Text

License Amendment Request - Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
	ML121230354
Person / Time
Site:	Peach Bottom
Issue date:	04/27/2012
From:	Jesse M; Exelon Nuclear, Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
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ML121230353	List: ML121230354;
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	Download: ML121230354 (146)
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Exelon Nuclear www.exeloncorp.com 200 Exelon Way Nuclear Kennett Square, PA 19348 PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 10 CFR 50.90 10 CFR Part 54 April 27, 2012 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

License Amendment Request - Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (Exelon) requests proposed changes that would modify Technical Specification (TS) Section 1.1 ("Definitions"),

Section 3.4.9 ("RCS Pressure and Temperature (PIT) Limits"), and Section 5.6 ("Reporting Requirements") by replacing the existing reactor vessel heatup and cooldown rate limits and the pressure and temperature (P-T) limit curves with references to the Pressure and Temperature Limits Report (PTLR) at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3.

The proposed changes have been reviewed by the PBAPS Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the Exelon Quality Assurance Program.

Exelon requests approval of the proposed amendment by April 27, 2013. Once approved, this amendment shall be implemented within 60 days of issuance.

Attachment 1 contains the evaluation of the proposed changes. Attachment 2 provides the marked up TS and Bases pages. The Bases pages are being provided for information only.

Attachment 3 contains the proprietary PBAPS, Units 2 and 3 PTLR. Attachment 4 contains proprietary responses to requests for additional information' related to this issue involVing a separate nuclear power facility which have been customized for PBAPS, Units 2 and 3.

Attachments 5 and 6 are non-proprietary versions of Attachments 3 and 4, respectively.

In accordance with 10 CFR 50.91, Exelon is notifying the Commonwealth of Pennsylvania of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official.

Attachments 3 and 4 transmitted herewith contain Proprietary Information.

When separated from attachments, this document is decontrolled.

License Amendment Request -

Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report April 27, 2012 Page 2 There are no commitments contained in this submittal; however, commitment 23 associated with license renewal for PBAPS, as detailed in NUREG-1769, Appendix D, is completed with this submittal. Commitment 23 required submittal of the reactor pressure vessel P-T curves for 54 EFPY. These curves are included as part of Attachment 3 of this license amendment request. contains information proprietary to the Electric Power Research Institute (EPRI).

EPRI requests that Attachment 3 be withheld from public disclosure in accordance with 10 CFR 2.390. Attachment 5 contains a non-proprietary version of the document. An affidavit supporting this request is also contained in Attachment 5. contains information proprietary to General Electric Hitachi and EPRI. General Electric Hitachi and EPRI request that Attachment 4 be withheld from public disclosure in accordance with 10 CFR 2.390. Attachment 6 contains a non-proprietary version of the document. Two (2) affidavits supporting this request are also contained in Attachment 6.

Should you have any questions concerning this letter, please contact Tom Loomis at (610) 765-5510.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 27th of April 2012.

Respectfully, ichael D. Jesse Director - Licensing Exelon Generation T,\"_ ..._ - " " : Evaluation of Proposed Changes : Markup of Technical Specifications and Bases Pages : Proprietary Version - Peach Bottom Atomic Power Station Unit 2 and Unit 3 Pressure and Temperature Limits Report : Proprietary Version - Responses to Requests for Additional Information : Non-Proprietary Version - Peach Bottom Atomic Power Station Unit 2 and Unit 3 Pressure and Temperature Limits Report : Non-Proprietary Version - Responses to Requests for Additional Information cc: USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Senior Project Manager, PBAPS R. R. Janati, Bureau of Radiation Protection S. T. Gray, State of Maryland

Attachment 1 Evaluation of Proposed Changes

SUBJECT:

Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 No Significant Hazards Consideration 4.4 Conclusions

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

Page 1

Attachment 1 Evaluation of Proposed Changes 1.0

SUMMARY

DESCRIPTION In accordance with 10 CFR 50.90, IIApplication for amendment of license, construction permit, or early site permit, II Exelon Generation Company, LLC (Exelon) requests an amendment to Renewed Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The proposed amendment modifies the Technical Specifications (TS) by replacing the pressure and temperature (P-T) limit curves with references to the Pressure and Temperature Limits Report (PTLR). Relocation of the P-T limit curves to the PTLR is consistent with the guidance provided in U.S. Nuclear Regulatory Commission (USNRC) approved GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1 ('IGE Hitachi Nuclear Energy Methodology for Development of ll Reactor Pressure Vessel Pressure-Temperature Curves (Reference 1). This topical report

)

uses the guidelines provided in USNRC Generic Letter (GL) 96-03, IIRelocation of the Pressure ll Temperature Limit Curves and Low Temperature Overpressure Protection System Limits (Reference 2). Additionally, the TS changes in this license amendment request are consistent with the guidance provided in GL 96-03 as supplemented by Technical Specification Task Force (TSTF) traveler TSTF-419-A, IIRevise PTLR Definition and References in ISTS 5.6.6, RCS PTLR II (Reference 3), and the guidance contained in the August 4, 2011 USNRC letter (Reference 4) which requires the full methodology citation in TS Section 5.6 ('IReporting ll Requirements as discussed below.

),

2.0 DETAILED DESCRIPTION The proposed change includes the following TS revisions:

ll a) TS Section 1.1, IIDefinitions - A new definition, IIPressure and Temperature Limits Report, II is added. The wording for this definition is consistent with that in TSTF-419-A.

ll b) TS Section 3.4.9, IIRCS Pressure and Temperature (prr) Limits The P-T curves and the associated TS wording have been deleted and replaced with references to the PTLR.

ll c) TS Section 5.6, IIReporting Requirements - A new Section 5.6.7 ('IReactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)II) has been added. The format and content of new Section 5.6.7 are consistent with that in TSTF-419-A, and the guidance contained in the August 4, 2011 USNRC letter (Reference 4) which requires ll the full methodology citation in TS Section 5.6 ('IReporting Requirements ). This new section: (1) identifies the individual TS that address reactor coolant system P-T limits; (2) references the USNRC-approved topical report that documents PTLR methodologies in a complete citation; and (3) requires that the PTLR and any revision or supplement thereto be submitted to the USNRC. provides the existing TS pages marked-up to show the proposed changes.

Marked-up pages showing corresponding changes to the TS Bases are provided in for information only. The TS Bases changes will be processed in accordance with the PBAPS, Units 2 and 3 Bases Control Program (TS 5.5.10).

The Attachment 3 PTLR provides the P-T curves developed to represent steam dome pressure versus minimum vessel metal temperature incorporating appropriate non-beltline limits and irradiation embrittlement effects in the beltline region. PBAPS, Units 2 and 3 are currently Page 2

Attachment 1 Evaluation of Proposed Changes licensed to P-T curves for up to 32 effective full power years (EFPV); the analysis performed in this report establishes curves for up to 32 and 54 EFPV. The 1998 Edition of the ASME Boiler and Pressure Vessel Code including 2000 Addenda was used in this evaluation.

As documented in Section 4.0 of the Safety Evaluation Report for GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, licensees who choose to implement NEDC-33178P-A, Revision 1 as their facility*s PTLR methodology must address one plant-specific action item:

The licensee must identify the report used to calculate the neutron fluence and document that the plant-specific neutron fluence calculation will be performed using an approved neutron fluence calculation methodology.

Accordingly, the PTLR incorporates a fluence calculated in accordance with the GE Licensing Topical Report NEDC-32983P-A, Revision 2, which has been approved by the USNRC (Reference 5), and is in compliance with Regulatory Guide 1.190. The latest information from the BWRVIP Integrated Surveillance Program that is applicable to PBAPS, Units 2 and 3 has been utilized.

This license amendment request is being submitted to satisfy commitment 23 associated with license renewal for PBAPS, as detailed in NUREG-1769, Appendix D. In order to bound potential future operations at uprated conditions, the revised fluence represents a power level of 120% of original licensed thermal power, equal to 3951 MWt. Current Licensed Power level fluence (3514 MWt) was considered through 31.06 Effective Full Power Years (EFPV) for Unit 2 and 31.96 EFPY for Unit 3, which represents the end of Cycle 20. For the remainder of the plant's operating license, fluence at a power level of 120% of original licensed thermal power was assumed. Use of this fluence for the P-T curves for current operating conditions is conservative and is not dependent on the approval of an Extended Power Uprate application.

As stated previOUSly, relocation of the P-T limit curves to the PTLR is consistent with the guidance provided in USNRC Generic Letter (GL) 96-03, IIRelocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits ll (Reference 2), TSTF-419-A, IIRevise PTLR Definition and References in ISTS 5.6.6, RCS PTLR II (Reference 3), and the guidance contained in the August 4, 2011 USNRC letter (Reference 4) which requires the full methodology citation in TS Section 5.6 C*Reporting Requirements ll ).

3.0 TECHNICAL EVALUATION

10 CFR 50, Appendix G, requires the establishment of P-T limits for material fracture toughness requirements of the Reactor Coolant Pressure Boundary materials. 10 CFR 50, Appendix G requires an adequate margin to brittle failure during normal operation, abnormal operational transients, and system hydrostatic tests. It mandates the use of the ASME Code,Section III, Appendix G.

Historically, the P-T limit curves for BWRs have been contained in the TS, necessitating the submittal of license amendment requests to update the curves. This caused both the USNRC and licensees to expend resources that could otherwise be devoted to other activities.

Page 3

Attachment 1 Evaluation of Proposed Changes Generic Letter 96-03 allows plants to relocate their P-T curves and associated numerical limits (such as heatup and cooldown rates) from the plant TS to a PTLR, which is a licensee-controlled document. As stated in Generic Letter 96-03, during the development of the improved Standard Technical Specifications (STS), a change was proposed to relocate the P-T limits currently contained in the plant TS to a PTLR. As one of the improvements to the STS, the USNRC staff agreed with the industry that the curves may be relocated outside the plant TS to a PTLR so that the licensee could maintain these limits efficiently. One of the prerequisites for having the PTLR option is that the P-T curves and limits be derived using methodologies approved by the USNRC, and that the associated licensing topical reports describing the approved methodologies be referenced in the plant TS.

The purpose of GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, is to provide the methodology developed by GE Hitachi Nuclear Energy (GEH) for the determination of reactor pressure vessel P-T curves. The adequacy of the GEH methodology is demonstrated through a detailed description of the calculation procedures and examples showing agreement between GEH practices and the standards and Code requirements set forth in 10 CFR 50, Appendix G. NEDC-33178P-A, Revision 1, does not include development or licensing of vessel fluence methods. The fluence methods are provided in GE Licensing Topical Report NEDC-32983P-A, Revision 2.

In order to implement the PTLR, the analytical methods used to develop the P-T limits must be consistent with those previously reviewed and approved by the USNRC and must be referenced in the Administrative Controls section of the plant TS. GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, provides the current methodology for developing reactor coolant system P-T limit curves and other associated numerical limits for BWRs. The PBAPS, Units 2 and 3 P-T curves have been developed in accordance with the NEDC-33178P-A, Revision 1, methodology as documented in the PTLR provided in .

The P-T curves included in the PTLR have been developed to present steam dome pressure versus minimum vessel metal temperature incorporating appropriate non-beltline limits and irradiation embrittlement effects in the beltline region. Complete P-T curves were developed for 32 and 54 effective full power years (EFPV). These P-T curves and a tabulation of the curves are provided in the PTLR. This report incorporates a fluence (E > 1 MeV) calculated in accordance with the GE Licensing Topical Report NEDC-32983P-A, Revision 2, which has been approved by the USNRC, and is in compliance with Regulatory Guide 1.190. The latest information from the BWRVIP Integrated Surveillance Program that is applicable to PBAPS, Units 2 and 3 has been utilized.

The methodology used to generate the P-T curves in this report is presented in Section 3.0 of the PTLR. The 1998 Edition of the ASME Boiler and Pressure Vessel Code including 2000 Addenda was used in this evaluation.

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 and low-level physics tests, referred to as core not critical operation or Curve B, and (c) core critical operation, referred to as Curve C. There are four vessel regions that should be monitored against the P-T curve operating limits; these regions are defined on the thermal cycle diagram:

Page 4

Attachment 1 Evaluation of Proposed Changes

Closure flange region (Region A)

Core beltline region (Region B)

Upper vessel (Regions A & B)

Lower vessel (Regions B & C)

For the core not critical and the core critical curves, the P-T curves specify a coolant heatup and cooldown temperature rate of 1OO°F/hr or less 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. The bounding transients used to develop the curves are described in NEDC-33178P-A, Revision 1. For the hydrostatic pressure and leak test curve, a coolant heatup and cooldown temperature rate of 20°F/hr or less must be maintained at all times. The P-T curves apply for both heatup and cooldown and for both the 1/4T and 3/4T locations because the maximum tensile stress for either heatup or cooldown is applied at the 1/4T location. For beltline curves this approach has added conservatism because irradiation effects cause the allowable toughness, Klr, at 1/4T to be less than that at 3/4T for a given metal temperature. Curves A and B provide separate bottom head as well as composite upper vessel and beltline requirements.

Separate P-T curves were developed for the upper vessel, beltline (at various intermediate and end of license EFPYs), and bottom head for the Pressure Test and Core Not Critical conditions.

Composite P-T curves were generated for each of the Pressure Test, Core Not Critical and Core Critical conditions at intermediate and end of license EFPYs. The composite curves were generated by enveloping the most restrictive P-T limits from the separate bottom head, beltline, upper vessel and closure assembly P-T limits.

The proposed TS revisions associated with relocation of the P-T limits to a PTLR are consistent with the guidance provided in GL 96-03 as supplemented by TSTF-419-A, and the Reference 4 letter.

In the Reference 7 letter, the U.S. Nuclear Regulatory Commission requested additional information concerning the Grand Gulf Nuclear Station, Unit 1 license amendment request pertaining to the implementation of a PTLR. Attachment 4 provides a response to these questions for PBAPS, Units 2 and 3.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria As discussed in the Safety Evaluation Report for GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, the USNRC has established requirements in 10 CFR 50, Appendix G in order to protect the integrity of the Reactor Coolant Pressure Boundary in nuclear power plants. Appendix G requires that the P-T limits for an operating light-water nuclear reactor be at least as conservative as those that would be generated if the methods of Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code were used to generate the P-T limits. 10 CFR Part 50, Appendix G also requires that applicable surveillance data from RPV material surveillance programs be incorporated into the calculations of plant specific P-T limits, and that the P-T limits for operating reactors be generated using a method that accounts for the effects of neutron irradiation on the material properties of the RPV beltline materials. USNRC regulatory guidance related to P-T limit curves Page 5

Attachment 1 Evaluation of Proposed Changes is found in Regulatory Guide 1.99, Revision 2 C'Radiation Embrittlement of Reactor Materials")

and Standard Review Plan (NUREG-0800) Section 5.3.2 ("Pressure-Temperature Limits, Upper-Shelf Energy, and Pressurized Thermal Shock").

Adoption of the USNRC-approved methodology described in the GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, for the preparation of the P-T limit curves ensures that the requirements of 10 CFR 50, Appendix G will be satisfied. 10 CFR Part 50, Appendix H provides criteria for the design and implementation of reactor pressure vessel material surveillance programs for operating light water reactors. PBAPS, Units 2 and 3 demonstrates its compliance with the requirements of 10 CFR Part 50, Appendix H through participation in the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) (Reference 6).

Generic Letter 96-03 provides regulatory guidance regarding relocation of P-T curves and associated numerical limits (such as heatup and cooldown rates) from plant TS to a PTLR (a licensee-controlled document). As stated in GL 96-03, a licensee requesting such a change must satisfy the following three criteria:

(1) Have USNRC-approved methodologies to reference in the TS, (2) Develop a PTLR to contain the P-T limit curves, associated numerical limits, and any necessary explanation, and (3) Modify applicable sections of the TS accordingly.

The USNRC-approved methodology of GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, has been adopted for preparation of the PBAPS, Units 2 and 3 P-T limit curves. As discussed in Section 5.0 ("Conclusion") of the Reference 1 USNRC Safety Evaluation Report:

liThe NRC staff concludes that BWROG LTR NEDC-33178P, Revision 1, satisfies the criteria in Attachment 1 in GL 96-03 and provides adequate methodology for BWR licensees to calculate P-T limit curves, given that licensees referencing this LTR comply with the conditions listed in Section 4.0 of this SE. Using this methodology and following the PTLR guidance in GL 96-03, as amended by NRC TSTF-419, BWR licensees will be able to relocate the P-T limit curves from TS to a PTLR, a licensee-controlled document. II As discussed previously, the PTLR incorporates a fluence calculated in accordance with the GE Licensing Topical Report NEDC-32983P-A, Revision 2, which has been approved by the USNRC (Reference 5), and is in compliance with Regulatory Guide 1.190, thus satisfying the requirement contained in Section 5.0 of the USNRC Safety Evaluation Report.

Proposed revisions to applicable sections of the TS have been prepared and are provided in to this submittal. These proposed TS changes are consistent with the guidance provided in GL 96-03, as supplemented by TSTF-419-A, and the guidance contained in the August 4, 2011 USNRC letter (Reference 4) which requires the full methodology citation in TS Section 5.6 ("Reporting Requirements").

Page 6

Attachment 1 Evaluation of Proposed Changes 4.2 Precedent The USNRC has approved similar license amendments to relocate P-T limit curves to a PTLR.

Recent examples for boiling water reactor plants include:

1) Oyster Creek Nuclear Generating Station (License Amendment No. 269 issued by USNRC letter dated September 30,2008 - ADAMS Accession No. ML082390685).

2) James A. Fitzpatrick Nuclear Power Plant (License Amendment No. 292 issued by USNRC letter dated October 3, 2008 - ADAMS Accession No. ML082630385).

4.3 No Significant Hazards Consideration Exelon Generation Company, LLC (Exelon) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below.

1. Do the proposed changes involve a significant increase" in the probability or consequences of an accident previously evaluated?

Response: No The proposed changes modify the TS by replacing references to existing reactor vessel heatup and cooldown rate limits and P-T limit curves with references to the PTLR. The proposed amendment also adopts the USNRC-approved methodology of the GE Hitachi Nuclear Energy Licensing Topical Report NEDC-33178P-A, Revision 1, for the preparation of the PBAPS, Units 2 and 3 P-T limit curves. In 10 CFR 50, Appendix G, requirements are established to protect the integrity of the Reactor Coolant Pressure Boundary in nuclear power plants. Implementing the USNRC-approved methodology for calculating P-T limit curves and relocating those curves to the PTLR provide an equivalent level of assurance that Reactor Coolant Pressure Boundary integrity will be maintained, as specified in 10 CFR 50, Appendix G.

The proposed changes do not adversely affect accident initiators or precursors, and do not alter the design assumptions, conditions, or configuration of the plant or the manner in which the plant is operated and maintained. The ability of structures, systems, and components to perform their intended safety functions is not altered or prevented by the proposed changes, and the assumptions used in determining the radiological consequences of previously evaluated accidents are not affected.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. .

2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No Page 7

Attachment 1 Evaluation of Proposed Changes The change in methodology for calculating P-T limits and the relocation of those limits to the PTLR do not alter or involve any design basis accident initiators. Reactor Coolant Pressure Boundary integrity will continue to be maintained in accordance with 10 CFR 50, Appendix G, and the assumed accident performance of plant structures, systems and components will not be affected. These changes do not involve any physical alteration of the plant (Le., no new or different type of equipment will be installed), and installed equipment is not being operated in a new or different manner. Thus, no new failure modes are introduced.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Do the proposed changes involve a significant reduction in a margin of safety?

Response: No The proposed changes do not affect the function of the Reactor Coolant Pressure Boundary or its response during plant transients. By calculating the P-T limits using USNRC-approved methodology, adequate margins of safety relating to Reactor Coolant Pressure Boundary integrity are maintained. The proposed changes do not alter the manner in which safety limits, limiting safety system settings, or limiting conditions for operation are determined. There are no changes to setpoints at which protective actions are initiated, and the operability requirements for equipment assumed to operate for accident mitigation are not affected.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Based on the above evaluation, Exelon concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of no significant hazards consideration is justified.

4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission1s regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

Exelon has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 1I CFR 20, IIStandards for Protection Against Radiation. However, the proposed amendment does not involve: (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in Page 8

Attachment 1 Evaluation of Proposed Changes 10 CFR 51.22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review, II paragraph (c)(9). Therefore, pursuant to 10 CFR 51.22, paragraph (b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.

