17 27 0 13 27 53 3 Lower 2-307A, B. C 21935/3889 0 183 0.704 172 -50 3 76E+17 245E+17 34 0 17 34 67 17 2-307 A 8, C 12008/3889 0.235 0.975 233 -50 3.76E+17 2 45E+17 45 0 23 45 91 41 2-307A B C 21935& 12008 Tandem 0.213 0 867 209 -50 3 76E+17 245E+17 41 0 20 41 81 31 Lower-Intermediate 4-308 A, B, C 305414/3947 0 337 0 609 209 -50 8 34E+17 5776+17 66 0 28 56 122 72 4-308A B, C 12008/3947 0 235 0 975 233 -50 834E+17 577E=17 74 0 28 56 130 80 4-308 A. B. C 305414 & 12008 Tandem 0.286 0 792 219 -50 8 34E+17 5.77E+17 69 0 28 56 125 75 Middle 3-308 A, B, C 305424/3889 0.273 0.629 1095 -50 6 22E+17 4316+17 51 0 26 51 102 52 3-308A B, C 1P3571/3958 0.283 0.755 212 -30 622E+17 4.31E+17 57 0 28 56 113 83 NOZ71-ESP1:

N6 LPCI Nozzle Q2C122W 010 0.82 67 10 3.14E+17 2176+17 12 0 6 12 24 34 N12 Water Level Instrumentation Nozzle G-5605-1 A5333-1 012 054 82 -10 2 39E+17 1.65E+17 12 0 6 12 25 15 G-5605-2 130078-1 0.15 0.50 105 .10 2 39E+17 1 65E+17 16 0 8 16 32 22 G-5605-3 C6123.2 0.13 068 93 -10 239E+17 1 65E+17 14 0 7 14 28 18 NE LPCI Nozzle Weld?'

ABEA 0.04 098 54 -50 3.14E+17 2 17E+17 10 0 5 10 20 -30 FAGA 0.03 095 41 -50 3 14E+17 2176217 7 0 4 7 15 .35 CCJA 002 086 27 -50 3.14E+17 217E17 5 0 2 5 10 -40 FOAA 0.03 1.00 41 -50 3.14E+17 2 17E+17 7 0 4 7 15 -35 EAIB 0 12 l't 086 155 -50 3.14E+17 2.17E+17 28 0 14 28 56 6 N12 Water Level Instrumentation Nozzle Weld131 Alloy 600 BEST ESTIMATE CHEMISTRIES Plate N/A Weld N/A INTEGRATED SURVEILLANCE PROGRARO Platelq C6345-1 0 14 054 152 4 -20 8.34E+17 5.77E+17 48 0 65 17 65 45 Weld's) 1P3571 0.21 0.75 437 -30 622E=17 4 31E+17 118 0 14 28 146 116

[1) Fluence robes for LaSalle Unit 1 for 102% EPU condition

[2) NI3 LPCI Nozzle Weld chemistry values are obtained from LaSalle Unit 1 CMTRs. The test temperature. Tun = 10°F and there is no drop weight temperature. The following equation was used to calculate the initial RTNDT : Ty3T - 60°F = 10°F - 60°F = -50

[3) The N12 Water Lei.el Instrumentation Nozzle Weld material for LaSalle Unit us Ni-Cr-Fe. Alloy 600. Since material is Alloy 600 no fracture toughness valuation is required

[4] Values are from BVVRVIP.135 R2.

[5] Since the 1SP plate material is not the same as the plant-specific material, the CF should be determined by RG 1.99 Rev 2. However, the 1SP plate material is within the extended beltline and there are two irradiated data sets. Therefore. the ISP data prodded in Reference 6.9 should be considered in the ART determination for the LaSalle 1 plate heat.

[6) Since the 1SP weld matetial is the same as the plant-specific material, the 120° sur.eillance capsule data is included in the limiting ART calculations The adjusted CF is calculated using the Bled CF obtained from EPRI letter 2012-026.

[7) Both the plate and weld matenals are added for the fracture toughness ei.eluation of N6 LPCI and 1412 WLI nozzles.

[8] BWR feet and RVID data for SMAW materials was used to obtain the copper content. considering 83 unique data points and Mean Page 27 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Table B-5: LSCS Unit 1 RPV Beltline P/T Curve Input Values A = -30 + 146 = 116°F Adjusted RTNDT = Initial RTNDT + Shift (Based on ART values in Table B-4)

Vessel Height H = 863.3 inches Bottom of Active Fuel Height B = 216.3 inches Vessel Radius (to base metal) R = 127.0 inches Minimum Vessel Thickness (without clad) t = 6.13 inches Page 28 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Table B-6: LSCS Unit 1 Definition of RPV Beltline Regionil l Elevation Component (inches from RPV "0")

Shell # 3 - Top of Active Fuel (TAF) 366.3" Shell # 1 - Bottom of Active Fuel (BAF) 216.3" Shell # 3 Top of Extended Beltline Region (32 EFPY) 371.7" Shell # 1 Bottom of Extended Beltline Region (32 EFPY) 211.9" Centerline of Recirculation Outlet Nozzle in Shell # 1 172.5" Top of Recirculation Outlet Nozzle Ni in Shell # 1 197.2 Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0" Top of Recirculation Inlet Nozzle N2 in Shell It 1 197.7" Centerline of 2" Water Level Instrumentation Nozzle in Shell 366.0"

1. 3 Centerline of LPCI Nozzle in Shell #3 372.5" Note [I]: The beltline region is defined as any location where the peak neutron fluence is expected to exceed or equal 1.0E17 n/cm2.

Based on the above, it is concluded that none of the LSCS Unit 1 reactor vessel plates, nozzles, or welds, other than those included in the Adjusted Reference Temperature Table, are in the beltline region.

Page 29 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Appendix C: LSCS Unit 1 Reactor Pressure Vessel PIT Curve Checklist Page 30 of 33

EPRI Non-Proprietary Information LSCS Unit 1 P/T Limits Parameter Completed Comments/Resolutions/Clarifications Initial RTNDT Initial RTNDT has been determined With the exception of weld 4P6519, all for LSCS Unit 1 for all vessel Initial RTNDT values used are consistent materials including plates, flanges, with the NRC Reactor Vessel Integrity forgings, studs, nuts, bolts, welds. Database (RVID) Initial RTNDT values.

For weld 4P6519, the value used was Include explanation (including determined using CMTR data and the methods/sources) of any NRC-approved methodology defined in exceptions, resolution of discrepant Section 4.1.1.3 of the GEH LTR.

data (e.g., deviation from originally reported values).

Appendix B contains tables of all Initial RTNDT values for LSCS Unit 1 Has any non-LSCS Unit 1 initial 0 No.

RTNDT information (e.g., ISP, comparison to other plant) been used?

If deviation from the LTR process occurred, sufficient supporting information has been included (e.g.,

Charpy V-Notch data used to determine an Initial RTNDT).

All previously published Initial RTNDT values from sources such as the GL88-01, RVID, FSAR, etc., have been reviewed.

Adjusted Reference Temperature (ART)

Sigma I (standard deviation for Initial RTNDT) is 0°F unless the RTNDT was obtained from a source other than CMTRs. If al is not equal to 0, reference/basis has been provided.

Sigma A (standard deviation for 1 ARTNDT) is determined per RG 1.99, Rev. 2 Page 31 o133

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Parameter Completed Comments/Resolutions/Clarifications Chemistry has been determined for The chemistry values for copper and all vessel beltline materials including nickel listed for many of the materials plates, forgings (if applicable), and differ from the values listed in RVID, but welds for LSCS Unit 1. in all cases the chemistry values used are consistent with the currently Include explanation (including licensed P/T curve values.

methods/sources) of any exceptions, resolution of discrepant data (e.g., deviation from originally reported values).

Non-LSCS Unit 1 chemistry information (e.g., ISP, comparison to other plant) used has been adequately defined and described.

For any deviation from the LTR process, sufficient information has been included.

All previously published chemistry values from sources such as the GL88-01, RVID, FSAR, etc., have been reviewed.

The fluence used for determination of ART and any extended beltline region was obtained using an NRC-approved methodology.

The fluence calculation provides an axial distribution to allow determination of the vessel elevations that experience fluence of 1.0E17 n/cm2 both above and below active fuel.