6.0 REFERENCES

1) Letter from D. Coleman (BWR Owners* Group) to U.S. Nuclear Regulatory Commission, IISubmittal of GE BWROG Topical Report NEDC-33178P-A, 'General Electric Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves',11 ML092370486, dated July 29, 2009

2) Generic Letter (GL) 96-03, IIRelocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits,1I dated January 31, 1996

3) Technical Specification Task Force (TSTF) Traveler TSTF-419-A, IIRevise PTLR Definition and References in ISTS 5.6.6, RCS PTLR, II dated August 4, 2003

4) Letter from J. Jolicoeur (U.S. Nuclear Regulatory Commission) to Technical Specification Task Force, IIlmplementation of Travelers TSTF-363, Revision 0, 'Revise Topical Report References in ITS 5.6.5, COLR (Core Operating Limits Report),' TSTF-408, Revision 1,

'Relocation of LTOP (Low-Temperature Overpressure Protection) Enable Temperature and PORV (Power-Operated Relief Valve) Lift Setting to the PTLR (Pressure-Temperature Limits Report),' and TSTF-419, Revision 0, 'Revise PTLR Definition and References in ISTS (Improved Standard Technical Specification) 5.6.6, RCS (Reactor Coolant System) PTLR',II ML110660285, dated August 4, 2011

5) Letter from G. Stramback (GE) to U.S. Nuclear Regulatory Commission, IIAccepted Version of GE Licensing Topical Report NEDC-32983P-A, Revision 2 (TAC No. MC3788),1I ML072480116, dated February 1, 2006

6) Letter from G. Wunder (U.S. Nuclear Regulatory Commission) to J. Skolds (Exelon Generation Company, LLC), IIPeach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Amendment RE: Revision to the Reactor Pressure Vessel Material Surveillance Program (TAC Nos. MB7006 and MB7007),1I dated November 4,2003

7) Letter from M. A. Krupa (Entergy Operations, Inc.) to U.S. Nuclear Regulatory Commission, IIRequest for Additional Information Regarding Extended Power Uprate, II ML110540540, dated February 23, 2011 Page 9

ATTACHMENT 2 Markup of Technical Specifications and Bases Pages Revised Pages (Units 2 and 3)

TS Page 1.1-5 3.4-21 3.4-22 3.4-23 3.4-24 3.4-25 3.4-26 3.4-27 5.0-22 B 3.4-43 B 3.4-44 B 3.4-45 B 3.4-46 B 3.4-47 B 3.4-48 B 3.4-49 B 3.4-50 B 3.4-51

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

The PTLR is the unit-specific document that provides the reactor vessel pressure and temperature limits. 1n1 tions including heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and 1.1 temperature limits shall be determined for each fluence period in accordance with Specification 5.6.7.

=> 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THER"AL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3514 HWt.

REACTOR PROTECTION SYSTEM The RPS RESPONSE TIME shall be that time interval (RPS) RESPONSE TIME from the opening of the sensor contact up to and including the opening of the trip actuator contacts.

RECENTLY IRRADIATED RECENTLY IRRADIATED FUEL is fuel that has occupied FUEL part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . When using this definition to suspend the Applicability of LeOs, secondary containment ground-level hatches H15, H16, H17, H18, H19, and H33 shall be closed during the movement of any irradiated fuel in Secondary Containment.

SHUTDOWN MARGIN (SOH) SDH shall be the amount of reactivity by which the reactor is subcr1tical or would be subcritical assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68°F; and

c. All control rods are fUlly inserted except for the single control rod of highest reactivity worth, which is assumed to be fUlly withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determi nat; on of SO" ..

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n ;s the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERHAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

(continued)

PBAPS UNIT 2 1 .1-5 Amendment No. 269

Res PIT Limits 3.4.9 I ~ 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 ReS Pressure and Temperature (PIT) limits Leo 3.4.9 Res pressure, ReS temperature, ReS heatup and cooldown rates, and the recirculation pump starti e erature requi rements shall be 1111 nta 1ned wi th 1n .I'-.....r__.._

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOT£--------- A.I Restore parameter(s) 30 minutes Required Action A.2 shall be completed if

.to within limits

this Condition is MIl entered.

A.2 Detenaine ReS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of the continued operation.

LCD not met in MODE 1, 2, or 3.

B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A Arm not met. "'

8.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

')

.. .,../

PBAPS UNIT 2 3.4-21 Amendment No. 210

I~ CS P/ r L i rn 1 t s 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

c. .' ... _.... -NOTE - .. _.... - - -.. C.1 Initiate dction to Immediately Required Action e.2 restore parameter(s) shall be completed if to within 1imits.

this Condition is entered. AHa C.2 Determine ReS is Prior to Requirements of the acceptable for entering MODE 2 LCD not met in other operation. or 3.

than MODES 1, 2, and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 - - - - - .. - - - - ...... - .. - - - .. NOTE .. - ......... - - - - ...... - .. - - - - ..

Only required to be performed during ReS heatup and cool down operations and ReS

nservice leak and hydrostatic testing.

In accordance within the limits specified in the PTLR with the Surveillance Frequency Control Program.

within the limits specified in the PTLR. (continued)

)

PBAPS UNIT 2 3.4-22 Amendment No. 278

RCS PIT Limits 3.4.9 SURVEILLANCE RE UIREMENTS continued SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are Once within

~~~~~r~ica11ty limits specified in 15 minutes prior to control rod withdrawal for the purpose of achieving cri t i ca11 ty SR 3.4.9.3 --------------------NOTE-------------------

Only required to be ..t in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pre sure vessel (RPV) coolant temperature prior to each is

startup of a recirculation

(~ pump within the limits specified in the PTLR.

SR 3.4.9.4 -------------------NOTE--------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor Once within coolant temperature in the recirculation 15 minutes loop to be sta~he RPV coolant prior to each temperature is * . startup of a recirculation pump within the limits specified in the PTLR.

(continued)

I)

PBAPS UNIT 2 3.4-23 Amendment No. 210

I~C S P/ r lim its 3.4.9 t.***.:.)* SURVEILLANCE REQUIREMENrS (continued)

'I.

SURVEILLANCE FREOUENCY SR 3.4.9.5 - NO TE ..

Only required to be performed when tensioning the reactor vessel head bolting studs.

Ve r i f y rea c tor ves self l.____n_e. .-. . . __.-.. . . In accordance flange temperatures ar with the Surveillance Frequency within the limits specified in the PTLR.

Control Program

SR 3.4.9.6 .. .. .. .. .. .. .. - NOTE ..

Not required to be performed until 30 minutes after ReS temperature S 80°F 1n MODE 4.

Verify reactor vessel fl~n~~~~~~ In accordance flange temperatures ar with the Surveillance Frequency within the limits specified in the PTLR.

Control Program .

SR 3.4 . 9.7 ............................................ NOTE* - - ..

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after ReS t~mperature S lOQoF in MODE 4.

Veri fy reactor vessel ~ head In accordance flange temperatures ar . with the Surveillance Frequency Control within the limits specified in the PTLR.

Program.

.)

PBAPS UNIT 2 3.4-24 Amendment No. 278

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Te.,erature/Pressure Limits for Inservice Hydrostatic and Inservice Leakage Tests PBAPS UNIT 2 3.4-25 Amendment No. Z10

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IS LESS U" E CURVE

THAN DISCONT1NUf1Y C B o I o 100 . 200 JOO. 400 50 600 twlNIMUW ~OR VESSEL METAL lDof'ERAlURE (Of')

Figure 3.4.9-2 (page 1 of 1)

Te.perature/Pressure Limits for Non-Nuclear Heatup and Cooldown Following a Shutdown PBAPS UNIT 2 3.4-26 Amendment No. 210

Res PIT Limit 3.4 i .* . ,. iJ i l .. . . . ** I '

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Figure 3.4.9 -3 (page 1 of 1)

Temperature/Pressure Limits for Criti cality PBAPS UNIT 2 3.4-21 Amendment No. 210

f<npor t. i nq I~(*~qui r~rnf~n t s

~) .6

)

~) . 6*5 CJ) RE () PER Ar I NG LIM [ rS f~ EPQRr (C 0LR) ( C 0 rl tin u e d )

I. PECo-FMS-0005 A, "Methods for Performinq BWR Steddy-State Reactor Physics Analysis";

H. PECo-FMS*0006*A, "Methods for Performing BWR Reload Sdfety Evaludtions"; and

9. NEDO*32465-A, UReactor Stability Detect and Suppress Solutions Licensing Basis Methodology And Reload Applications," August 1996.

c. rhe core operating limits shall be determined such that all dpplicablel irnits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) 1irnits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon jssuance for each reload cycle to the NRC.

5.6.6 Post Ac~ident Monitoring (PAM) Ins.trumentation Report When d report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.7 .Reactor Coolant ~em (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. ReS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following: .

i) Limiting Conditions for Operation Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits" ii) Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits*'

b. The analytical methods used to determine the ReS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

i) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves," Revision 1, June 2009

c. The PTLR shall be prOVided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

PBAPS UNIT 2 5.0-22 Amendment No. 251

Res PIT limits B 3.4.9 B 3.4 REACTOR COOLANT SYSTEM (ReS)

)

B 3.4.9 RCS Pressure and Temperature (PIT) Limits BASES BACKGROUND All components of the Res are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LCO limits the pressure and temperature changes during ReS heatup and cool down , within the design assumptions and the stress limits for cycllc operat1on.

The PRESSURE AND ~~~~~~~lcontains PIT limit curves for heatup, TEMPERATURE LIMITS coo own, a n ervice leakage and hydrostatic testing, and REPORT (PTLR) (Ref. 10) also limits the maximum rate of change of reactor coolant temperature. The criticality curve provides limits for both heatup and criticality.

Each PIT limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.

The LCD establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RePB). The vessel is the component most subject to brittle failure. Therefore, the Leo limits apply to the vessel.

10 CFR 50, Appendix G (Ref. 1), requires the establishment of PIT limits for material fracture toughness requirements of the RepS materials. Reference 1 requires an adequate margin to brittle failure during nonnal operation, abnormal operational transients, and system hydrostatic tests. It mandates the use of the ASHE Code,Section III, Appendix G (Ref. 2).

The actual shift in the RTmy of the vessel material will be established periodically by removing and evaluating th~

irradiated reactor vessel material specimens, in accordance with the UFSAR (Ref. 3) and Appendix H of 10 CFR 50 (Ref. 4). The operating PIT limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendations of Reference 5.

"\

)

(continued)

PBAPS UNIT 2 B 3.4-43 Revision No. 0

Res PIT limits B 3.4.9 BASES

)

BACKGROUND The PIT limit curves are composite curves established by (continued) superimposing limits derived from stress analyses of those portions of the reactor vessel and head that are the most restrictive. At any specific pressure, temperature, and temperature rate of change, one location within the reactor vessel will dictate the most restrictive limit. Across the span of the PIT limit curves, different locations are more restrictive, and, thus, the curves are composites of the most restrictive regions.

The heatup curve represents a different set of restrictions than the cool down curve because the directions of the therMal gradients through the vessel wall are reversed. The thermal gradient reversal alters the location of the tensile stress between the outer and inner walls.

The criticality limits include the Reference 1 requirement that they be at least 40-F above the heatup curve or the cool down curve and not lower than 60*F above the adjusted reference temperature of the reactor vessel material in the region that is controlling (reactor vessel flange region).

The consequence of violating the LCO limits is that the RCS

")

(,,' has been operated under conditions that can result in brittle failure of the reactor pressure vessel, possibly leading to a nonisolab1e leak or loss of coolant accident.

In the event these limits are exceeded, an evaluation must be performed to determine the effect on the structural integrity of the RCPS components. ASHE Code,Section XI, AppendiX E (Ref. 6), prOVides a recommended methodology for evaluating an operating event that causes an excursion outside the limits.

APPLICABLE The PIT limits are not derived from Design Basis Accident SAFETY ANALYSES (DBA) analyses. They are prescribed during normal operation to avoid encountering pressure, temperature, and temperature rate of change conditions that might cause undetected flaws to propagate and cause nonductile failure of the reactor

. . 1 lnce tie ere are no acceptance limits related to the limits. Rather, the PIT limits are acceptance limits themselves since they preclUde operation in an unanalyzed condition.

(continued)

')

./

PBAPS UNIT 2 B 3.4-44 Revision No. 0

Res PIT limits B 3.4.9 BASES

)

APPLICABLE ReS PIT limits satisfy Criterion 2 of the NRC Policy SAFETY ANALYSES Statement.

(continued) leo The elements of this LCD are:

a.

e temperature difference between the reactor coolant in the respective~lation loop and in the

~~ ~re~a~cit~or~v~e~s~se~l~~duringrecirculation pump s ar up; the PTLR,

d. ReS pressure and temperature arT~~~~~~

criticality limits specified in , prior to achieving criticality; and

e. The reac ~e and the head flange temperatures a when tensioning the reactor vessel head bolting s ds.

These limits define allowable operating regions and permit a large nu.o.r of operating cycles while also providing a wide margin to nonductile failure.

The rate of change of temperature limits controls the thermal gradient through the vessel wall and is used as input for calculating the heatup, cool down, and inservice leakage and hydrostatic testing PIT 1i.it curves. Thus, the LCO for the rate of change of temperature restricts stresses caused by thermal gradients and also ensures the validity of the PIT limit curves.

(continued)

)

PBAPS UNIT 2 B 3.4-45 Revision No. 0

RCS PIT limits B 3.4.9 i ') BASES LCO Violation of the limits places the reactor vessel outside of (continued) the bounds of the stress analyses and can increase stresses in other RCS components. The consequences depend on siveral factors, as follows:

a. The severity of the departure from the allowable operating pressure temperature regime or the severity of the rate of change of temperature;

b. The length of time the limits were violated (longer violations allow the temperature gradient in the thick vessel walls to become more pronounced); and

c. The existences, sizes, and orientations of flaws in the vessel material.

APPLI CAB ILlTV The potential for violating a PIT limit exists at all times.

For example, PIT limit violations could result from ambient temperature conditions that result in the reactor vessel metal temperature being less than the mini.u. allowed temperature for boltup. Therefore, this LCO is applicable even when fuel is not loaded in the core.

ACTIONS A.I and A.2 ;-1in the PTLR I Operation outside the PIT 1illits~i1e in MODES I, 2, and 3 must be corrected so that the RCPB is returned to a condition that has been verified by stre~s analyses.

The 30 minute Completion Time reflects the urgency of restoring the parameters to within the analyzed range. Most violations will not be severe, and the activity can be accomplished in this time in a controlled manner.

Besides restoring operation within limits, an evaluation is required to dete~ine if RCS operation can continue. The evaluation must verify the RCPB integrity remains acceptable and must be completed if continued operation is desired.

Several methods .ay be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, or inspection of the components.

ASME Code,Section XI, Appendix E (Ref. 6), may be used to support the evaluation. However, its use is restricted to evaluation of the vessel belt1ine.

) (continued)

PBAPS UNIT 2 B 3.4-46 Revision No. 0

Res PIT Limits B 3.4.9

) BASES ACTIONS A,l and A.2 (continued)

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable to accomplish the evaluation of a .ild violation. More severe violations may require special. event specific stress analyses or inspections. A favorable evaluation must be completed if continued operation is desired.

Condition A is modified by a Note requiring Required Action A.2 be completed whenever the Condition is entered.

The Note emphasizes the need to perfo~ the evaluation of the effects of the excursion outside the allowable limits.

Restoration alone per Required Action A.I 1s insufficient because higher than analyzed stresses may have occurred and may have affected the RePB integrity.

8.1 and 9.2 If a Required Action and associated Completion Time of Condition A are not met, the plant must be placed in a lower MODE because either the Res remained in an unacceptable PIT region for an extended period of increased stress, or a sufficiently severe event caused entry into an unacceptable region. Either possibility indicates a need for more careful examination of the event, best accomplished with the Res at reduced pressure and temperature. W1.th the reduced pressure and temperature conditions, the possibility of propagation of undetected flaws is decreased.

Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

(.1 an d e.2 ~in the PTLR . I Operation outside the PIT limits in other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the RePB is returned to a condition that has been verified by stress analyses. The Required Action must be initiated without delay and continued until the limits are restored.

(continued)

PBAPS UNIT 2 B 3.4-47 Rev;sion No. 0

f~ CS P/ T L i rn i t ~

B 3.4. C)

, ~) 8ASES ACTIONS C,l dod C,2 (continued)

Besides restoring the PIT limit parameters to within limits, dn evaluation is required to determine if RCS operation ;s

()11owed. rhis eVdludtion must verify that the RCPB integrity is acceptable and must be completed before dpproaching criticality or heating up to > 212°F. Several methods may be used, including comparison with pre*analyzed transients, new analyses, or inspection of the components.

ASME Code, Section Xl, Appendix E (Ref. 6), may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.

SURVEILLANCE 58 3.4.9,1 REQUIREMENTS Verification that operation ;s within is required when ReS pressure and temperature conditions are undergoing planned changes. Plant procedures specify the pressure and temperature monitoring points to be used during the performance of this Surveil lance. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Surveillance for heatup, cooldown, or inservice leakage and hydrostatic testing may be discontinued when the criteria given in the relevant plant procedure for ending the activity are satisfied.

This SR has been modified with a Note that requires this Surveillance to be performed only during system heatup and cool down operations and inservice leakage and hydrostatic testing.

in the PTLR SR 3.4.9,2 A separate limit is used when the reactor is approaching criticality. Consequently, the ReS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical.

(continued)

)

PBAPS UNIT 2 B 3.4-48 Revision No. 86

Res PIT limits B 3.4.9

.) BASES SURVEILLANCE S8 3.4.9.2 (continued)

REQUIREMENTS Performing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the control rod withdrawal.

in the PTLR 58 3.4.9.3 and 58 3,4,9,4 Differential temperatures within the applicable limits ensure that thermal stresses resulting fro. the startup of an idle recirculation pump will not exceed design allowances. In addition, compliance with these limits ensures that the assumptions of the analysis for the startup of an idle recirculation loop (Ref. 9) are satisfied.

Performing the Surveillance within IS minutes before starting the idle recirculation pump provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start.

An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.9.4 is to compare the temperatures of the operating recirculation loop and the idle loop.

SR 3.4.9.3 and SR .3.4.9.4 have been modified by a Note that requires the Surveillance to be met only 1n MODES 1, 2, 3, and 4. In MODE 5, the overall stress on limiting components is lower. Therefore,41 limits are not required. The Note also states the SR is only required to be met during a recirculation pump startup, since this is when the stresses occur.

in the PTLR Lim; on the reactor vessel flange and head flange temperatures are generally bounded by the other PIT limits during system heatup and cooldown. However, operations approaching MODE 4 fro. MODE 5 and in MODE 4 w;th ReS temperature less than or equal to certain specified values require assurance that these temperatures meet the LeO 1imits.

) (continued)

PBAPS UNIT 2 B 3.4-49 Revision No. 0

I~ Csri r Lim its B 3.4.9

) BASES SURVEILLANCE SR 3,4,9.5. SR 3,4,9.6. dod SR 3,4,9.7 (continued)

J~EQU (REM........ S_ _~

EN......T__

linthePTLR ~fltlnge temperatures must be verified to be above the i;mi~before and while tensioning the vessel head bolting (j t uds toe n sur e t hat 0 nee the he ad i s ten s ; oned the 1i mit s dre satisfied. When in MODE 4 with ReS temperature S 80°F, checks of the flange temperatures are required because of the reduced margin to the limits. When in MODE 4 with ReS temperature S lOQoF, monitoring of the flange temperature is required to ensure the temperature is within the limits

':> pee if; ed

I"""in-th-e-p-r-L-R-p Ihe Surveillance Frequency is controlled under the Survei I lance Frequency Control Program.

SR 3.4.9.5 ;s modified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs. SR 3,4.9.6 is modified by a Note that requires the Surveillance to be initiated ufter ReS temperature s 80°F in MODE 4. SR 3.4.9.7 ;s modified by a Note that requires the Surveillance to be initiated after ReS temperature s lOQoF in MODE 4. The Notes contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the limits specified.

REFERENCES 1. 10 CFR 50, Appendix G.

2. ASME, Boiler and Pressure Vessel Code,Section III, Appendix G.

3. UFSAR, Section 4.2.6 and Appendix K.

4. 10 CFR 50, Appendix H.

5. Regulatory Guide 1,99, Revision 2, May 1988.

(continued)

)

PBAPS UNIT 2 B 3.4-50 Revision No. 86

RCS PIT limits B 3.4.9

) BASES REFERENCES 6. Boiler and Pressure Vessel Code,Section XI, (continued) i DELETED

9. UFSAR, Section 14.5.6.2.

10. PRESSURE AND TEMPERATURE LIMITS REPORT.

/

)

PBAPS UNIT 2 B 3.4-51 Revision No. 0

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) Definitions The PTLR is the unit-specific document that provides the reactor vessel pressure and temperature limits. 1. 1 including heatup and cooldown rates, for the current reactor vessal fluance period. These pressure and

.. temperature limits shall be determined for each fluence period In accordance with Specification 5.6.7.

() 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59: or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3514 MWt.

REACTOR PROTECTION SYSTEM The RPS RESPONSE TIME shall be that time interval (RPS) RESPONSE TIME from the opening of the sensor contact up to and including the opening of the trip actuator contacts.

RECENTLY IRRADIATED RECENTLY IRRADIATED FUEL is fuel that has occupied FUEL part of a critical reactor core within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . When using this definition to suspend the Applicability of LeOs, secondary containment*

ground-level hatches H20, H21. H22, H23, H24, and H34 shall be closed during the movement of any irradiated fuel in Secondary Containment.

SHUTDOWN MARGIN (SOH) SOH shall be the amount of reactivity by which the*

...." reactor is subcritica1 or would be subcr1t1cal

()

~"'" . assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68°F; and

c. All control roda are fully inserted except for the single control rod of highest reactivity worth, which ;s assumed to be fully withdrawn.

With control rods not capable of bein~ fUlly inserted, the reactivity worth of these control rods must be accounted for in the determination of SOH.

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems. subsystems, channels. or other designated components during the interval specified by the Surveillance FrequencYr so that all systems, subsystems, channels, or other designated components are tested during nSurveillance Frequency intervals, where n is the total number of systems, s~bsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to th& reactor coolant.

(continued)

PBAPS UNIT 3 1.1-5 Amendment No. 273

Res PIT limits 3.4.9

() 3.4 REACTOR COOLANT SYSTEM (ReS) 3.4.9 Res Pressure and Temperature (PIT) Limits leo 3.4.9 Res pressure, ReS temperature, ReS heatup and cooldown rates, and the recirculation pump starti~rature requirements shall be maintained within*

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE--------- A.I Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed if this Condition is Arm entered.

-~~-~-~--~----~-~~---- A.2 Detenaine ReS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for

(, .,../

) Requirements of the continued operation

leo not met in MODE 1, 2, or 3.

B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND not met.

8.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

PBAPS UNIT 3 3.4-21 Amendment No. 214

RC 5 P/ r L j mit ')

.3.4.~

ACTrONS (continued)

CONDIfION J~EOUIRED ACTION COMPLEflON rIME C* . - . - - - - - - NO TE.... - * - ** - - C* 1 Initiate action to Immediately Required Action e.2 restore parameter(s)

~hal1 be completed if to within l1mits.

this Condition is f:~n t e red. LViIl C.2 Determine RCS 1s Prior to Requirements of the acceptable for entering MODE 2 LCO not met in other operation. or 3.

than MODES 1, 2, and 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 ---- - - - .. - - - .. NOTE - - - .. - - - - - - .. - -

Only required to be performed during ReS heatup and cool down operations and RCS inservice leak and hydrostatic testing.

Verify: In accordance within the limits specified in the PTLR with the a ~~"-'-""''''''''''~~'~'''''''-~':-''~--'''''''''''~---I~-----'~~

Survei 11 ante

~~~~~~~~~~~~~~~.-A..../\~ Frequency Control Program.

b. re within the limits specified in the PTLR. (continued)

PBAPS UNIT 3 3.4-22 Amendment No. 281

RCS PIT limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILlANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are Once within

~cality li.its specified in 15 minutes prior to control rod

~~.PTLRI withdrawal for the purpose of achieving critical ity SR 3.4.9.3 --------------------NOTE-------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom Once within head coolant temperature and the reactor 15 minutes pre~sura v~sel (RPV) coolant temperature prior to each i 5'" .-Y, ~ .'Vi

-startup of a "L: X. ox. "-.

'y red rcu 1at ion pump IWithin the limits specified in the PTLR. I SR 3.4.9.4 -------------------NOTE--------------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor Once within coolant temperature in the recirculation 15 minutes loop to be sta~he RPV coolant prior to each temperature ~l

startup of a recirculation pump IWithin the limits specified in the PTLR. I (continued)

PBAPS UNIT 3 3.4-23 Amendment No. 214

RC S P/ r Lim its 3.4 . cJ C;lJf~VE I LLANCE f~EOU (REMEN rs (cant i n'Jed)

SURVEILLANCE FREQUENCY SR 3.1.9.5 .-- -. -~ - . - - NO TE.. - . - - ---- - ..

Only required to be performed when tensioninq the reactor v~ssel head bolting

'i tuds.

Veri fy reactor vessel f ~ head In accordance flange temperatures d r e ~ with the Surveillance Frequency within the limits specified in the PTLR. Control Program .

SR 3.4.9.6 .. - - - .. - - .... - - - - .. - - - ..... NOTE ..... - - .. - - - .......... - ........ - . .

Not required to be performed until 30 minutes after ReS temperature S 80°F in MODE 4.

Veri fy reactor vessel fl~ head In accordance flange temperatures are~~~~~ with the Surveillance Frequency within the limits specified in the PTLR. Control Program.

SR 3.4.9.7 _.. - - - - - - - - - - _.. - - - - -NOTE- - - - - - - - - - - - - - - - - --

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after ReS temperature S lOQoF in MODE 4.

Veri fy reactor vessel fl head In accordance flange temperatures are~~~--J with the Surveillance Frequency within the limits specified in the PTLR. Control Program.

PBAPS UNIT 3 3.4-24 Amendment No. 281

Res PIT L1l11i

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PBAPS UNIT 3 3.4-26 Amendment No. 263

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PBAPS UNIT 3 3.4-27 Amendment No.263

Repo r t i nq RF~q u i rf*~,n~n t$

S.h 5.6.5 CORE QPERATING LlMlTS REPORT <<(OLB) (continued)

1. PEC*o . FMS*Q005*A, "Methods for Performing BWR Steady .

State Reactor Physics Analysis";

8. PECo*FMS . Q006 . A, "Methods for Performing BWR Reload Sdfety Evaluations"; and

9. NEDO*32465*A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology And Reload Applications," August 1996.

c. The core operating limits shall be determined such that all d pP1; cab 1e '1 i mi t 5 (e. 9 ., f ue 1 the rma 1 me chan i cal '1 i mit s ,

core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM. transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COlR. including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report ;s required by Condition B or F of LCO 3.3.3.1, If Pas t Ace; dent M0 n ; tor; n g ( PAM) Ins t r ume ntat ; on ," a report shal 1 be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. ReS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the follOWing:

i) Limiting Conditions for Operation Section 3.4.9, "ReS Pressure and Temperature (prr) Limits" ii) Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits"

b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the follOWing document:

i) NEDC-33178P-A, "GE Hitachi Nuclear Energy Methodology for Development of Reactor Pressure Vessel Pressure-Temperature Curves, It Revision 1, June 2009

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

PBAPS UNIT 3 5.0-22 Amendment No. 254

Res PIT limits B 3.4.9 B 3.4 REACTOR COOlANT SYSTEM (ReS)

B 3.4.9 Res Pressure and Temperature (PIT) Limits BASES BACKGROUND All components of the ReS are designed to withstand effects of cyclic loads due to syste. pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LeO limits the pressure and temperature changes during ReS heatup and cool down , within the design assumptions and the stress limits for cyclic operation.

~onta1nsPIT limit curves for heatup, The PRESSURE AND , rvlce leakage and hydrostatic testing, and TEMPERATURE LIMITS also limits the maximum rate of change of reactor coolant REPORT (PTLR) (Ref. 9) temperature. The criticality curve provides limits for both heatup and criticality.

Each PIT limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and

( compared to the applicable curve to determine that operation is within the allowable region.

The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RePB). The vessel is the component most subject to brittle failure. Therefore, the LCO limits apply to the vessel.

10 CFR 50, Appendix G (Ref. 1), requires the establishment of PIT limits for material fracture toughness requirements of the Reps materials. Reference 1 requires an adequate margin to brittle failure during normal operation, abnormal operational transients, and system hydrostatic tests. It mandates the use of the ASHE Code, Section lIlt Append;x G (Ref. 2).

The actual shift in the RT.T of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with the UFSAR (Ref. 3) and Appendix H of 10 CFR 50 (Ref. 4). The operating PIT limit curves will be adjusted, as necessary, based on the evaluation findings and the recommendat;ons of Reference 5.

(continued)

PBAPS UNIT 3 B 3.4-43 Revision No. 0

RCS PIT Limits B 3.4.9 BASES BACKGROUND:

. ',:' '.~

(cant 1nued)**

~.. ::", .

r'~. **f;**,:*

PBAPS. UNIT 3: Revision No. 0

RCS PIT Limits 8 3.4.9 BASES APPLICABLE RCS PIT limits satisfy Criterion 2 of the NRC Policy SAFETY ANALYSES Statement.

(continued) lCO The elements of this

a. RCS pressure~~lo;Y. . .1':l;J~Il~.~~~""V~~""ir~

an c oldown specified i ~~~~S~lllili~il;~ .,

The temperature difference between the reactor vessel bottom head coo1a the reactor pressure vessel (RPY) coolant i during recirculation pump startup; e temperature difference between the reactor coolant in the respective 1ation loop and in the reactor vessel i uring recirculation pump s artup;

d. RCS pressure and temperature a

( criticality limits specified i ~~~~~~~ rior to achieving criticality; and

e. e and the head flange

~~~~when tensioning the reactor s.

These limits define allowable operating regions and permit a large number of operating cycles while also providing a wide margin to nonducti1e failure.

The rate of change of temperature limits controls the thermal gradient through the vessel wall and is used as input for calculating the heatup, cool down, and inservice leakage and hydrostatic testing PIT limit curves. Thus, the lCO for the rate of change of temperature restricts stresses caused by thermal gradients and also ensures the validity of the PIT limit curves.

(continued)

PBAPS UNIT 3 B 3.4-45 Revision No. 0

Res PIT Limits B 3.4.9 BASES LCO Violation of the limits places the reactor vessel outside of (continued) the bounds of the stress analyses and can increase stresses in other ReS components. The consequences depend on several factors, as follows:

a. The severity of the departure from the allowable operating pressure temperature regime or the severity of the rate of change of temperature;

b. The length of time the limits were violated (longer violations allow the temperature grad'1ent in the thick vessel walls to become more pronounced); and

c. The existences, sizes, and orientations of flaws in the vessel material.

APPLICABILITY The potential for violating a PIT limit exists at all times.

For example, PIT limit violations could result from ambient temperature conditions that result in the reactor vessel metal temperature being less than the minimum allowed temperature for boltup. Therefore, this LeO is applicable even when fuel is not loaded in the core.

-1in the PTLR ACTIONS A*1 an_d A*-2 It: ..n _

Operation outside the PIT limits while in MODES 1, 2, and 3 must be corrected so that the RepS is returned to a condition that has been verified by stress analyses.

The 30 minute Completion Time reflects the urgency of restoring the parameters to within the analyzed range. Most violations will not be severe, and the activity can be accomplished in this time in a controlled manner.

Besides restoring operation within limits, an evaluation is required to dete~1ne if ReS operation can continue. The evaluation must verify the RepS integrity remains acceptable and must be completed if continued operation is desired.

Several methods may be used, including comparison with pre-analyzed transients in the stress analyses, new analyses, or inspection of the components.

ASHE Code,Section XI, Append;x E (Ref. 6), may be used to support the evaluat;on. However, its use is restricted to evaluation of the vessel beltl1ne.

(continued)

PBAPS UNIT 3 8 3.4-46 Revision No. 0

Res PIT L im1 ts B 3.4.9 BASES ACTIONS A,l and A.Z (continued)

The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable to accomplish the evaluation of a .ild violation. More severe violations may require special, event specific stress analyses or inspections. A favorable evaluation must be completed if continued operation is desired.

Condition A is modified by a Note requiring Required Action A.2 be cOMpleted whenever the Condition is entered.

The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits.

Restoration alone per Required Action A.I is insufficient because higher than analyzed stresses may have occurred and may have affected the RepS integrity.

B.1 and 8.2 If a Required Action and associated Completion Time of Condition A are not met, the plant must be placed in a lower MODE because either the Res remained in an unacceptable PIT region for an extended period of increased stress, or a

( sufficiently severe event caused entry into an unacceptable region. Either possibility indicates a need for more careful examination of the event, best accomplished with the Res at reduced pressure and temperature. With the reduced pressure and temperature conditions, the possibility of propagation of undetected flaws is decreased.

Pressure and temperature are reduced by placing the plant in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

in the PTLR e.1 and C.2 Operation outside the PIT limits n other than MODES 1, 2, and 3 (including defueled conditions) must be corrected so that the Rep8 is returned to a condition that has been verified by stress analyses. The Required Action must be initiated without delay and continued until the limits are restored.

(continued)

PBAPS UNIT 3 B 3.4-47 Revision No. 0

f~ CS P/ r l. i mit s B 3.4.9 RASES ACTIONS e.l dod e.2 (continued)

Besides restoring the PIT l1mit parameters to within 1 imits.

an evaluation is required to determine if ReS operation is allowed. rhts evaluation must verify that the RepS integrity is acceptable and must be completed before approaching critical1ty or heat1ng up to > 212°F. Several methods may be used, including comparison with pre-analyzed transients, new analyses, or inspection of the components.

ASME Code,Section XI, Appendix E (Ref. 6), may be used to support the evaluation; however, its use is restricted to evaluation of the beltline.

SURVEILLANCE 58 3.4,9,1 ~TLR I REQUIREMENTS Verification that operation is within lmits is required when ReS pressure and temperature conditions are undergoing planned changes. Plant procedures specify the pressure and temperature monitoring points to be used during the performance of this Surveillance. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

Surveillance for heatup, cooldown. or inservice leakage and hydrostatic testing may be discontinued when the criteria given in the relevant plant procedure for ending the activity are satisfied.

This SR has been modified with a Note that requires this Surveillance to be performed only during system heatup and cooldown operations and ;nserv;ce leakage and hydrostatic testing.

SR 3,4,9,2 ~inthePTLR A separate limit~ used when the reactor is approaching criticality. Consequently, the ReS pressure and temperature must be verified within the appropriate limits before withdrawing control rods that will make the reactor critical.

(continued)

PBAPS UNIT 3 B 3.4-48 Revision No. 87

Res PIT Limits B 3.4.9 BASES SURVEILLANCE SR 3,4,9,2 (continued)

REQUIREMENTS Perfo~ing the Surveillance within 15 minutes before control rod withdrawal for the purpose of achieving criticality provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the control rod withdrawal.

in the PTLR SR 3.4,9,3 and sa 3.4,9,4 Differential temperatures within the applicable limits ensure that thermal stresses resulting from the startup of an idle recirculation pump will not exceed design allowances. In addition, compliance with these limits ensures that the assumptions of the analysis for the startup of an idle recirculation loop (Ref. 8) are satisfied.

Performing the Surveillance within 15 minutes before starting the idle recirculation pump provides adequate assurance that the limits will not be exceeded between the time of the Surveillance and the time of the idle pump start.

An acceptable means of demonstrating compliance with the temperature differential requirement in SR 3.4.9,4 is to compare the temperatures of the operating recirculation loop and the idle loop.

SR 3,4.9.3 and SR 3.4.9.4 have been modified by a Note that requires the Surveillance to be met only in MODES 1, 2, 3, and 4. In MODE 5, the overall stress on limiting components is lower. Therefore, 41 limits are not required. The Note also states the SR is only required to be met during a recirculation pump startup, since this is when the stresses occur.

SR 3,4.9.5, S8 3.4.9.6, and S8 3.4.9.7 lin the PTLR

~ on the reactor vessel flange and head flange temperatures are generally bounded by the other PIT limits during system heatup*and cooldown. However, operations approaching MODE 4 from MODE 5 and in MODE 4 with ReS temperature less than or equal to certain specified values require assurance that these temperatures meet the lCO 1imits.

(continued)

PBAPS UNIT 3 B 3.4-49 Revision No. 0

I~ CS P/ r Lim j t 5 B 3.4.9 BASES SURVEILLANCE S8 3,4.9,5. 58 3.4.9,6. dod 58 ),4.9,7 (continued)

REQUIREMENTS lin the PTLR ~nge temperatures must be verified to be dbove the lim" before and while tensioning the vessel head boltlng studs to ensure that once the head is tensioned the limits are satisfied. When in MODE 4 with ReS temperature s 80°F, checks of the flange temperatures are required because of the reduced margin to the limits. When in MODE 4 with ReS temperature ~ lOO°F, monitoring of the flange temperature is required to ensure the temperature is within the limits specifi in the PTLR he Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.4.9.5 is mOdified by a Note that requires the Surveillance to be performed only when tensioning the reactor vessel head bolting studs. SR 3.4.9.6 is modified by a Note that requires the Surveillance to be initiated after ReS temperature s 80°F in MODE 4. SR 3.4.9.7 is modified by a Note that requires the Surveillance to be initiated after ReS temperature S lOQoF in MODE 4. The Notes

( contained in these SRs are necessary to specify when the reactor vessel flange and head flange temperatures are required to be verified to be within the limits specified.

REFERENCES 1. 10 CFR 50, Appendix G.

2. ASME. Boiler and Pressure Vessel Code,Section III, Appendix G.

3. UFSAR, Section 4.2.6 and Appendix K.

4. 10 CFR 50, Appendix H.

5. Regulatory Guide 1.99, Revision 2, May 1988.

(continued)

PBAPS UNIT 3 B 3.4-50 Revision No. 87

Res PIT limits B 3.4.9 BASES REFERENCES 6. ASHE, Boiler and Pressure Vessel Code,Section XI, (continued) A pendix E.

9. PRESSURE AND TEMPERATURE LIMITS REPORT.

PBAPS UNIT 3 B 3.4-51 Revision No. 0

ATTACHMENT 5 Non-Proprietary Version - Peach Bottom Atomic Power Station Unit 2 and Unit 3 Pressure and Temperature Limits Report

Attachment 1

~~11 e-I-I~

ELECTRIC POWeR RESEARCH INSTITUTE NEIL WILMSHUUT Vice President and Chief Nuclear ofRc.,

Rel EPRI Project Number 669 April 17, 2012 Document Control Desk Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Andrew Hon

Subject:

Request for Withholding of the following Proprietary Information Included in:

Exelon/Peach Bottom Atomic Power Station (PBAPS) Unit 2 & Unit 3 Pressure and Temperature Limits Report (PTLR) up to 32 and 54 Effective Full-Power Years Revision 0 To Whom It May Concem:

This is a request under 10 C.F.R. §2.390(a)(4) that the U.S. Nuclear Regulatory Commission ("NRCj withhold from public disclosure the report identified in the enclosed Affidav~ consisting of the proprietary information owned by Electric Power Research Institute, Inc. ("EPRI1 identified in the attached report. Proprietary and non-proprietary versions of the Report and the Affidavit in support of this request are enclosed.

EPRI desires to disclose the Proprietary Information in confidence for informational purposes regarding a submittal to the NRC by Exelon Corporation. The Proprietary Information is not to be divulged to anyone outside of the NRC or to any of its contractors, nor shall any copies be made of the Proprietary Information provided herein. EPRI welcomes any discussions and/or questions relating to the information enclosed.

If you have any questions about the legal aspects of this request for withholding, please do not hesitate to contact me at (704) 704-595-2732. Questions on the content of the Proprietary Information should be directed to Randy Stark of EPRI at (650) 855-2122.

c: Sheldon Stuchel', NRC (Sheldon.stuchell@nrc.gov)

Together . . . Shaping the future of Electricity 1300 WestW.T. Hams Boulevard, Charlotte, NC 28262-8550 USA. 704.595.2732

Mobile 704.490.2653

nwilmshurstOepri.com

~~~II ELECTRIC POWER

~I-Ic;;. RESEARCH INSTITUTE AFFIDAVIT RE: Request for Withholding of the Following Proprietary Information Included In::

Exelon/Peach Bottom Atomic Power Station (PBAPS) Unit 2 &Unit 3 Pressure and Temperature Limits Report (PTLR) up to 32 and 54 Effective Full-Power Years Revision 0 I, Neil Wilmshurst, being duly sworn, depose and state as follows:

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Executed at 1300 W WT Harris Blvd being the premises and place of business of Electric Power Research Institute, Inc.

oa/l] 4- IJ - )..011.