The fluence calculation provides an axial distribution to allow determination of the fluence for intermediate locations such as the beltline girth weld (if applicable) or for any nozzles within the beltline region.

All materials within the elevation range where the vessel experiences a fluence .?1.0E17 n/cm2 have been included in the ART calculation. All initial RTNDT and chemistry information is available or explained.

Page 32 of 33

EPRI Non-Proprietary Information LSCS Unit 1 PIT Limits Parameter Completed Comments/Resolutions/Clarifications Discontinuities The discontinuity comparison has been performed as described in Section 4.3.2.1 of the LTR. Any deviations have been explained.

Discontinuities requiring additional 0 components (such as nozzles) to be considered part of the beltline have been adequately described. It is clear which curve is used to bound each discontinuity.

Appendix G of the LTR describes the process for considering a thickness discontinuity, both beltline and non-beltline. If there is a discontinuity in the LSCS Unit 1 vessel that requires such an evaluation, the evaluation was performed. The affected curve was adjusted to bound the discontinuity, if required.

Appendix H of the LTR defines the I basis for the CRD Penetration curve discontinuity and the appropriate transient application. The LSCS Unit 1 evaluation bounds the requirements of Appendix H.

Appendix J of the LTR defines the 0 basis for the Water Level Instrumentation Nozzle curve discontinuity and the appropriate transient application. The LSCS Unit 1 evaluation bounds the requirements of Appendix J.

Page 33 of 33

ATTACHMENT 3 Revised Exelon Response to GGNS RAI #6 (Non-Proprietary)

LaSalle County Station, Unit 1 3 pages follow

GEH Non-Proprietary Information EPRI Non-Proprietary Information GGNS RAI #6 Provide the surveillance data and the analysis of the surveillance data used to determine ART from BWRVIP-135, "BWR Vessel and Internals project Integrated Surveillance Program (ISP)

Data Source Book and Plant Evaluations", as required by NEDC-33178P-A.

Response

BWRVIP-135, Revision 2 (Reference 6.10) defines the representative Materials for LSCS Unit 1.

Excerpt from BWRVIP-135, Revision 2 (used by permission)

Target Vessel ISP Representative Materials Materials Weld 1P3571 1P3571 Plate 05978-2 C6345-1 The results from the testing of the LaSalle Unit 1120° Surveillance capsule have not yet been incorporated into BWRVIP-135. BWRVIP Letter 2012-026 (Reference 6.9) provides the LaSalle Unit 1 surveillance data considered in determining the chemistry and any adjusted Chemistry Factors (CF) for the beltline materials.

Plate For LaSalle Unit 1, the Integrated Surveillance Program (ISP) representative plate, heat 06345-1, is not the target plate, but is a heat in the LaSalle Unit 1 beltline region, and therefore the data reported in Reference 6.9 was considered in the evaluation of that vessel plate. The Best Estimate Chemistry for plate 06345-1 is 0.14% Cu and 0.54% Ni; the CF from Regulatory Guide 1.99 Revision 2 for this chemistry is 97.3°F. A fitted CF of 152.42°F was determined based on the testing documented in Reference 6.9. The maximum scatter in the fitted data is within the 1-sigma value of 17°F for plates given in Regulatory Guide 1.99 Revision 2.

Because there are two irradiated data sets for this plate that fall within the 1-sigma scatter band, the ISP surveillance data was used to revise the projected ART value for vessel plate heat 06345-1, with a reduced margin term (Regulatory Guide 1.99 Revision 2 Position 2.1).

Although this material was considered in determining the limiting ART for the P/T curves; this is not the limiting material.

Page 4 of 11

GEH Non-Proprietary Information EPRI Non-Proprietary Information Best Estimate Chemistry of Available Data Sets for Plate Heat C63.45-1 Cu (wt%) Ni OW%) P (wt%) S (wt%) Si (wt%) Specimen ID Source D.14 0_56 0.015 - - B-417 Reiererce A-7-2 D.14 0_47 - - - B-417 Reference A-7-1 0.14 0.515 0.015 - - Average 13-417 -

D.12 0.49 0.015 - - 9-433 Reierence A-7-2

.14 0 57 - - - 9-433 Reference A-7-1 0.13 0.53 0.015 - - Average B-433 -

72.11 0.51.:. 0.016 - - 6-415 Reference A-7-2 D.18 0_8D - - - B435 Reference A-7-1 0.145 0.55 0.016 - - Average B-435 -