Neil Wilmsg...... e--=--------------

(State of North Carolina)

(County of Mecklenburg)

Subscribed and ~ (or affirmed) before me on this J'l'*aay of ~ , 2016 by

--'71Jil W~ I proved to me on the basis of'ttistactory evidence to be the person(s) who appeared before me.

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My Commission Expires ..It ~ay of ~ I 20!.i

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ lit EXELON/PEACH BOTTOM ATOMIC POWER STATION (PBAPS)

UNIT 2 & UNIT 3 Pressure and Temperature Limits Report (PTLR) up to 32 and 54 Effective Full-Power Years Revision 0

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" Table of Contents Section 1.0 Purpose 3 2.0 Applicability 3 3.0 Methodology 3 4.0 Operating Limits 5 5.0 Discussion 6 6.0 References 9 Figure 1- Unit 2 Composite Curve A Pressure Test P-T Curves Effective for up to 32 EFPY 11 Figure 2 - Unit 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 32 EFPY 12 Figure 3 - Unit 2 Limiting Curve C Core Critical P-T Curves Effective for up to 32 EFPY 13 Figure 4 - Unit 2 Composite Curve A Pressure Test P-T Curves Effective for up to 54 EFPY 14 Figure 5 - Unit 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 54 EFPY 15 Figure 6 - Unit 2 Limiting Curve C Core Critical P-T Curves Effective for up to 54 EFPY 16 Figure 7 - Unit 3 Composite Curve A Pressure Test P-T Curves Effective for up to 32 EFPY 17 Figure 8 - Unit 3 Composite Curve B Core Not Critical P-T Curves Effective for up to 32 EFPY 18 Figure 9 - Unit 3 Limiting Curve C Core Critical P-T Curves Effective for up to 32 EFPY 19 Figure 10 - Unit 3 Composite Curve A Pressure Test P-T Curves Effective for up to 54 EFPY 20 Figure 11- Unit 3 Composite Curve B Core Not Critical P-T Curves Effective for up to 54 EFPY 21 Figure 12 - Unit 3 Limiting Curve C Core Critical P-T Curves Effective for up to 54 EFPY 22 Table 1 - Unit 2 Tabulation of Curves - 32 EFPY 23 Table 2 - Unit 2 Tabulation of Curves - 54 EFPY 28 Table 3 - Unit 3 Tabulation of Curves - 32 EFPY 33 Table 4 - Unit 3 Tabulation of Curves - 54 EFPY 38 Appendix A: Reactor Vessel Material Surveillance Program 43 Appendix B: PBAPS Unit 2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information 44 Appendix C: PBAPS Unit 3 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information 56 Appendix D: PBAPS Unit 2 and Unit 3 Reactor Pressure Vessel P-T Curve Checklist 69 2

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by"[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIV~'DATE]

1.0 Purpose The purpose of the PBAPS Unit 2 and Unit 3 Pressure and Temperature Limits Reports (PTLR) is to present operating limits relating to:

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

2. RCS Heatup and Cooldown rates;

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

4. RPV bottom head coolant temperature to RPV coolant temperature L\T requirements during Recirculation Pump startups;

5. RPV head flange bolt-up temperature limits.

This report has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.7, "Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)".

2.0 Applicability This report is applicable to the PBAPS Unit 2 and Unit 3 RPVs for up to 32 and 54 Effective Full-Power Years (EFPY).

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

TS 3.4.9 RCS Pressure and Temperature (P/T) Limits 3.0 Methodology The limits in this report were derived from the NRC-approved methods listed in TS 5.6.7, using the specific revisions listed below:

1. The neutron fluence was calculated per Licensing Topical Report, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation, NEDC-32983P-A, Revision 2, January 2006, approved in Reference 6.1.

3

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ lit PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVe~ DATE]

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.

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

Initial issuance of the PTLR

Application of GEH Topical Report for P-T Curves

Fluence application for operation at 3951 Mwt As discussed in Appendix A, PBAPS Unit 2 and Unit 3 participate in the BWRVIP Integrated Surveillance Program (lSP). Unit 2 is a host plant and is scheduled to remove its second capsule at 33.7 EFPY. The third Unit 2 capsule is classified as a standby capsule. As Unit 3 is not a host plant, the surveillance capsules have an ISP status designation of deferred (standby) per Reference 6.4.

The adjusted reference temperature (ART) values for 32 and 54 EFPY included in Appendix B (Unit 2) and Appendix C (Unit 3) are developed considering the latest ISP published surveillance data available that is representative of the applicable materials in the PBAPS Unit 2 and Unit 3 RPV beltline (Reference 6.3). The surveillance data used in the Unit 2 ART calculations is obtained from actual Unit 2 RPV test specimens; the surveillance data used in the Unit 3 ART calculations is not obtained from actual PBAPS Unit 3 RPV test specimens. For Unit 2, the ISP materials did not have the limiting ART.

For Unit 3, the ISP plate material has the limiting ART; however, this value is not considered in the development of the P-T curves because the ISP material is not the identical heat to the material in the Unit 3 RPV.

Should actual surveillance capsules be withdrawn and tested from the PBAPS Unit 3 RPV (e.g., status change to be an ISP host plant under the BWRVIP ISP), compliance with 10 CFR 50 Appendix H requirements on reporting test results and evaluations on the effects to plant operations parameters (e.g., P-T limits, hydrostatic and leak test conditions) will be in accordance with Section 3 of Reference 6.3.

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EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVtl, DATE]

Changes to the curves, limits, or parameters within this PTLR, based upon new irradiation fluence data of the RPV, or other plant design assumptions in the Updated Final Safety Analysis Report (UFSAR), can be made pursuant to 10 CFR 50.59, provided the above methodologies are utilized. The revised PTLR shall be submitted to the NRC upon issuance.

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.

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.

Complete P-T curves were developed for 32 and 54 EFPY. The P-T curves are provided in Figures 1 through 12, and a tabulation of the curves is included in Table 1 (32 EFPY) and Table 2 (54 EFPY) for Unit 2 and in Table 3 (32 EFPY) and Table 4 (54 EFPY) for Unit 3.

Other temperature limits applicable to the RPV are:

Heatup and Cooldown rate limit during Hydrostatic and Class 1 Leak Testing: ~

20 of/hour.

Normal Operating Heatup and Cooldown rate limit: ~ 100 of/hour.

RPV bottom head coolant temperature to RPV coolant temperature ~T limit during Recirculation Pump startup: ~ 145 of.

Recirculation loop coolant temperature to RPV coolant temperature ~T limit during Recirculation Pump startup: ~ 50 of.

RPV flange and adjacent shell temperature limit: ~ 70 of.

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[EFFEcrlv~r DAI$]

5.0 Discussion The computer codes described in References 6.1 and 6.2 were used in the development of the P-T curves for PBAPS Units 2 and 3.

The method for determining the Initial Reference Temperature of Nil-Ductility Transition (RTNOT) for all vessel materials is defined in Section 4.1.2 of Reference 6.2. Initial RTNOT values for all vessel materials considered are presented in tables in Appendix B (for Unit

2) and Appendix C (for Unit 3) of this report.

For PBAPS Unit 2, the limiting surveillance material, plate heat C2761-2, was considered using Procedure 2 as defined in Appendix I of Reference 6.2. This procedure was used because the target vessel material and the surveillance material are not identical heats.

However, C2761-2 is a beltline plate in the PBAPS Unit 2 vessel, with only one set of test results. The surveillance data should be considered after a second surveillance capsule is tested and credible surveillance data is available.

For PBAPS Unit 3, the limiting surveillance material, plate heat B0673-1, was considered using Procedure 2 as defined in Appendix I of Reference 6.2. This procedure was used because the target vessel material and the surveillance material are not identical heats.

For PBAPS Unit 2, there are four (4) thickness discontinuities in the vessel: (1) between the bottom head dollar plate and the bottom head torus, (2 and 3) between the bottom head torus and the support skirt attachment at two locations, and (4) between the bottom head torus and Shell Ring #1. The P-T curves defined in Section 4.3 of Reference 6.2 are based upon an RTNOT of 50°F for the bottom head Curves A and C, 46°F for the bottom head Curve B, and 48°F for the upper vessel. The 32 EFPY beltline curves are based on an ART of 50°F, and the 54 EFPY beltline curves are based on an ART of 64.2°F.

Curves based on these temperatures bound the requirements due to the thickness discontinuities.

For PBAPS Unit 3, there are four (4) thickness discontinuities in the vessel: (1) between the bottom head dollar plate and the bottom head torus, (2 and 3) between the bottom head torus and the support skirt attachment at two locations, and (4) between the bottom head torus and Shell Ring #1. The P-T curves defined in Section 4.3 of Reference 6.2 are based upon an RTNOT of 54°F for the bottom head Curves A and C, 42°F for the bottom head Curve B, and 44°F for the upper vessel. The 32 EFPY beltline curves are 6

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

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based on an ART of 78.3°F, and the 54 EFPY beltline curves are based on an ART of S8.6°F. Curves based on these temperatures bound the requirements due to 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 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 the N16 nozzle, were obtained from plant-specific vessel purchase order records, Certified Material Test Reports (CMTRs). The N16 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 Shell Ring #2. The copper (Cu) and nickel (Ni) values were used with Tables 1 and 2 of RG 1.99, to determine a chemistry factor (CF) per Paragraph 1.1 of RG 1.99 for welds and plates, respectively.

ART values for 32 and 54 EFPY are presented in Appendix B for Unit 2 and Appendix C for Unit 3. The ART tables also include plant-specific materials considering best estimate chemistry values obtained from Reference 6.3.

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 PBAPS Unit 2 and Unit 3 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 PBAPS using plant-specific RTNOT values for the reactor pressure vessel.

The peak RPV 10 fluence used in the P-T curve evaluation for Unit 2 at 32 EFPY is 2 2 9.54e17 n/cm and at 54 EFPY is 1.61e18 n/cm

These values were calculated using methods that comply with the guidelines of RG 1.190, (as discussed in Reference 6.1).

This fluence applies to the lower-intermediate shell plates and longitudinal welds. The fluence is adjusted for the lower plates, associated longitudinal welds, and the girth weld based upon an attenuation factor of 0.764; hence, the peak 10 surface fluence for 2

these components is 7.2ge17 n/cm for 32 EFPY and 1.23e18 n/cm 2 for 54 EFPY.

Similarly, the fluence is adjusted for the N16 nozzle based upon an attenuation factor of 7

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by n[ In PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE~IV6~OAJ~]

2 0.353; hence the peak 10 surface fluence used for this component is 3.37e17 n/cm for 2

32 EFPY and 5.6ge17 n/cm for 54 EFPY.

The peak RPV 10 fluence used in the P-T curve evaluation for Unit 3 at 32 EFPY is 9.07e17 n/cm 2 and at 54 EFPY is 1.53e18 n/cm 2

These values were calculated using methods that comply with the gUidelines of RG 1.190, (as discussed in Reference 6.1).

This fluence applies to the lower-intermediate shell plates and longitudinal welds. The fluence is adjusted for the lower plates, associated longitudinal welds, and the girth weld based upon an attenuation factor of 0.62; hence, the peak 10 surface fluence for 2

these components is 5.62e17 n/cm for 32 EFPY and 9.48e17 n/cm 2 for 54 EFPY. PBAPS Unit 3 has an additional intermediate shell in the beltline region. The fluence for the peak location in this shell is based upon an attenuation factor of 0.624; hence, the peak 10 surface fluence for these components is 5.65e17 n/cm 2 for 32 EFPY and 2

9.54e17 n/cm for 54 EFPY. Similarly, the fluence is adjusted for the N16 nozzle based upon an attenuation factor of 0.372; hence the peak 10 surface fluence used for this 2

component is 3.37e17 n/cm for 32 EFPY and 5.6ge17 n/cm 2 for 54 EFPY.

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, Klr, 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 8

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

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(Curve A), a coolant heatup and cooldown temperature rate of :5: 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 PBAPS Unit 2, plate heat C2873-1 is the limiting material for the beltline region for 32 and 54 EFPY. The initial RTNOT for plate heat C2873-1 material is -GoF. The generic pressure test P-T curve is applied to the PBAPS Unit 2 beltline curve by shifting the P vs.

(T - RTNOT) values to reflect the ART value of 50°F for 32 EFPY and 64.2°F for 54 EFPY.

Using the fluence discussed above, the P-T curves are not beltline limited for Curves A, B, or C, for 32 or 54 EFPY.

For PBAPS Unit 3, plate heat C2773-2 is the limiting material for the beltline region for 32 and 54 EFPY. The initial RTNDT for plate heat C2773-2 material is 10°F. The generic pressure test P-T curve is applied to the PBAPS Unit 3 beltline curve by shifting the P vs.

(T - RTNDT) values to reflect the ART value of 78.3°F for 32 EFPY and 88.6°F for 54 EFPY.

Using the fluence discussed above, the P-T curves are not beltline limited for Curves A, B, or C, for 32 EFPY. For 54 EFPY, Curve A is beltline limited at pressures above 1070 psig and Curves Band Care beltline limited at pressures above 1160 psig.

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 of Reference 6.2 for the non-beltline and beltline regions, respectively, are applied.

6.0 References 6.1 Final Safety Evaluation Regarding Removal of Methodology Limitations for NEDG-32983P-A, General Electric Methodology for Reactor Pressure Vessel Fast Neutron Flux Evaluation (TAG NO. MG3788), November 17, 2005.

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

April 27, 2009.

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EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[E FFEt:llVS';OAT_l 6.3 BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations, BWRVIP-135, Revision 1, EPRI, Palo Alto, CA, June 2007 (EPRI Proprietary) 6.4 BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan, BWRVIP-86, Revision 1, EPRI, Palo Alto, CA:

September 2008. 1016575. (EPRI Proprietary) 6.5 Pressure-Temperature Limits Report for Exe/on Generation Company LLC, Peach Bottom Atomic Power Station Unit 2, 0000-0107-8606-R1, Revision 1, Class III (GEH Proprietary Information), March 2012 6.6 Pressure-Temperature Limits Report for Exelon Generation Company LLC, Peach Bottom Atomic Power Station Unit 3, 0000-0133-0506-R1, Revision 1, Class III (GEH Proprietary Information), March 2012 6.7 Peach Bottom Atomic Power Station Unit 2 Vessel Surveillance Materials Testing and Fracture Toughness Analysis, SASR 88-24, Revision 1, DRF B13-01445-1, Class I, December 1991 6.8 Peach Bottom Atomic Power Station Unit 3 Vessel Surveillance Materials Testing and Fracture Toughness Analysis, SASR 90-50, Revision 1, DRF B11-00494, Class I, July 1995 10

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by tI[ )"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE~ OATE]

Figure 1- Unit 2 Composite Curve A Pressure Test P-T Curves Effective for up to 32 EFPY 1400 1300 i

I I J INITIALRTNJT VALUES ARE

-e-F FOR BELTlINE, 1200 4rF FOR UPPER 1100

/ I VESSEL, AND 5o-F FOR BOTTOM HEAD a

11000 1/ I eaniNECURVE5

~

ADJUSTED Na SHOWN:

900 i EFPV SHIFTrF) 32 58

/

Go 0

I-LLI 800 a

> j I

lIl: 100 0

I-

~ 600

/ ACCEPTABLE REGION ~

HEATUPICOOLOOWN RATE OF coa.ANT

~2O"FIHR lIl:

OF OPERATION IS TO

~

l- THE RIGHTOFTHE i 500 BOTTOM APPLICABLE CURVE f--

~ HEAD w 68'F lIl:

~

400 w

lIl: 312 PSIGI Go 300 FLANGE -UPPER VESSEL 200 REGION AND BELTUNE

~ 70'F LIMITS

~ ------- BOTTOM HEAD 100 CURVE 0

o 25 so 15 100 125 150 175 200 MINIMUM REACTORVE88EL METAL TEMPERATURE rF) 11

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVEDAT~]

Figure 2 - Unit 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 32 EFPY 1400 1

1300 j INITIALRTNOT VALUES ARe 1200 ': FOR BeLTUNE, 1100 7 WF FOR UPPER veSSEL, AND 4trF FOR BOTTOM HEAD a

11000 ;I

~

c 900 I BeLTLINE CURVES ADJUSTeD AS SHOWN:

eFPY SHIFT rF)

A.

o I-

. 32 58 id 800

!> /II Ill: 700 '-

~

ACCEPTABLE REGION OF HEATUPICOOLOOWN RATE OF COOLANT Ill: 600

/ " OPERATION IS ..... ~ 100-FIHR l:

I-

~500 I~/ J TO THE RIGHT OF THE APPLICABLE CURVE '-

w 400 I

7 1A. 300 -

BOTTOM HEAD .. 1312PSIG V

68"F 200 -UPPER VESSEL AND BelTLI NE

/ /

FLANGE REGION LIMITS

BOTTOM HEAD 100 I

.V 700F I

CURVE o I o 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTORYE88EL METAL TEMPERATURE rF) 12

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE PATE]

Figure 3 - Unit 2 Limiting Curve C Core Critical P-T Curves Effective for up to 32 EFPY 1400 INITIALRTfOr VALUES 1300 ARE

-e-F FOR eELTLINE, 48-': FOR UPPER 1200 veSSEL, AHD 50,: FOR BOTTOM HEAD 1100 a

).1000 BELTlINE CURVE ADJUSTED A.S SHOWN:

~900 EFPV SHIFT rF) 32 58 o

I-m800 HEATUPICOOlOOWN

!> RATE OF COOLANT

~ 100-FIHR oa= 700

~ 800 il j l-isco II

J 'I ACCEPTABLE w REGION OF a=

OPERATION IS

~4QO TO THE RIGHT faa=

A. 300 1312 PSiG I

I - OF THE APPLICABLE CURVE 200

/

/ I -BELTLINE AND NON-BELTLINE 100 Minimum Vessel r?

e:-- ...- Temperatura 70 D F I I I'-- LIMITS o

o 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTORVE88EL METAL TEMPERATURE(*F) 13

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PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFECTIVE DATE]

Figure 4 - Unit 2 Composite Curve A Pressure Test P-T Curves Effective for up to 54 EFPY 1400 1300 ,i II JI INITIAL RTfIJT VALUES ARE

.= FOR BELTLINE, 1200 4rF FOR UPPER 1100

/ I vessel, AND 5O-F FOR BOTTOM HEAD a

11000 1/

~

aanlNECURVES ADJUSTED AS SHOWN:

A.

900 ,I EFPV SHIFT ('"F) 54 70.2 0

11.1 800

/

a V

lllI: 700 0

I-

/ HEATUPICOOLOOWN

~lllI: 800 ACCEPTABLE REGION OF OPERATION IS TO I--

RATE OF COOLANT

~ 2O"FIHR

~ THE RIGHT OF THE l-i 500 APPLICABLE CURVE I--

BODOM

1 HEAD 11.1 OO"F lllI:

i11.1 lllI:

400 312 PSIG a.

300 FLANGE -UPPER VESSEL 200 REGION AND BELTUNE

~ 70"F LIMITS

~ ------- BonOM HEAD 100 CURVE I

I I

0 o 25 50 75 100 125 150 175 200 MINIMUM REACTORVE88EL METAL TEMPERATURErF) 14

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVEOATEj Figure 5 - Unit 2 Composite Curve B Core Not Critical P-T Curves Effective for up to 54 EFPY 1400

/

1300 INITIAL RTMDT VALUES 1200

! ARE 1100 I -e~ FOR BELTlINE, 48-F FOR UPPeR VESSEL, AND

/

46-F FOR BOTTOM HEAD 1i1 11000 Q,

900 I BELn.INE CURVES ADJUSTED AS SHOWN:

EFPV SHIFT rF) 54 70.2 0

t-id ,i a

~

800 700 /

0 t- II HEATUPICOOLDOWN

~ 600 / RATE OF COOLANT l/ ~

~ 1cxrFIHR t-i 500 J ACCEPTABLE REGION

3 w

~ I OF OPERATION IS TO THE RIGHT OF THE APPLICABLE CURVE

~

w 400

~

Q, 300 -

BOTTOM HEAD 68*f

. 11312 PSIGl 200

, I -UPPER VESSEL 100

'/ ./

FlANGE REGION 700f AND BELTLI NE LIMITS

BOTTOM HEAD JIt V CURVE 0

o 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTORVE88EL METAL TEMPERATURErF) 15

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE~DATE]

Figure 6 - Unit 2 Limiting Curve C Core Critical P-T Curves Effective for up to 54 EFPY 1400 INITIALRTNJT VALUES 1300 ARE

': FOR BELTLINE, 48-': FOR UPPER 1200 VEssel, AND 50-': FOR BOTTOM HEAD 1100 BELTLINE CURVE ADJUSTED AS SHOWN:

EFPY SHIFT ("F) 54 70.2 HEATUPICOOLOOWN RATE OF COOlANT

~ 100-FMR

~

II'I ACCEPTABLE REGION OF OPERATION IS TO THE RIGHT OF 1312 PSIGI I

- THE CURVE 200 I

/

/ -BELTLINE AND NON-BELTLINE 100 Minimum Vessel ~

LIMITS r~ t:-

~ Temperature 70°F o I I o 25 50 15 100 125 150 115 200 225 250 MINIMUM REACTORVE88EL METAL TEMPERATURErF) 16

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTiVe DATE]

Figure 7 - Unit 3 Composite Curve A Pressure Test peT Curves Effective for up to 32 EFPY 1400

~

I I 1300 INITIAL RTfIJ1' VALUES 1200

/ J ARE 10eF FOR BELTLlNE, 44"F FOR UPPER 1100

/ vessa.,

AND 54-': FOR BOTTOM HEAD

/'J ~ eanlNe CURVES

/

I ADJUSTED AS SHOWN:

EFPV SHIFT ("F) 32 68.3

/

J l/ /

II ACCEPTABLE REGION ~

OF OPERATION IS TO HEATUPICOOLOOWN THE RIGHTOFTHE RATE OF COOlANT APPLICABLE CURVE ~ ,S2o-F1HR BOTTOM HEAD 68°F 1312 PSIGI FlANGE -UPPER VESSEL REGION AND BELTLI NE 200

~ 70"F .

LIMITS

~ ------- BOTTOM HEAD 100 CURVE o

o 25 50 75 100 125 150 175 200 MINIMUM REACTORVE88EL METAL TEMPERAnJRErF) 17

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE OAtS]

Figure 8 - Unit 3 Composite Curve B Core Not Critical P-T Curves Effective for up to 32 EFPY 1400 1300 1200 ,I INITIAL RTfQI' VALUES ARE 1O'"F FOR BELT1.INE, 1100 f 44~ FOR UPPER VESSEL, AND 4rF FOR BOTTOM HEAD I

I BELTLINE CURVES ADJUSTED N3 SHOWN:

EFPY SHIFT rF)

! 32 68.3 I

I Ii

/

I ACCEPTABLE f-HEATUPICOOLOOWN RATE OF COOlANT 1/ I REGION OF OPERATION IS TO

~

S 10O'"FIHR THE RIGHTOFTHE I APPLICABLE CURVE BOTTOM HEAD 68°F - 1312PSIGI 200

/ - UPPER VESSEL ANDBELTUNE 1/ ~

FLANGE REGION LIMITS 100 o

V I

V 700F ------- BOTTOM HEAD CURVE o 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTORVE88EL METAL TEMPERAnJRE rF) 18

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Figure 9 - Unit 3 Limiting Curve C Core Critical P-T Curves Effective for up to 32 EFPY 1400 r

INITIAl RTtaT VALUES 1300 ARE 1o-F FOR BELTLINE, 44., FOR UPPER 1200 vessa, AND 54-': FOR BOTT0t\4 HEAD 1100 a

),1000 BElTLINE CURVE Q ADJUSTED AS SHOWN:

(fj EFPV SHIFT (OF)

c 900 32 88.3 a.

o I-id 800 a

HEATUPICOOlOOWN RATE OF COOLANT

~ 100-FIHR a.: 700 o

I-

~

a.: 800 ~

~

l-i

I w

500 ,I ACCEPTABLE ....

REGION OF

~ OPERATION IS

~400 TO THE RIGHT~

OF THE

~

a. 300 1312 PSIG

,,.... CURVE

~

200 J V -BELTLINE AND 100 ~

/ Minimum Vessel t---

NON-BELTLINE LIMITS r~

~ Temperature 70°F

~

o o 25 50 75 100 125150 175 200 225 250 MINIMUM REACTORYE88EL METAL TEMPERATURE(*F) 19

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ )"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE PATE]

Figure 10 - Unit 3 Composite Curve A Pressure Test P-T Curves Effective for up to S4 EFPY 1400 I

1300 I 1200 I / INITIAL RTfin' VALUES ARE 1o-F FOR BELTUNE, 44.,. FOR UPPER 1100 / VESSEL, AND 54.,. FOR BOTTOM HEAD a

11000

/1/ ~

BELnlNE CURVES a.

900 I ADJUSTED AS SHOWN:

EFPV SHIFT ("F) 54 78.8 0

~

LU 800

/

a

> V/

ae 700 II 0 / HEATUPICOOLOOWN

~

Ill:

600 ACCEPTABLE REGION OF OPERATION IS TO

~

RATE OF COOlANT

~ 2O"FIHR

!i THE RIGHT OF THE

~

i 500 BOTTOM APPLICABLE CURVE ~

J HEAD III 68°F ae i 400 III ae Q,

300 I I 312 PSIGI I

I I

I FLANGE -UPPER VESSEL I

200 REGION AND BELTUNE I ~ 70°F LIMITS I, 1.........-' ------- BOTTOM HEAD 100 I CURVE I

I I

I 0

o 25 50 75 100 125 150 175 200 MINIMUM REACTORVE88EL METAL TEMPERATURE rF) 20

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by tI[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEqIViDAT~]

Figure 11- Unit 3 Composite Curve B Core Not Critical P-T Curves Effective for up to 54 EFPY 1400 1300 I

1200 I I INITIAL RTfOI' VALUES ARE 1crF FOR BELTlINE, 1100 I 44-': FOR UPPER VESSEL, 4~ FOR AND BOTTOM HEAD I BELTlINE CURVES ADJUSTED AS SHOWN:

EFPY SHIFT rF)

/ 54 78.8

/ ACCEPTABLE REGION OF HEATUPICOOlDOWN

/ J OPERATION IS TO THE RATE OF COOLANT

.s: 10o-FIHR

/ / RIGHTOF THE APPLICABLE I CURVE BOTTOM HEAD 68'F V

- I 312PSIG I

-UPPER VESSEL 200 ANDBElTUNE 100

/ ./

FlANGE REGION 700F LIMITS

BOTTOM HEAD j/ CURVE a

I I I a ~ ~ ~ 100 1~ 1~ 1~ 200 MINIMUM REACTORVE88EL METAL TEMPERAnJRErF) 21

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE [)ATE]

Figure 12 - Unit 3 Limiting Curve C Core Critical P-T Curves Effective for up to 54 EFPY 1400 , INITIAL RTMJr VALUES 1300 ARE 1<rF FOR BELTUNE, 44-F FOR UPPeR VESsel, 1200 AND 54~ FOR BOTTOM HEAD 1100 til

).1000 BeLn.INECURve ADJUSTED AS SHOWN:

~

EFPV SHIFT rF) 54 78.8 900 a.

0 t-w 800 a

II: 700 HEATUP/COOLOOWN RATE OF COOlNIT

~ 10o-FIHR 0 ACCEPTABLE I-REGION OF

~ 800 OPERATION IS TO THE l:

l- J RIGHTOF i 500 THE CURVE

J w

II:

I ilUJ 400 w

II:

a. 300 ,- 1312 PSIGI 200 J

/ -BELTLINE AND 100 ,/ Minimum Vessel r--

NON-BELTUNE LIMITS r~

Temperatura 70°F 0

I o 25 50 75 100 125 150 175 200 225 250 MINIMUM REACTORVE88EL METAL TEMPERATURE rF) 22

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE"CTIVEOAT&]

Table 1- Unit 2 Tabulation of Curves - 32 EFPY 0 68.0 70.0 68.0 70.0 70.0 10 68.0 70.0 68.0 70.0 70.0 20 68.0 70.0 68.0 70.0 70.0 30 68.0 70.0 68.0 70.0 70.0 40 68.0 70.0 68.0 70.0 70.0 50 68.0 70.0 68.0 70.0 79.1 60 68.0 70.0 68.0 70.0 88.0 70 68.0 70.0 68.0 70.0 95.2 80 68.0 70.0 68.0 70.0 101.2 90 68.0 70.0 68.0 70.0 106.3 100 68.0 70.0 68.0 70.8 110.8 110 68.0 70.0 68.0 74.9 114.9 120 68.0 70.0 68.0 78.7 118.7 130 68.0 70.0 68.0 82.2 122.2 140 68.0 70.0 68.0 85.4 125.4 150 68.0 70.0 68.0 88.2 128.2 160 68.0 70.0 68.0 90.9 130.9 170 68.0 70.0 68.0 93.5 133.5 180 68.0 70.0 68.0 95.9 135.9 190 68.0 70.0 68.0 98.2 138.2 200 68.0 70.0 68.0 100.3 140.3 210 68.0 70.0 68.0 102.3 142.3 220 68.0 70.0 68.0 104.3 144.3 230 68.0 70.0 68.0 106.1 146.1 240 68.0 70.0 68.0 107.9 147.9 250 68.0 70.0 68.0 109.6 149.6 260 68.0 70.0 68.0 111.2 151.2 270 68.0 70.0 68.0 112.8 152.8 280 68.0 70.0 68.0 114.3 154.3 290 68.0 70.0 68.0 115.8 155.8 23

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFf~crIVe~OAT~]

300 68.0 70.0 68.0 117.2 157.2 310 68.0 70.0 68.0 118.5 158.5 312.5 68.0 70.0 68.0 118.9 158.9 312.5 68.0 100.0 68.0 130.0 170.0 320 68.0 100.0 68.0 130.0 170.0 330 68.0 100.0 68.0 130.0 170.0 340 68.0 100.0 68.0 130.0 170.0 350 68.0 100.0 68.0 130.0 170.0 360 68.0 100.0 68.0 130.0 170.0 370 68.0 100.0 68.0 130.0 170.0 380 68.0 100.0 68.0 130.0 170.0 390 68.0 100.0 68.0 130.0 170.0 400 68.0 100.0 68.0 130.0 170.0 410 68.0 100.0 68.0 130.2 170.2 420 68.0 100.0 68.0 131.2 171.2 430 68.0 100.0 68.0 132.2 172.2 440 68.0 100.0 68.0 133.2 173.2 450 68.0 100.0 68.0 134.1 174.1 460 68.0 100.0 68.0 135.1 175.1 470 68.0 100.0 68.6 136.0 176.0 480 68.0 100.0 71.1 136.9 176.9 490 68.0 100.0 73.4 137.7 177.7 500 68.0 100.0 75.6 138.6 178.6 510 68.0 100.0 77.8 139.4 179.4 520 68.0 100.0 79.8 140.2 180.2 530 68.0 100.0 81.8 141.0 181.0 540 68.0 100.0 83.7 141.8 181.8 550 68.0 100.0 85.5 142.6 182.6 560 68.0 100.0 87.3 143.4 183.4 570 68.0 100.0 89.0 144.1 184.1 580 68.0 100.0 90.6 144.9 184.9 590 68.0 100.0 92.2 145.6 185.6 600 68.0 100.0 93.8 146.1 186.1 24

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0 LEE~jg!Y~QAtj]

....<.. -.~:.

PRESSU

,J/'P~I(;

610 68.0 100.0 95.3 146.6 186.6 620 68.0 100.0 96.7 147.0 187.0 630 68.0 101.0 98.1 147.4 187.4 640 68.0 102.0 99.5 147.8 187.8 650 68.0 103.0 100.8 148.2 188.2 660 68.0 104.0 102.1 148.7 188.7 670 68.0 104.9 103.4 149.1 189.1 680 68.0 105.9 104.7 149.5 189.5 690 68.7 106.8 105.9 149.9 189.9 700 70.2 107.7 107.0 150.3 190.3 710 71.7 108.6 108.2 150.7 190.7 720 73.1 109.4 109.3 151.1 191.1 730 74.5 110.3 110.4 151.5 191.5 740 75.8 111.1 111.5 151.9 191.9 750 77.1 112.0 112.6 152.2 192.2 760 78.4 112.8 113.6 152.6 192.6 770 79.6 113.6 114.6 153.0 193.0 780 80.8 114.3 115.6 153.4 193.4 790 82.0 115.1 116.6 153.8 193.8 800 83.2 115.9 117.5 154.1 194.1 810 84.3 116.6 118.5 154.5 194.5 820 85.4 117.4 119.4 154.9 194.9 830 86.5 118.1 120.3 155.2 195.2 840 87.5 118.8 121.2 155.6 195.6 850 88.6 119.5 122.0 155.9 195.9 860 89.6 120.2 122.9 156.3 196.3 870 90.6 120.9 123.7 156.6 196.6 880 91.5 121.6 124.6 157.0 197.0 890 92.5 122.3 125.4 157.3 197.3 900 93.4 122.9 126.2 157.7 197.7 910 94.4 123.6 127.0 158.0 198.0 920 95.3 124.2 127.7 158.4 198.4 930 96.1 124.9 128.5 158.7 198.7 2S

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEgIY:~'tlp.r~]

940 97.0 125.5 129.3 159.0 199.0 950 97.9 126.1 130.0 159.4 199.4 960 98.7 126.7 130.7 159.7 199.7 970 99.6 127.3 131.5 160.0 200.0 980 100.4 127.9 132.2 160.4 200.4 990 101.2 128.5 132.9 160.7 200.7 1000 102.0 129.1 133.6 161.0 201.0 1010 102.7 129.7 134.2 161.3 201.3 1015 103.1 130.0 134.6 161.5 201.5 1020 103.5 130.2 134.9 161.6 201.6 1030 104.3 130.8 135.6 162.0 202.0 1035 104.6 131.1 135.9 162.1 202.1 1040 105.0 131.4 136.2 162.3 202.3 1050 105.7 131.9 136.9 162.6 202.6 1055 106.1 132.2 137.2 162.7 202.7 1060 106.4 132.5 137.5 162.9 202.9 1070 107.2 133.0 138.1 163.2 203.2 1080 107.9 133.5 138.8 163.5 203.5 1090 108.6 134.1 139.4 163.8 203.8 1100 109.2 134.6 140.0 164.1 204.1 1105 109.6 134.8 140.3 164.3 204.3 1110 109.9 135.1 140.6 164.4 204.4 1120 110.6 135.6 141.2 164.7 204.7 1130 111.2 136.1 141.8 165.0 205.0 1140 111.9 136.6 142.3 165.3 205.3 1150 112.5 137.1 142.9 165.6 205.6 1160 113.1 137.6 143.5 165.9 205.9 1170 113.8 138.1 144.0 166.2 206.2 1180 114.4 138.6 144.6 166.5 206.5 1190 115.0 139.1 145.1 166.7 206.7 1200 115.6 139.5 145.7 167.0 207.0 1210 116.2 140.0 146.2 167.3 207.3 1220 116.8 140.5 146.8 167.6 207.6 26

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE'DAT$l 1230 117.3 140.9 147.3 167.9 207.9 1240 117.9 141.4 147.8 168.2 208.2 1250 118.5 141.8 148.3 168.4 208.4 1260 119.0 142.3 148.8 168.7 208.7 1270 119.6 142.7 149.3 169.0 209.0 1280 120.1 143.2 149.8 169.2 209.2 1290 120.7 143.6 150.3 169.5 209.5 1300 121.2 144.0 150.8 169.8 209.8 1310 121.7 144.5 151.3 170.1 210.1 1320 122.3 144.9 151.8 170.3 210.3 1330 122.8 145.3 152.2 170.6 210.6 1340 123.3 145.7 152.7 170.8 210.8 1350 123.8 146.1 153.2 171.1 211.1 1360 124.3 146.6 153.6 171.4 211.4 1370 124.8 147.0 154.1 171.6 211.6 1380 125.3 147.4 154.5 171.9 211.9 1390 125.8 147.8 155.0 172.1 212.1 1400 126.3 148.2 155.4 172.4 212.4 27

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by ttl ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE,CTIVE', PATE]

Table 2 - Unit 2 Tabulation of Curves - 54 EFPY 0 68.0 70.0 68.0 70.0 70.0 10 68.0 70.0 68.0 70.0 70.0 20 68.0 70.0 68.0 70.0 70.0 30 68.0 70.0 68.0 70.0 70.0 40 68.0 70.0 68.0 70.0 70.0 50 68.0 70.0 68.0 70.0 79.1 60 68.0 70.0 68.0 70.0 88.0 70 68.0 70.0 68.0 70.0 95.2 80 68.0 70.0 68.0 70.0 101.2 90 68.0 70.0 68.0 70.0 106.3 100 68.0 70.0 68.0 70.8 110.8 110 68.0 70.0 68.0 74.9 114.9 120 68.0 70.0 68.0 78.7 118.7 130 68.0 70.0 68.0 82.2 122.2 140 68.0 70.0 68.0 85.4 125.4 150 68.0 70.0 68.0 88.2 128.2 160 68.0 70.0 68.0 90.9 130.9 170 68.0 70.0 68.0 93.5 133.5 180 68.0 70.0 68.0 95.9 135.9 190 68.0 70.0 68.0 98.2 138.2 200 68.0 70.0 68.0 100.3 140.3 210 68.0 70.0 68.0 102.3 142.3 220 68.0 70.0 68.0 104.3 144.3 230 68.0 70.0 68.0 106.1 146.1 240 68.0 70.0 68.0 107.9 147.9 250 68.0 70.0 68.0 109.6 149.6 260 68.0 70.0 68.0 111.2 151.2 270 68.0 70.0 68.0 112.8 152.8 280 68.0 70.0 68.0 114.3 154.3 28

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFf~fitlV~QAI~

pStG 290 68.0 70.0 68.0 115.8 155.8 300 68.0 70.0 68.0 117.2 157.2 310 68.0 70.0 68.0 118.5 158.5 312.5 68.0 70.0 68.0 118.9 158.9 312.5 68.0 100.0 68.0 130.0 170.0 320 68.0 100.0 68.0 130.0 170.0 330 68.0 100.0 68.0 130.0 170.0 340 68.0 100.0 68.0 130.0 170.0 350 68.0 100.0 68.0 130.0 170.0 360 68.0 100.0 68.0 130.0 170.0 370 68.0 100.0 68.0 130.0 170.0 380 68.0 100.0 68.0 130.0 170.0 390 68.0 100.0 68.0 130.0 170.0 400 68.0 100.0 68.0 130.0 170.0 410 68.0 100.0 68.0 130.2 170.2 420 68.0 100.0 68.0 131.2 171.2 430 68.0 100.0 68.0 132.2 172.2 440 68.0 100.0 68.0 133.2 173.2 450 68.0 100.0 68.0 134.1 174.1 460 68.0 100.0 68.0 135.1 175.1 470 68.0 100.0 68.6 136.0 176.0 480 68.0 100.0 71.1 136.9 176.9 490 68.0 100.0 73.4 137.7 177.7 500 68.0 100.0 75.6 138.6 178.6 510 68.0 100.0 77.8 139.4 179.4 520 68.0 100.0 79.8 140.2 180.2 530 68.0 100.0 81.8 141.0 181.0 540 68.0 100.0 83.7 141.8 181.8 550 68.0 100.0 85.5 142.6 182.6 560 68.0 100.0 87.3 143.4 183.4 570 68.0 100.0 89.0 144.1 184.1 580 68.0 100.0 90.6 144.9 184.9 29