0.15 0_56 - - - B-411 Reference A-7-2 0.13 0.51 - - - B-4J1 Reference A-7-2 0.15 0.57 - - - 9-436 Reference A-7-2 0.15 0.57 - - - 9-437 Refererce A-7-2 0.13 0.50 - - - 13-4J5 Reference A-7-2

...13 0.50 - - - B-4JC Reierence A-7-2 D.14 0.54 - - - B-4JC Reference A-7-1 0.135 0.52 - - - Average I3-4JC -

D.15 0.5-8 - - - B-4J6 Reference A-7-2 D.15 036 - - - 9-4J6 Reference A-7-1 0.15 0_57 - - - Average 13-4J6 -

0.14 0.56 - - - 8-438 Refererce A-7-2 0.19 051 - - - 9-413 Reference A-7-2 0.14 0.55 0.011 - - CE Refererre A-7-2 0.14 0.54 0.014 - - 4-Best Estimate Average Weld For LaSalle Unit 1, the ISP representative weld, 1P3571, is identical to the target weld and therefore the data reported in Reference 6.9 was considered in the evaluation of the vessel weld. The weld heat in the LaSalle Unit 1 vessel for weld 1P3571is 0.283% Cu and 0.755% Ni; the CF from Regulatory Guide 1.99 Revision 2 for this chemistry is 212°F. The Best Estimate Chemistry for weld 1P3571 is 0.21% Cu and 0.75% Ni; the CF from Regulatory Guide 1.99 Revision 2 for this chemistry is 188.75°F. A fitted CF of 388.47°F was determined based on the testing documented in Reference 6.9. The maximum scatter in the fitted data is within the 1-sigma value of 28°F for welds given in Regulatory Guide 1.99 Revision 2.

Because the representative weld material is the same heat number as the target weld in the LaSalle Unit 1 reactor, and because there are two irradiated data sets for this weld, the ISP surveillance data was used to determine an Adjusted Surveillance CF.

Table CFvezei Adjusted Stul,-. CF =

• Fined Data Table CFs.,_c,,

Page 5 of 11

GEH Non-Proprietary Information EPRI Non-Proprietary Information Therefore, the adjusted surveillance CF = (212 / 188.75)* 388.47°F = 437°F, which is used for the ISP weld material evaluation with a reduced margin term (Regulatory Guide 1.99 Revision 2 Position 2.1). The weld material 1P3571 is the limiting material for LaSalle Unit 1.

Best Estimate Chemistry of Available Data Sets for Weld Neat 1P3571 Cu Ni P S Si Specimen Source (wt%) (M%) (wt%) (wt%) (wt%) ID 0.2 0.73 - - - 44U Reference B-8-2 7:22 0/3 - - - 44M Reference 6-8-2

., 15 C 54 - - - 44M Reference B 020 0.585 - - - Average 44M -

0.2 0.74 - - - 410 Reference B-8.2 0.2 035 0.017 _ _ 443 Reference B-8-2 0.14 C5; - - - 443 Reference B-8-1 0.195 012 0.017 - - Average 443 -

0_22 0/5 - - - 444 Reference B-5-2 0.2 0.76 0.016 - - 4-IA Reference B-8-2 2.18 0.7 - - - 444 Reference 13-8-1 0.19 0.73 0.016 - - Average 44A -

0.22 0.79 - - - 447 Reference B-8-2 0_21 0.8 - - - 45K Reference B-8-2 0.21 0.0 - - - 45M Reference B-8-2 0.22 0.8 - - - 450 Reference B-8-2 0.23 C 52 0.014 - - 45E Reference 6-8-2 018 0.54 - - - 45E Reference B-8-1 018 0.e.4 - - - 45E Reference B-8-1 0.197 0.717 0.014 - - Average 45E -

.".. 22 0 .*': - - - 44F Reference B-8-2 2.19 C74 - - - 44F Reference B t 0.205 0.77 - - - Average 44F -

0.21 0.78 0.015 - - CE Reference B-8-2 0.21 0.75 0.016 - - 4 Beet Estimate Average Page 6 of 11