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by tI[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFfECTIVE' DAT~]

590 68.0 100.0 92.2 145.6 185.6 600 68.0 100.0 93.8 146.1 186.1 610 68.0 100.0 95.3 146.6 186.6 620 68.0 100.0 96.7 147.0 187.0 630 68.0 101.0 98.1 147.4 187.4 640 68.0 102.0 99.5 147.8 187.8 650 68.0 103.0 100.8 148.2 188.2 660 68.0 104.0 102.1 148.7 188.7 670 68.0 104.9 103.4 149.1 189.1 680 68.0 105.9 104.7 149.5 189.5 690 68.7 106.8 105.9 149.9 189.9 700 70.2 107.7 107.0 150.3 190.3 710 71.7 108.6 108.2 150.7 190.7 720 73.1 109.4 109.3 151.1 191.1 730 74.5 110.3 110.4 151.5 191.5 740 75.8 111.1 111.5 151.9 191.9 750 77.1 112.0 112.6 152.2 192.2 760 78.4 112.8 113.6 152.6 192.6 770 79.6 113.6 114.6 153.0 193.0 780 80.8 114.3 115.6 153.4 193.4 790 82.0 115.1 116.6 153.8 193.8 800 83.2 115.9 117.5 154.1 194.1 810 84.3 116.6 118.5 154.5 194.5 820 85.4 117.4 119.4 154.9 194.9 830 86.5 118.1 120.3 155.2 195.2 840 87.5 118.8 121.2 155.6 195.6 850 88.6 119.5 122.0 155.9 195.9 860 89.6 120.2 122.9 156.3 196.3 870 90.6 120.9 123.7 156.6 196.6 880 91.5 121.6 124.6 157.0 197.0 890 92.5 122.3 125.4 157.3 197.3 900 93.4 122.9 126.2 157.7 197.7 30

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFECJIVEOATE]

910 94.4 123.6 127.0 158.0 198.0 920 95.3 124.2 127.7 158.4 198.4 930 96.1 124.9 128.5 158.7 198.7 940 97.0 125.5 129.3 159.0 199.0 950 97.9 126.1 130.0 159.4 199.4 960 98.7 126.7 130.7 159.7 199.7 970 99.6 127.3 131.5 160.0 200.0 980 100.4 127.9 132.2 160.4 200.4 990 101.2 128.5 132.9 160.7 200.7 1000 102.0 129.1 133.6 161.0 201.0 1010 102.7 129.7 134.2 161.3 201.3 1015 103.1 130.0 134.6 161.5 201.5 1020 103.5 130.2 134.9 161.6 201.6 1030 104.3 130.8 135.6 162.0 202.0 1035 104.6 131.1 135.9 162.1 202.1 1040 105.0 131.4 136.2 162.3 202.3 1050 105.7 131.9 136.9 162.6 202.6 1055 106.1 132.2 137.2 162.7 202.7 1060 106.4 132.5 137.5 162.9 202.9 1070 107.2 133.0 138.1 163.2 203.2 1080 107.9 133.5 138.8 163.5 203.5 1090 108.6 134.1 139.4 163.8 203.8 1100 109.2 134.6 140.0 164.1 204.1 1105 109.6 134.8 140.3 164.3 204.3 1110 109.9 135.1 140.6 164.4 204.4 1120 110.6 135.6 141.2 164.7 204.7 1130 111.2 136.1 141.8 165.0 205.0 1140 111.9 136.6 142.3 165.3 205.3 1150 112.5 137.1 142.9 165.6 205.6 1160 113.1 137.6 143.5 165.9 205.9 1170 113.8 138.1 144.0 166.2 206.2 1180 114.4 138.6 144.6 166.5 206.5 31

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFECTIVe', DAT~]

1190 115.0 139.1 145.1 166.7 206.7 1200 115.6 139.5 145.7 167.0 207.0 1210 116.2 140.0 146.2 167.3 207.3 1220 116.8 140.5 146.8 167.6 207.6 1230 117.3 140.9 147.3 167.9 207.9 1240 117.9 141.4 147.8 168.2 208.2 1250 118.5 141.8 148.3 168.4 208.4 1260 119.0 142.3 148.8 168.7 208.7 1270 119.6 142.7 149.3 169.0 209.0 1280 120.1 143.2 149.8 169.2 209.2 1290 120.7 143.6 150.3 169.5 209.5 1300 121.2 144.0 150.8 169.8 209.8 1310 121.7 144.5 151.3 170.1 210.1 1320 122.3 144.9 151.8 170.3 210.3 1330 122.8 145.3 152.2 170.6 210.6 1340 123.3 145.7 152.7 170.8 210.8 1350 123.8 146.1 153.2 171.1 211.1 1360 124.3 146.6 153.6 171.4 211.4 1370 124.8 147.0 154.1 171.6 211.6 1380 125.3 147.4 154.5 171.9 211.9 1390 125.8 147.8 155.0 172.1 212.1 1400 126.3 148.2 155.4 172.4 212.4 32

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE DAT~]

Table 3 - Unit 3 Tabulation of Curves - 32 EFPY 0 68.0 70.0 68.0 70.0 70.0 10 68.0 70.0 68.0 70.0 70.0 20 68.0 70.0 68.0 70.0 70.0 30 68.0 70.0 68.0 70.0 70.0 40 68.0 70.0 68.0 70.0 70.0 50 68.0 70.0 68.0 70.0 75.1 60 68.0 70.0 68.0 70.0 84.0 70 68.0 70.0 68.0 70.0 91.2 80 68.0 70.0 68.0 70.0 97.2 90 68.0 70.0 68.0 70.0 102.3 100 68.0 70.0 68.0 70.0 106.8 110 68.0 70.0 68.0 70.9 110.9 120 68.0 70.0 68.0 74.7 114.7 130 68.0 70.0 68.0 78.2 118.2 140 68.0 70.0 68.0 81.4 121.4 150 68.0 70.0 68.0 84.2 124.2 160 68.0 70.0 68.0 86.9 126.9 170 68.0 70.0 68.0 89.5 129.5 180 68.0 70.0 68.0 91.9 131.9 190 68.0 70.0 68.0 94.2 134.2 200 68.0 70.0 68.0 96.3 136.3 210 68.0 70.0 68.0 98.3 138.3 220 68.0 70.0 68.0 100.3 140.3 230 68.0 70.0 68.0 102.1 142.1 240 68.0 70.0 68.0 103.9 143.9 250 68.0 70.0 68.0 105.6 145.6 260 68.0 70.0 68.0 107.2 147.2 270 68.0 70.0 68.0 108.8 148.8 280 68.0 70.0 68.0 110.3 150.3 290 68.0 70.0 68.0 111.8 151.8 33

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE,CTIVE DATE]

300 68.0 70.0 68.0 113.2 153.2 310 68.0 70.0 68.0 114.5 154.5 312.5 68.0 70.0 68.0 114.9 154.9 312.5 68.0 100.0 68.0 130.0 170.0 320 68.0 100.0 68.0 130.0 170.0 330 68.0 100.0 68.0 130.0 170.0 340 68.0 100.0 68.0 130.0 170.0 350 68.0 100.0 68.0 130.0 170.0 360 68.0 100.0 68.0 130.0 170.0 370 68.0 100.0 68.0 130.0 170.0 380 68.0 100.0 68.0 130.0 170.0 390 68.0 100.0 68.0 130.0 170.0 400 68.0 100.0 68.0 130.0 170.0 410 68.0 100.0 68.0 130.0 170.0 420 68.0 100.0 68.0 130.0 170.0 430 68.0 100.0 68.0 130.0 170.0 440 68.0 100.0 68.0 130.0 170.0 450 68.0 100.0 68.0 130.1 170.1 460 68.0 100.0 68.0 131.1 171.1 470 68.0 100.0 68.0 132.0 172.0 480 68.0 100.0 68.0 132.9 172.9 490 68.0 100.0 69.4 133.7 173.7 500 68.0 100.0 71.6 134.6 174.6 510 68.0 100.0 73.8 135.4 175.4 520 68.0 100.0 75.8 136.2 176.2 530 68.0 100.0 77.8 137.0 177.0 540 68.0 100.0 79.7 137.8 177.8 550 68.0 100.0 81.5 138.6 178.6 560 68.0 100.0 83.3 139.4 179.4 570 68.0 100.0 85.0 140.1 180.1 580 68.0 100.0 86.6 140.9 180.9 590 68.0 100.0 88.2 141.6 181.6 600 68.0 100.0 89.8 142.1 182.1 34

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EF~~,qly~q~t~]

"12,5 610 68.0 100.0 91.3 142.6 182.6 620 68.0 100.0 92.7 143.0 183.0 630 68.0 100.0 94.1 143.4 183.4 640 68.0 100.0 95.5 143.8 183.8 650 68.0 100.0 96.8 144.2 184.2 660 68.0 100.0 98.1 144.7 184.7 670 69.6 100.9 99.4 145.1 185.1 680 71.2 101.9 100.7 145.5 185.5 690 72.7 102.8 101.9 145.9 185.9 700 74.2 103.7 103.0 146.3 186.3 710 75.7 104.6 104.2 146.7 186.7 720 77.1 105.4 105.3 147.1 187.1 730 78.5 106.3 106.4 147.5 187.5 740 79.8 107.1 107.5 147.9 187.9 750 81.1 108.0 108.6 148.2 188.2 760 82.4 108.8 109.6 148.6 188.6 770 83.6 109.6 110.6 149.0 189.0 780 84.8 110.3 111.6 149.4 189.4 790 86.0 111.1 112.6 149.8 189.8 800 87.2 111.9 113.5 150.1 190.1 810 88.3 112.6 114.5 150.5 190.5 820 89.4 113.4 115.4 150.9 190.9 830 90.5 114.1 116.3 151.2 191.2 840 91.5 114.8 117.2 151.6 191.6 850 92.6 115.5 118.0 151.9 191.9 860 93.6 116.2 118.9 152.3 192.3 870 94.6 116.9 119.7 152.6 192.6 880 95.5 117.6 120.6 153.0 193.0 890 96.5 118.3 121.4 153.3 193.3 900 97.4 118.9 122.2 153.7 193.7 910 98.4 119.6 123.0 154.0 194.0 920 99.3 120.2 123.7 154.4 194.4 930 100.1 120.9 124.5 154.7 194.7 35

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFfEC11V, DAT~]

940 101.0 121.5 125.3 155.0 195.0 950 101.9 122.1 126.0 155.4 195.4 960 102.7 122.7 126.7 155.7 195.7 970 103.6 123.3 127.5 156.0 196.0 980 104.4 123.9 128.2 156.4 196.4 990 105.2 124.5 128.9 156.7 196.7 1000 106.0 125.1 129.6 157.0 197.0 1010 106.7 125.7 130.2 157.3 197.3 1015 107.1 126.0 130.6 157.5 197.5 1020 107.5 126.2 130.9 157.6 197.6 1030 108.3 126.8 131.6 158.0 198.0 1035 108.6 127.1 131.9 158.1 198.1 1040 109.0 127.4 132.2 158.3 198.3 1050 109.7 127.9 132.9 158.6 198.6 1055 110.1 128.2 133.2 158.7 198.7 1060 110.4 128.5 133.5 158.9 198.9 1070 111.2 129.0 134.1 159.2 199.2 1080 111.9 129.5 134.8 159.5 199.5 1090 112.6 130.1 135.4 159.8 199.8 1100 113.2 130.6 136.0 160.1 200.1 1105 113.6 130.8 136.3 160.3 200.3 1110 113.9 131.1 136.6 160.4 200.4 1120 114.6 131.6 137.2 160.7 200.7 1130 115.2 132.1 137.8 161.0 201.0 1140 115.9 132.6 138.3 161.3 201.3 1150 116.5 133.1 138.9 161.6 201.6 1160 117.1 133.6 139.5 161.9 201.9 1170 117.8 134.1 140.0 162.2 202.2 1180 118.4 134.6 140.6 162.5 202.5 1190 119.0 135.1 141.1 162.7 202.7 1200 119.6 135.5 141.7 163.0 203.0 1210 120.2 136.0 142.2 163.3 203.3 1220 120.8 136.5 142.8 163.6 203.6 36

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by n[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EfFECTIVE DATE]

1230 121.3 136.9 143.3 163.9 203.9 1240 121.9 137.4 143.8 164.2 204.2 1250 122.5 137.8 144.3 164.4 204.4 1260 123.0 138.3 144.8 164.7 204.7 1270 123.6 138.7 145.3 165.0 205.0 1280 124.1 139.2 145.8 165.2 205.2 1290 124.7 139.6 146.3 165.5 205.5 1300 125.2 140.0 146.8 165.8 205.8 1310 125.7 140.5 147.3 166.1 206.1 1320 126.3 140.9 147.8 166.3 206.3 1330 126.8 141.3 148.2 166.6 206.6 1340 127.3 141.7 148.7 166.8 206.8 1350 127.8 142.1 149.2 167.1 207.1 1360 128.3 142.6 149.6 167.4 207.4 1370 128.8 143.0 150.1 167.6 207.6 1380 129.3 143.4 150.5 167.9 207.9 1390 129.8 143.8 151.0 168.1 208.1 1400 130.3 144.2 151.4 168.4 208.4 37

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFEqIV~>i)AT~]

Table 4 - Unit 3 Tabulation of Curves - 54 EFPY o 68.0 70.0 68.0 70.0 70.0 10 68.0 70.0 68.0 70.0 70.0 20 68.0 70.0 68.0 70.0 70.0 30 68.0 70.0 68.0 70.0 70.0 40 68.0 70.0 68.0 70.0 70.0 50 68.0 70.0 68.0 70.0 75.1 60 68.0 70.0 68.0 70.0 84.0 70 68.0 70.0 68.0 70.0 91.2 80 68.0 70.0 68.0 70.0 97.2 90 68.0 70.0 68.0 70.0 102.3 100 68.0 70.0 68.0 70.0 106.8 110 68.0 70.0 68.0 70.9 110.9 120 68.0 70.0 68.0 74.7 114.7 130 68.0 70.0 68.0 78.2 118.2 140 68.0 70.0 68.0 81.4 121.4 150 68.0 70.0 68.0 84.2 124.2 160 68.0 70.0 68.0 86.9 126.9 170 68.0 70.0 68.0 89.5 129.5 180 68.0 70.0 68.0 91.9 131.9 190 68.0 70.0 68.0 94.2 134.2 200 68.0 70.0 68.0 96.3 136.3 210 68.0 70.0 68.0 98.3 138.3 220 68.0 70.0 68.0 100.3 140.3 230 68.0 70.0 68.0 102.1 142.1 240 68.0 70.0 68.0 103.9 143.9 250 68.0 70.0 68.0 105.6 145.6 260 68.0 70.0 68.0 107.2 147.2 270 68.0 70.0 68.0 108.8 148.8 280 68.0 70.0 68.0 110.3 150.3 290 68.0 70.0 68.0 111.8 151.8 38

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFE:cTIVe: OATS]

300 68.0 70.0 68.0 113.2 153.2 310 68.0 70.0 68.0 114.5 154.5 312.5 68.0 70.0 68.0 114.9 154.9 312.5 68.0 100.0 68.0 130.0 170.0 320 68.0 100.0 68.0 130.0 170.0 330 68.0 100.0 68.0 130.0 170.0 340 68.0 100.0 68.0 130.0 170.0 350 68.0 100.0 68.0 130.0 170.0 360 68.0 100.0 68.0 130.0 170.0 370 68.0 100.0 68.0 130.0 170.0 380 68.0 100.0 68.0 130.0 170.0 390 68.0 100.0 68.0 130.0 170.0 400 68.0 100.0 68.0 130.0 170.0 410 68.0 100.0 68.0 130.0 170.0 420 68.0 100.0 68.0 130.0 170.0 430 68.0 100.0 68.0 130.0 170.0 440 68.0 100.0 68.0 130.0 170.0 450 68.0 100.0 68.0 130.1 170.1 460 68.0 100.0 68.0 131.1 171.1 470 68.0 100.0 68.0 132.0 172.0 480 68.0 100.0 68.0 132.9 172.9 490 68.0 100.0 69.4 133.7 173.7 500 68.0 100.0 71.6 134.6 174.6 510 68.0 100.0 73.8 135.4 175.4 520 68.0 100.0 75.8 136.2 176.2 530 68.0 100.0 77.8 137.0 177.0 540 68.0 100.0 79.7 137.8 177.8 550 68.0 100.0 81.5 138.6 178.6 560 68.0 100.0 83.3 139.4 179.4 570 68.0 100.0 85.0 140.1 180.1 580 68.0 100.0 86.6 140.9 180.9 590 68.0 100.0 88.2 141.6 181.6 600 68.0 100.0 89.8 142.1 182.1 39

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by"[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTlVepAT&)

610 68.0 100.0 91.3 142.6 182.6 620 68.0 100.0 92.7 143.0 183.0 630 68.0 100.0 94.1 143.4 183.4 640 68.0 100.0 95.5 143.8 183.8 650 68.0 100.0 96.8 144.2 184.2 660 68.0 100.0 98.1 144.7 184.7 670 69.6 100.9 99.4 145.1 185.1 680 71.2 101.9 100.7 145.5 185.5 690 72.7 102.8 101.9 145.9 185.9 700 74.2 103.7 103.0 146.3 186.3 710 75.7 104.6 104.2 146.7 186.7 720 77.1 105.4 105.3 147.1 187.1 730 78.5 106.3 106.4 147.5 187.5 740 79.8 107.1 107.5 147.9 187.9 750 81.1 108.0 108.6 148.2 188.2 760 82.4 108.8 109.6 148.6 188.6 770 83.6 109.6 110.6 149.0 189.0 780 84.8 110.3 111.6 149.4 189.4 790 86.0 111.1 112.6 149.8 189.8 800 87.2 111.9 113.5 150.1 190.1 810 88.3 112.6 114.5 150.5 190.5 820 89.4 113.4 115.4 150.9 190.9 830 90.5 114.1 116.3 151.2 191.2 840 91.5 114.8 117.2 151.6 191.6 850 92.6 115.5 118.0 151.9 191.9 860 93.6 116.2 118.9 152.3 192.3 870 94.6 116.9 119.7 152.6 192.6 880 95.5 117.6 120.6 153.0 193.0 890 96.5 118.3 121.4 153.3 193.3 900 97.4 118.9 122.2 153.7 193.7 910 98.4 119.6 123.0 154.0 194.0 920 99.3 120.2 123.7 154.4 194.4 930 100.1 120.9 124.5 154.7 194.7 40

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[E~FEqIVE::D~T~]

940 101.0 121.5 125.3 155.0 195.0 950 101.9 122.1 126.0 155.4 195.4 960 102.7 122.7 126.7 155.7 195.7 970 103.6 123.3 127.5 156.0 196.0 980 104.4 123.9 128.2 156.4 196.4 990 105.2 124.5 128.9 156.7 196.7 1000 106.0 125.1 129.6 157.0 197.0 1010 106.7 125.7 130.2 157.3 197.3 1015 107.1 126.0 130.6 157.5 197.5 1020 107.5 126.2 130.9 157.6 197.6 1030 108.3 126.8 131.6 158.0 198.0 1035 108.6 127.1 131.9 158.1 198.1 1040 109.0 127.4 132.2 158.3 198.3 1050 109.7 127.9 132.9 158.6 198.6 1055 110.1 128.2 133.2 158.7 198.7 1060 110.4 128.5 133.5 158.9 198.9 1070 111.2 129.0 134.1 159.2 199.2 1080 111.9 129.5 134.8 159.5 199.5 1090 112.6 130.2 135.4 159.8 199.8 1100 113.2 130.9 136.0 160.1 200.1 1105 113.6 131.3 136.3 160.3 200.3 1110 113.9 131.7 136.6 160.4 200.4 1120 114.6 132.4 137.2 160.7 200.7 1130 115.2 133.1 137.8 161.0 201.0 1140 115.9 133.8 138.3 161.3 201.3 1150 116.5 134.5 138.9 161.6 201.6 1160 117.1 135.1 139.5 161.9 201.9 1170 117.8 135.8 140.0 162.3 202.3 1180 118.4 136.5 140.6 162.8 202.8 1190 119.0 137.1 141.1 163.3 203.3 1200 119.6 137.8 141.7 163.8 203.8 1210 120.2 138.4 142.2 164.3 204.3 1220 120.8 139.0 142.8 164.8 204.8 41

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTiVe} OATS]

1230 121.3 139.6 143.3 165.3 205.3 1240 121.9 140.2 143.8 165.8 205.8 1250 122.5 140.8 144.3 166.3 206.3 1260 123.0 141.4 144.8 166.7 206.7 1270 123.6 142.0 145.3 167.2 207.2 1280 124.1 142.6 145.8 167.7 207.7 1290 124.7 143.2 146.3 168.1 208.1 1300 125.2 143.7 146.8 168.6 208.6 1310 125.7 144.3 147.3 169.1 209.1 1320 126.3 144.9 147.8 169.5 209.5 1330 126.8 145.4 148.2 170.0 210.0 1340 127.3 146.0 148.7 170.4 210.4 1350 127.8 146.5 149.2 170.8 210.8 1360 128.3 147.0 149.6 171.3 211.3 1370 128.8 147.5 150.1 171.7 211.7 1380 129.3 148.1 150.5 172.1 212.1 1390 129.8 148.6 151.0 172.6 212.6 1400 130.3 149.1 151.4 173.0 213.0 42

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by n[ In PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE:~IVE; DATE]

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 PBAPS Unit 2 reactor vessel after Cycle 7, during refueling outage (RFO) 7. The 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 E18S-82. The methods and results of testing are presented in Reference 6.7, as required by 10 CFR 50, Appendices G and H. After testing, a reconstituted capsule was prepared and installed in the vessel during RFO 8.

The' first surveillance capsule was removed from the PBAPS Unit 3 reactor vessel after Cycle 7, during refueling outage (RFO) 7. The 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 E18S-82. The methods and results of testing are presented in Reference 6.8, as reqUired by 10 CFR 50, Appendices G and H. After testing, a reconstituted capsule was prepared and installed in the vessel during RFO 8.

As described in PBAPS Unit 2 and PBAPS Unit 3 Updated Final Safety Analysis Report (UFSAR)

Section 4.2.6, Inspection and Testing, the Integrated Surveillance Program (lSP) will determine the removal schedule for the remaining PBAPS Unit 2 and Unit 3 surveillance capsules. The PBAPS material surveillance program is administered in accordance with the BWR Vessel and Internals Project (VIP) ISP. The ISP combines the US BWR surveillance programs into a single integrated program. This program uses similar heats of materials in the surveillance programs of BWRs to represent the limiting materials in other vessels. It also adds data from the BWR Supplemental Surveillance Program (SSP). Per the BWRVIP ISP, Unit 2 is a host plant; the second Unit 2 capsule is scheduled to be removed at 33.7 EFPY and the remaining capsules are classified as "Standby". Per the BWRVIP ISP, Unit 3 is not a host plant, and the remaining capsules are classified as "Standby".

43

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ lit PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTiVe OATS]

Appendix B: PBAPS Unit 2 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information 44

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEClIVEOArE]

Figure B-1: PBAPS Unit 2 Reactor Pressure Vessels TOP HEAD

/ "<

f \ TOP HEAD FlANGE SHELL FLANGE ; v""'" @ @

t,

! /

SHELL 1i5 i

~ ..

I f: , .. ,

SHELlM

~

,,' n'

...H

/

I: ~ ~ SHELL j3 V

a TOP OF ACTlVEFUEl (TA:F)36l8" "

SHELL #2

~ ~ AXIAL WElDS !

V

. C1. C2. C3 (ESWs) , GI RTH WelD (BC)

~

8OTIOMOF ACTIVE FUEL .. '.

(BAiF) 21111" f.'

Q fj( @) !; ~ )

t V* SHELL 1i1

~~

B1, B2. B3 (ESWlI) ]I

' " . '. ,. . j'

\ .

v~ BOTTOM HEAD

/ v SUPPORT SI<JRT 1"- ..

. ~ .,' "

~

.. .. -- 00' 45

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by tt[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE'CTIVEDATE]

Table B-1: PBAPS Unit 2 Initial RTNOT Values for RPV Materials Top Head and Cylindrical Shell Materials PLATES Top Head & Flange Shell Flange Mk. 48-139-1 124-V-201 ASB-87 10 L 141 123 111 40 10 10 Head Flange Mk. 209-139-1 5P-2744 ABU 134 10 L 57 78 96 40 10 10 Top Head Dollar Mk.201-127-1 85842-2 40 L 66 67 "72 70 40 40 Top. Head Side Plates Mk. 202-145-1 C3131-3 10 L 75 46 91 48 10 10 Mk. 202-145-~ C3042-3 10 I. L 80 84 79 40 10 10 Mk. 202-146-3 C3262-1 10 L 97 94 79 40 10 10 Mk.202-145-6 C3042-3 10 L 87 87 84 40 10 10 Mk. 202-146-5 C3262-3 10L. 105 103 92 40 10 10 Mk. 202-146-6 C3262-3 10 L 72 78 93 40 10 10 Shell Course.

Shell 5 Mk.6-139-4 C2796-2 10 L 43 53 49 54 10 10 Mk.6-139-6 C2773-1 10 . ~ .. 45 .. ?O .59 50 10 10 Mk.6-139-5 C2863-2 10 L 65 62 72 40 10 10 Shell 4 I***

Mk. 15-139-1 ................................... C2789-3 10 L 68 41 65 58 10 10 Mk. 15-139-2 C2775-3 10 L 66 ... 11 51 40 10 10 Mk. 15-139-3 86776-1 10 L . 7! 69 65 40 10 10 Shell 3 Mk. 6-139-1 C3042-2 10 L 50 56 59 40 10 10 Mk. 6-139-2 C2796-1 10 L 65 54 47 46 10 10 Mk. 6-139-3 q~8?9-2. 10 ..... L 62 59 ... ~~. 40 10 10 Shell 2 ... f*

Mk. 6-139-17 C2761-2 10 57 69 58 40 -20 -20 Mk. 6-139-18 C2873-1 10 L 43 52 48 54 -20 -6 Mk. 6-139-23 C2894-2 10 .... L... 57 .. ?2 .... ?4. 40 -30 -20 Shell 1 Mk. 6-139-13 C2761-1 10 L 47 59 63 46 -30 -14 Mk.6-139-14 C2791-2 10 L 61 55 44 52 -30 -8 Mk.6-139-15 C2873-2 10 L 60 69 64 40 -30 -20 46

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE'CTIVE:OATE]

Table B-2: PBAPS Unit 2 Initial RTNOT Values for RPV Materials Bottom Head and Support Skirt Materials Bottom Head Upper Torus Mk. 2-122-12 A0931-2 40 L 79 86 77 70 40 40 Mk. 2-122-9 A0942-2 40 L 90 72 60 70 40 40 Mk. 2-127-5 85825-2 40 L 57 ,50 68 70 40 40 Mk. 2-127-6 85825-2 40 L 57 55 54 70 40 40 Mk. 2-127-4 A0985-2 40 L 74 75 50 70 40 40 Mk. 2-127-3 A0985-2 40 L 62 54 61 70 40 40 Lower Torus Mk. 4-139-5 A1907-2 40 L 65 33 40 104 40 44 Mk. 4-139-6 A1907-2 40 L 45 44 60 82 40 40 Mk. 4-139-7 C3042-1 40 L 45 65 40 90 40 40 Mk. 4-139-8 C3042-1 40 L 66 60 71 70 40 40 Bottom Head Dollar Mk. 1-139-2 C2781-2 40 L 32 32 55 106 40 46 Support Skirt Knuckle Mk.24~127-1 through ~4 B7478-3 40 L 56 61 69 70 40 40 Skirt Mk. 40-139-1 C3885-3C 40 L 100 103 104 70 40 40 Mk. 40-139-2 C3885-4C 40 L 94 66 81 70 40 40 Base Ring Mk. 41-139-5 thru 8 C3888-3 40 L 113 115 92 70 40 40 47

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTiVe: DATE]

Table B-3: PBAPS Unit 2 Initial RTNOT Values for RPV Materials Nozzle Nt through N3 Materials

.. " .:: :f.' :,,: ,'" . "

,,, '. , .. ., ,t:.-' HEATJ.::'

-'" . COMPONENl'I" .'. 'f'.::

- " I" '1;- 1' .....

.~, ".\'1"':'

Nozzl**:

N1 Recirculation Outlet Nozzle N1A AV-1595. Forging 71-6387 40 L 58 61 84 70 40 40 N1B AV-1834. Forging 7K-6310 .. 40 L 32 48 76 106 40 46 N2 Recirculation Inlet Nozzle N2A EV9947. Forging 7G-8200 40 L 76 64 60 70 -10 10 N2B EV9934, Forging 7G-8197 40 L 34 44 36 102 o 42 N2C EV9947, Forging 7G-8205 40 L 72 75 112 70 -10 10 N2D EV9947, Forging 7G-8203 40 L 58 95 84 70 -10 10 N2E AV1662, Forging 71-6158A 40 L 92 96 89 70 40 40 N2F EV9934. Forging 7G-8194 40 L 30 40 31 110 o 50 N2G AV1662, Forging 71-6158B 40 L 92 96 89 70 40 40 N2H EV9947, Forging 7G-8202 40 L 56 95 84 70 -10 10 N2J EV9947, Forging 7G-8201 40 L 76 64 60 70 o 10 N2K EV9934, Forging 7G-8196 40 L 34 44 ~ 102 -10 42 N3 Stearn Outlet Nozzle N3A AV1670, Forging 7J-6163 40 L 55 ... 48 45 BO 40 40 N3B AV1684. Forging 7J-6270 40 "L 55 6.9 79 70 . 40 _ 40

'40 N3C AV1844, Forging 7K-6012 L 74 34 54 102 40 42 N3D AV1671, Forging 7J-6164 40 L 80 74 54 70 40 40 48

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE DATE]

Table B-4: PBAPS Unit 2 Initial RTNOT Values for RPV Materials Nozzle N4 through N16 Materials

.I. i "

L.

TEST . ., ;: CHIRPY:'

, . COMPONENT" " 'TEMP' )T~ ;',' ENERG~"

. (.f)t~. oc LontI ~" (fT: .us)!"

N4 Feedwater Nozzle N4A EV9964, Forging 7H-6028B 40 L 31 53 55 108 10 48 N4B AV1736, Forging 71-8415A 40 L 60 60 60 70 40 40 N4C AV1736, Forging 71-64158 40 L 60 60 60 70 40 40 N4D EV9964, Forging 7H-6027B 40 L 31 34 33 108 10 48 N4E AV1671, Forging 71-6301B 40 L 83 63 65 70 40 40 N4F AV1671, Forging 71-6301A 40 L 83 63 65 70 40 40 N5 Core Spray Nozzle N5A AVl607, Forging N7H6232A 40 L .. 95 104 80 70 o 10 N5B !'-V1607, Forging N7H6232B 40 L 95 104 80 70 o 10 N6 Top Head Spray Nozzle N6A ZT3043-4 40 L 170 158 142 70 40 40 N6B BT26154 40 L 123 143 144 70 40 40 N7 Top Head Vent Nozzle ZT3043-3 40 L 113 122 148 70 40 40 N8 Jet Pump instrumentation Nozzle N8A BT2615-2, Forging 9564B 40 L 132 118 120 70 40 40 N8B BT26154, Forging 95640 40 L 132 118 120 70 40 40 N9 CRD HYD System Retum Nozzle, Ser # 13-12 E23VW, Fofging 438H-2 40 L 120 112 114 70 40 40 Nl0 Core Della P& Liq ConI. Noz, Ser # 17-127-2 ZT3043-1 40 L 106 136 111 70 40 40 Nll instrumentation Nozzle Nll A & B (Alloy 600) .. 071708-1 & 8601-1 N12 Instrumentation Nozzle . ... .. .* ..... .. ...

Nl2A& B (Alloy 600) '071708-1 & 8601 -

. I*

N13 & N14 Hgh & Low Pressure Seal Leak Nozzle A276N (Alloy 600)

-. 21~1"

-- 40 . -_. -

N15 Drain Nozzle L 39 42 44 92 32 N16 Instrumentalion Nozzle Nl6A & B (Alloy 600) 071708-1 & 8601-1 .... 1-'

49

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVEO'ATE]

Table B-5: PBAPS Unit 2 Initial RTNOT Values for RPV Materials Shell Weld Materials Vertical and Meridional 'Nela Bottom Head Lower Torus (Z1, 22, 23, ZA) NlA Bottom Head Upper Torus (A1, /42., A'J, A4, M, A6) NlA Shell Course 1 (B1, B2, B3) 37C065 (Electroslag) -45 Shell Course 2 (C 1, C2, C3) 37C065 (Electroslag) -45 Shell Course 3 (01,02,03) Electros lag Shell Course 4 (04, 05, 06) Electroslag Shell Course 5 (E 1, E2, E3) Electroslag Top Head Torus (G1, G2, 00, G4, GS, 06) 01R4961S92W7A 10 L 62 64 68 10 -50 Glrth'Nela Bottom Head Dollar to Lower Torus 432Z0471/BOO3A27A 10 L 100 102 106 10 -50 Bottom Head Dollar to Lower Torus 01 R4961S92W7A 10 L 62 64 68 10 -50 Bottom Head Dollar to Lower Torus CTY5381NJ27A27A 10 L 94 95 95 10 -50 Bottom Head Lower to Upper Torus NlA Bottom Head Torus to Shell # 1 NlA SheH # 1 to SheU # 21 SheH # 2 to Shell # 3 5-3986 Linde 124 10 L 41 45 46 28 -32 Shell # 2 to Shell # 3 88E081/F920A27A 10 L 85 90 91 10 -50 Shell # 3 to Shell # 4 NlA Shell # 4 to Shell # 5 CTY5381NJ27A27A 10 L 94 95 95 10 -50 Shell # 4 to Shell # 5 CTY5381B012A27A 10 L n 81 87 10 -50 SheH # 4 to Shell # 5 08R48181S922A27A 10 L 65 68 69 10 -50 Shell # 4 to Shell # 5 5-3986 Linde 124 10 L 41 45 46 28 -32 Shell #5 to Shell Flange NlA Top Head Flange to Torus 1Torus to Dollar 08R481/J90S/427A 10 L 81 81 82 10 -50 Top Head Flange to Torus 1Torus to Dollar 01 R4961S925A27A 10 L 62 64 68 10 -50 Top Head Flange to Torus 1Torus to Dollar 820913/0908/42.7A 10 L 80 94 83 10 -50 Top Head Flange to Torus 1Torus to Dollar 5-3986 Linde 124 10 L 41 45 46 28 -32 To Head Torus to Dollar 88E081/F920A27A 10 L 85 90 91 10 -50 50

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by"[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE:etlVe DATe]

Table B-6: PBAPS Unit 2 Initial RTNOT Values for RPV Materials NOlzle and Appurtenance Weld and Bolting Materials

i,';:'"

."<' }"',

\:, ,.:'(' .',

J

,'c".. . . .',." '~" DRO_;" ;:'0'/

,'/,

i

""",,, ":,:':?":

ii'. "'.

i'," '::',':",."'.

,),';::,:" "::,:;".:';:,'

,;".','; ?;<"

i

':',',i, I,

~:'

---"',i'"

-,'}, j' .t~rJ~\g;'<.".

P:~I:;:"f' \\tiIGtm*, ~'\ ND'I;(: i!;~1i'tc

',. ,,:' ii:

",;,ih ',; .;.

.". j ::~r':

(':

" ',: ~\ ';, (~PJi0i;':

ft: 'i>

Nozzle Welda N1 Recirculation Outlet Nozzle NlA N2 Recirculation Inlet Nozzle NlA N3 Steam Outlet Nozzle 01 R4961S925A27A 10 L 62 64 68 10 -SO 82D9131D908A27A 10 L 80 94 83 10 -SO 6012211E916A27A 10 L 107 108 108 10 - -SO 601 090/090 1A27A 10 L 62 48 51 14 - -46 649T27311726A27A 10 L 81 67 81.5 10 -SO 650XOO6lJ807A27A 10 L 89 93 97 10 -SO 6013821S923A27A 10 L 77 78 78 10 -SO N4 Feedwater Nozzle NlA N5 Core Spray Nozzle Inconal Ne. N7 Top Head Instrument & Vent Nozzle 432ZD471/BOO3A27A 10 L 100 102 106 10 -SO 05R9381NJ27A27A 10 L 66 84 86 10 - -50 CTY5381NJ27A27A 10 L 94 95 95 10 -50 N8 Jet Pump Instrumentation Nozzle Stainless Steel N9 CRD HSR Nozzle Inconal N10 Core AP and Liquid Control Nozzle NlA N11. N12 Instrumentation Nozzle Inconal N13. N14 Hgh & Low Pressure Seal Leak Detector NlA N15 Drain Nozzle NlA N161nstrumentatlon Nozzle Inconal eRD Stub Tubes Inconal Appurtenance Welda Shroud Support Inconel Support Skirt Knuckle to Bottom Head NlA Feedwater Sparger Bracket Pads I Guide Rod Brackets Stainless Steel Surveillance Brackets I Core Spray Brackets Stainless Steel Steam Dryer Support Brackets Stainless Steel DryerHadDownBmc~ts NlA Thermocouple Pads I Top Head Lifting Lugs 88E081/F920A27A 10 L 85 90 91 10 - -SO Thermocouple Pads I Top Head lifting Lugs 01 R4961S925A27A 10 L 62 64 68 10 - -50 Thermocouple Pads 432Z4521/B020A27A 10 L 83 94 96 10 - -SO Thermocouple Pads 06R8851DOO1A27A 10 L 56 58 67 10 - -SO Top Head Lifting Lugs 4322D471/BOO3A27A 10 L 100 102 106 10 - -50 Jet Pump Riser Pads Stainless Steel Refueling Bellows Skirt 915L65 10 L 130 80 129 10 - -SO Stabilizer Brackets 401 ZB811/K914A27A 10 L 111 119 120 10 - -SO Stabilizer Brackets 08R48181S922A27A 10 L 65 68 69 10 - -SO Stabilizer Brackets 402A04621B023A27A 10 L 75 n 86 10 - -SO Insulation Brackets 04R976/COO4H1A 10 L 76 79 81 10 - -SO Insulation Brackets 04R9761COO6H1 A 10 L 41 122 123 28 - -32 STUDS: LST 1VI<-61 6720443 10 n/a 35 36 37 n/a 70 6780382 10 n/a 41 41 41 n/a 70 51

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE, DATE]

Table B-7: PBAPS Unit 2 Adjusted Reference Temperatures for up to 32 EFPY l.Dvwtr*lrt....,.ct.. Shell Rat.. and Aldal Wei..

Thickness In Inches:II 6.125 54 e:PV Peak 1.0. fluence :II 1.61E+18 nlan 2 32 e:PV Peak 1/4 T fluence : 6.61E+17 nlan 2 l.Dvwtr st.Il Rat.., Cret.mferentlal Weld and Aldal Wei..

Thickness In Inches: 6.125 54 e:PV Peak 1.0. fluence : 123E+18 nlan 2 32 e:PV Peak 1/4 T fluence : 5.05E+17 nlan 2 Water l8Vea InetrwnerUtlon NaaI. (l.Dwer*lrterrl*late Shell)

Thickness In Inches= 6.125 54 e:PV Peak 1.0. fluence : 5.69Et-17 nlan 2 32 e:PV Peak 1/4 T fluence : 2.33E+17 nlan2

"'."). ,,;;~

,,:;'i'

';,'."';'. :. <.. ,,:: .:y,'"

'J;;

,J, . .,;' ,.:.,:'. :.. ,),: .,. .:~ :' .",.::

'*>\:"N ..

,.ii:::;:*" ,::': f';;:"';:: .. . ."": .EfIi("

- - - ~~t.!4: . *' ...., .J~il*'\

';",i:.; '

iI",'.;:)) HfA"li/i" **:*~,.i;Js.'.

c'"

.. W,'%CXI\" .:;ii:** *,:*nIt:.:;:' ". tm'iL ,<::';.: oj:;:

, ~f lr' ", .. ..

~

i

*c. !>.

oyi;J,' ic' rvan":,,

.*......P!':*

'\:. :.: ..

.: .OF"

,':c...

""~PT:: .op;i, PlANT*SPEClFlC "OIEMSTAES PlATe!t C2791-2 0.12 0.52 81.4 -8 5.05E+17 23.9 0 12.0 23.9 47.9 39.9 Lower Shell C2761-1 0.11 0.54 73.4 -14 5.05E+17 21.6 0 10.8 21.6 432 292 Mark 57 C2873-2 0.12 0.57 82.4 -20 5.05E+17 242 0 12.1 24.2 48.5 28.5 C2894-2 0.13 0.42 85.6 -20 6.61E+17 29.0 0 14.5 29.0 58.1 38.1 lower-ntermedlate SleD C2873-1 0.12 0.57 82.4 -6 6.61E+17 27.9 0 14.0 27.9 55.9 49.9 Mark 58 C2761-2 0.11 0.54 73.4 -20 6.61E+17 24.9 0 12.4 24.9 49.8 29.8 AXIAL WB.DS:

Lower Sletl 81.B2,83 370)65 0.182 0.181 94.5 -45 5.05E+17 27.8 16 13.9 42.4 702 252 Lower-tnt Sletl C1 .C2.C3 370)65 0.182 0.181 94.5 -45 6.61E+17 32.0 16 16.0 45.3 n.3 32.3 CRCUMFERENTlAL WElDS:

g,3986 Unde 124 BC Lot 3876 0.056 0.96 76.4 -32 5.05E+17 22.5 0 112 22.5 45.0 13.0 NOZZLES:

N16 Forging [1] C2873-1 0.12 0.57 82.4 -6 2.33E+17 15.6 0 7.8 15.6 312 252 N16 weld [1] Alloy 600 BESr ESTlMAlE OtEMSTAEB from ElNRVlf'.135 R1 BC [ ] 792 -32 5.05E+17 23.3 0 11.7 23.3 46.6 14.6 I I INTEGRAlB) SURVEILlANCE PROGRAM (ElNRVlf'.135 Rt):

[

I I ]

Aate [2] 65.0 -20 6.61E+17 22.0 0 11.0 22.0 44.1 24.1 Weld [3] [ ] 842 -45 6.61E+17 28.6 0 14.3 28.6 57.1 12.1 Notes:

[1] The N16 water level Instrumentation NoZ2te occurs in the beltline region. Because the forging Is fabricated from Alloy 600 material, the ART is cala.llated using the plate heats where the nozzJes occur. The weld connecting the forging to the vessel shell is also Alloy 600 material, and is not required to be evaluated.

[2] The IS' plate material is not the vessel target material, but does occur within the Unit 2 beltline region (lower-Intermediate Slell} Therefore, this material is oonsidered in determining the limiting ART: O1ly one set of surveillance data is currently available; therefore, upon testing of a semnd Is:>> capsule sdleduled for 2018, the a= can be reviewed.

[3] The IS' weld material is not the vessel target material and does not occur within the Unit 2 beltllne region. Therefore, this material is not considered in determining the limiting ART: The a= is determined using R31.99 for the IS' chemistry.

52

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE: DATE]

Table B-8: PBAPS Unit 2 Adjusted Reference Temperatures for up to 54 EFPY lDwer-lrtermedate SMII Plat. . and Ald** Wei..

Thickness In Inches- 6.125 54 e:PY Peak J.D. fluence:: 1.61E+18 54 a:P( Peak 1/4 T fluence:: 1.11E+18 Lower SIwII Plate.. CrCl.l'l'lllrentl.' Weld and AU' Weide Thickness In Inches- 6.125 54 a:P( Peak J.D. fluence:: 123E+18 54 a:Pf Peak 1/4 T fluence:: 8.52E+17 Water Lavel Il1Itn.a11entat'on Nar.de (lDw8r-'ntennec:hta hll)

Thickness In Inches- 6.125 54 a:P( Peak 1.0. fluence = 5.69E+17 54 a:P( Peak 1/4 T fluence:: 3.94E+17

. :: /:i:':.,......... . : :.::.,: . ........': :': .

PLANT-SPB:IFlC OIBISTRIEB PlATB!t Lower S1eII C2791-2 0.12 0.52 81.4 -8 8.52E+17 31.4 o 15.7 31.4 62.8 54.8 I\1ark 57 C2761-1 0.11 0.54 73.4 -14 8.52E+17 28.3 o 14.1 28.3 56.8 42.6 C2873-2 0.12 0.57 82.4 -20 8.52E+17 31.8 o 15.9 31.8 63.5 43.5 lower-ntermedlate Slell C2894-2 0.13 0.42 85.6 -20 1.11E+18 37.6 o 17.0 34.0 71.6 51.6 I\1ark 58 C2873-1 0.12 0.57 82.4 -8 1.11E+18 362 o 17.0 34.0 702 642 C2781-2 0.11 0.54 73.4 -20 1.11E+18 322 o 18.1 322 64.4 44.4 A>CIAL waoa Lower SleH 81,82,83 37CD65 0.182 0.181 94.5 -45 8.52E+17 36.4 18 182 48.5 84.9 39.9 lower-nt Stetl C1 ,C2,C3 370>65 0.182 0.181 94.5 -45 1.11E+18 41.5 18 20.7 52.4 93.9 48.9 5-3988 Unde 124 Be lot 3878 0.058 0.96 78.4 -32 8.52E+17 29.5 o 14.7 29.5 58.9 28.9 NOl2L.EB N18 Forging [1] C2873-1 0.12 0.57 82A -8 3.94Et-17 212 o 10.8 212 42.3 36.3 N18 Weld [1] ,AJ1oy 600 EEBr ESnMATE OIBISTAES from BNR\4P.135 R1 Be ] 792 -32 8.52E+17 30.5 o 15.3 30.5 61.1 29.1 I I I INlCGRATED SJR\BUANCE PRJGRAM (BNR\4P.135 R1~

I I I Aate [2] ] 65.0 -20 1.11E+18 28.5 o 14.3 28.5 57.1 37.1 Weld [3] ] 842 -45 1.11E+18 37.0 o 18.5 37.0 73.9 28.9 Notes:

[1] 'The N18 Water Levei instrumentation Nozzte occurs In the beltllne region. Because the forging is fabricated from Alloy 600 material, the ART' Is calculated using the plate heats where the nozztes occur. The weld connecting the forging to the vessel shetl Is also ,AJ1oy 600 material, and Is not required to be evaluated.

[2] 'The 19' plate material Is not the vessel target material, but does oca.r within the Unit 2 beltllne region (lower-ntermedlate Sletl} Therefore, this material Is considered In determining the limiting ART. 011y one set of survelHance data Is currently available; therefore, upon testing of a second 19' capsule scheduled for 2018, the a= can be reviewed.

[3] The 19' weld material Is not the vessel target material and does not occur within the Unit 2 beltline region. Therefore, this material is not considered In determining the limiting ART. 'The a= Is determined using R31.99 for the 19' chemistry.

53

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVe>DATPl Table B-9: PBAPS Unit 2 RPV Beltline P-T Curve Input Values for 54 EFPY Adjusted RTNOT =Initial RTNOT + Shift A = -6 + 70.2 = 64.2°F (Based on ART values)

Vessel Height H = 875.125 inches Bottom of Active Fuel Height B = 216.3 inches Vessel Radius (to base metal) R = 125.7 inches Minimum Vessel Thickness (without clad) t = 6.125 inches 54

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFEC'[lVE.DATEl Table B-I0: PBAPS Unit 2 Definition of RPV Beltline Region[l]

Elevation Component (inches from RPV ti~)

Shell # 2 - Top of Active Fuel (TAF) 366.31" Shell # 1 - Bottom of Active Fuel (BAF) 216.31" Shell # 2 - Top of Extended Beltline Region (54 EFPY) 381.1" Shell # 1- Bottom of Extended Beltline Region (54 EFPY) 205.8" Circumferential Weld Between Shell #1 and Shell #2 258.69" Circumferential Weld Between Shell #2 and Shell #3 391.69" Centerline of Recirculation Outlet Nozzle in Shell # 1 161.5" Top of Recirculation Outlet Nozzle Nl in Shell # 1 188.0" Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0" Top of Recirculation Inlet Nozzle N2 in Shell # 1 193.5" Centerline of Water level Instrumentation Nozzle in Shell # 2 366.0" Bottom of Water level Instrumentation Nozzle in Shell # 2 364.6"

[1] The beltline region is defined as any location where the peak neutron fluence is expected 2

to exceed or equall.0e17 n/cm

Based on the above, it is concluded that none of the PBAPS Unit 2 reactor vessel plates, nozzles, or welds, other than those included in the Adjusted Reference Temperature Table, are in the beltline region.

55

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EfFE.¢tIVaj;fJ~r~]

Appendix C: PBAPS Unit 3 Reactor Pressure Vessel P-T Curve Supporting Plant-Specific Information 56

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE,DATS]

Figure C-1: PBAPS Unit 3 Reactor Pressure Vessels

- - TOf.'t-teAO TOP HEAD FLANG,!

SHE LL FLANGE SHEll.S SHELL #4 rop OF GIRTH /

\l\ElO MfAL \'VeLDS *

(ESV'JI) F1, F2. F3 SHELL #3 ACTIVE FUEl (TAF) 36Er

~EF)

--1zm~~~.~~~~~~,'i2'."~"~'~~ "

SHELLn AXIAL \tVELDS (ESWI) Et E2. E3, aOTTouor: SHE,lLJ.1 ACTIVE FUEL (BAF) 216" ---I

" - - - SUP'PORT SKIRT 57

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ 1" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEcrIVEDAT~]

Table C-1: PBAPS Unit 3 Initial RTNOT Values for RPV Materials Top Head and Cylindrical Shell Materials PLATES & FORGINGS:

Top Head & Flange Shell Flange IVk. 40-146-0 123V245 ACN-97 10 L 127 109 96 40 10 10 Head Flange IVk. 209-139-2 124T-609 AAL-95 10 L 54 81 87 40 10 10 Top .Head Dollar Wk. 201-127-2 C2426-4 40 L 75 74 64 70 40 40 Top Head Side Plates Wk. 202-139-8 C2737-1 10 L 73 64 55 40 10 10 Wk. 202-139-9 C2765-4 10 L 75 77 77 40 10 10 Wk. 202-139-10 C2765-4 10 L 74 82 78 40 10 10 IVk. 202-139-11 C1982-1 10 L 90 60 45 50 10 10 Wk. 202-139-12 C1982-1 10 L 76 74 69 40 10 10 IVk. 202-146-4 C3262-1 10 L 82 110 72 40 10 10 Shell Course.

Shell 5 Wk. 6-146-2 C4598-1 10 L 42 80 80 56 10 10 Wk. 6-146-3 C4679-1 10 L 65 71 80 40 10 10 IVk. 6..146..5 C4684-1 10 L 81 51 63 40 10 10 Shell 4 Wk. 15.146-1 C4613-2 10 78 75 72 40 10 10 Wk. 15.146-4 C4613-1 10 69 78 82 40 10 10 IVk. 15.146-6 C4608-2 10 73 85 84 "",.4(), 10 10 Shell 3 Wk. 6-146-2 C4654-1 10 L 55 77 79 40 10 10 IVk. 6-146-4 C4689-1 "

10 L 96 105 60 40 10 10 IVk. 6-146-5 C4608-1 10 L 102 90 82 40 10 10 Shell 2 IVk. 6-139-10 C2773-2 10 44 56 48 52 10 10 Wk. 6-139-11 C2775.1 10 58 66 68 40 10 10 IVk. 6-139-12 C3103-1 " J(l, 57 66 76 ,40 , "JQ 10 Shell 1 IVk. 6-146..1 C4689-2 ,1Q " L, 101 78 69 ... ,- .... 40 ",,-10 -10 IVk. 6-146..3 C4684-2 10 L 63 60 60 40 -20 -20 Wk. 6..146..7 C4627-1 10 " ,,,L, 68 82 90 40 ",' ~,20 -20 58

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by tI[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[Eff~~gIY~RAI'] ,

Table C-2: PBAPS Unit 3 Initial RTNOT Values for RPV Materials Bottom Head and Support Skirt Materials Bottom Head Up~rTorus ."

Wk.. 2*12!*1~ . . ,.. . . . . . ,G?3~3-3.. ,.. 4() ..... 104 .124 . 1~3. ,.. !o.... , ........~9.. ...40....

Wk. 2-145-1 . ".....925?1-2.,..... 40 125 105 129 70 40 40 Wk., ?-14tt4'.' ,93069-1 40 ",.", "", ',' I 6~, ,',' '69' ",' ~ , **'.",!9,..'...', . . 49.... , . . . **40" 87267-2 103 91 106 70 40 40 Wk. A2-146-2

. ,.. , ""87255-2*** , ' , 4040, 81 "28 "'64' . . , 114 Wk. A2*146-4 ,49" """&f' Wk~A2~ 146-tJ... ......................... ,,~!2~.1:~ " ......", ......"4.9 . . 100 1,(),1 ...... ~ ,..... , !().. ," ..... ,.49, 49 ,

Lower Torus Wk*.: ~14&.3:::""*" ... ... C3436-~, ""40'" 72 :':.,~? 75 '....rri*..' . . . 'f().. '"4Cf

Wk. 4-146-1 C2123-50 40 59 57 63 . . ".!().. ,..... , 40 40 rvt<. "'4-14~2 . . "'",*¢2.12.3~$Q*",',**' , 40 .,,{)Q 50 ,','~,.,4~', . ,... ~ . ", . , "",'"*'*'.*,','.,4cL*,,.. "49,"",,'

Wk. 4-146-4 ""'"''''' 9;3,4~~ " ,49 . 34 ""48 55 . J.o.?,.. 40 42 8ott0I'1l.t-i~~ . P.<>.!.I~r ,"u,,,,.,...,

M<.,J~.14~1., """'**,**"""'**""'*"":':"':*:~:*:*:**~*:':c,~3~,2".':"'*"" 40 65 55 ..... ~

Suppol1,.8ldl1, "

Knuckle Wk*~~,~,4~t~r()ugh~,.....,. J\4~6-t" ,4Q, .",,,,,..,, "',' ' ',','.'.',

122 *.*'j9~o.j~i ,. w ,',.**.., .. ,.w.,.~, ..",.,,,.., .

Skirt .

Wk. 40.1 A4973-5BA 40 110 115 110 wk~" 30:2' . . ,..

. .... ,A4.9.!~~~~ . '.. """40"" I .. *.... *.. *, .. "" .... , 1132 '110 ',*. 'tI,Q 8a~eRi.ng... .

rvt<.. . 41.... . , 9~~2Jt ... . .49.. . . ~?.. .."'~. . . .~. ~,

I,w.w ...,'.w.,.....,,'.. ... :-., ...,., .. , . . . . . . ..

59

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEerIV~DAT~]

Table C-3: PBAPS Unit 3 Initial RTNOT Values for RPV Materials Nozzle Nl through N3 Materials Nozzles:

N1 Recirc Outlet Nozzle N1A AV1650 Lot N7J.6388 40 L 50 69 69 70 40 40 N1B E31VW Lot 431H-2 ~O L 73 90 95 70 40 40 N2 Recirc Inlet Nozzle N2A AV1809 Lot 7J-6260B 40 L 64 78 42 86 0 26 N2B AV1684 Lot 7J.6305A 40 L 68 116 102 70 40 40 N2C EV9934 Lot 7G-6195 40 L 30 40 31 110 0 50 N2D AV1660 Lot 7J.6110B 40 L 31 34 42 108 40 48 N2E AV1809 Lot 7J-6259B 40 L 85 58 88 70 0 10 N2F AV1660 Lot 7J.6110A 40 L 31 34 42 108 40 48 N2G EV9947 Lot 7G-6204 40 L 72 75 112 70 0 10 N2H AV1809 Lot 7J-6259A 40 L 85 58 88 70 0 10 N2J AV1684 Lot 7J.6305B 40 L 68 116 102 70 40 40 N2K AV1809 Lot 7J-6260A 40 L 64 78 42 86 26 N3 Steam Outlet Nozzle N3A A\J1973 Lot NaA-60S9 40 L 35 58 '74 100 40 40 N3B AV2018 Lot N8A-6185 ' 40 L 66 41 46 88 40 40 N3C AV2029 Lot N8~186, , .. , 40 L 78 34 60 102 40 42 N3D AV1998 Lot NBA-6184 40 L 56 38 34 102 40 42 60

EPRI Non-Proprietary Information In Accord~nce with 10 CFR 2.390

/ As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[ EFFECTIVE:DAT~]

Table C-4: PBAPS Unit 3 Initial RTNOT Values for RPV Materials NOlzle N4 through N16 Materials N4 Feedwater Nozzle N4A AV1909 Lot 7K-6126A 40 L 85 67 89 70 40 40 N4B AV1951 Lot 7K-6247B 40 L 85 91 68 70 40 40 N4C EV9812 Lot 7J-6153B 40 L 62 112 76 70 40 40 N40 AV1970 Lot 7K-6350B 40 L 80 110 98 70 40 40 N4E AV1945 Lot 7K-6246B 40 L 80 68 106 70 40 40 N4F AV1945 Lot N80-6144 10 L 47 116 86 46 40 40 N5 Core Spray Nozzle N5A 'Ev26vW Lot 437H-4 "40 C' 107 '71 "'89 70 40 40 N5B EV9964 Lot N7H-6029 40 L 38 42 44 94 0 34 N6 Top Head Spray Nozzle N6A BT2615 Lot 4 40 L 123 143 144 70 40 40 N6B zr3043 Lot 4 40 L 170 158 142 70 40 40 N7 Top Head Vent Nozzle zr3043 Lot 3 40 L 102 130 117 70 40 40 N8 Jet Pump Instrumentation Nozzle N8A &N8B BT2615 Lot 2 40 132 118 120 70 40 40 I""

N9 CROHYo System Retum Nozzle EV9143 Lot N7H-6020A 40 L 94 92 96 70 -10 10 N10,Core Delta P& Liq Cant. Nozzle ZT3403 Lot'1 40 155 154 156 I 70 40 40 N1 f Instrurnentation Nozzle N11A& N11B I***,""""',',',,'.,*',',',,,""""""."" '.",'"',.',','....,, " " " " " " " " " " " " " " " " " " " " ' " ' ' ' ' ' ' ' ' 1**,,""'0""""""""''0' I*,

N12InstrumentStion,Nozzle, N12A& N12B 8601 LotJ(lnco"eI)

N13 High f>>ressu~e Seal Leak Detector: , ,,A27~N(lnc;onef)

.''""",,,,,, *.,,,,,,,,,,,,,., ',"""" I'" I"","""""

N14 Low Pressure Seal Leak Detector ' ,',A:?:?,~N.',(lrl~t?,,~I,)

N150rainNoZzie '" .. ,. ' ""1579" 40 . 39 "34' ., . 55 '102" ""'40" '::,:4?: :'"

N161nstrumentation Nozzle N16A 8601~ot1(lncon'el)".

N16B ,~~1~ Lot4 (513166) 61

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE'CTIVE DATE]

Table C-5: PBAPS Unit 3 Initial RTNOT Values for RPV Materials Vertical Weld Materials VVELDS:

Vertical Welds Bottom head Torus Ring 1 - B1, B2, B3, B4 N1A 40 Bottom Head Torus Ring 2 - C1, C2, C3, C4, C5, C6 N1A 40 Shell Course 1 - 01,02,03 37C065 (Electroslag Weld) -45 Shell Course 2 - E1, E2, E3 37C065 (ElectroslagWeld) -45 Shell Course 3 - F1, F2, F3 37C065 (Electroslag Weld) -45 Shell Course 4 - G1, G2, G3, G4, G5, G6 N1A 40 Shell Course 5 - H1, H2, H3 N1A 10 Topttead Torus :~1,K2,K3,K4,K5, K6 06R885 1 0001A27A 10 56 58 67 10 -50 78B743 1C727A27A 10 100 92 119 10 -50 S3986 138761 934 -20 123 92 158 -20 -50 06l1651 F017A27A 10 60 61 62 10 -50 06l1651 F011A27A 10 84 89 92 10 -50 01L333 1 L908A27A 10 50 53 56 10 -50 421Z0611/L908A27A 10 66 79 80 10 -50 62

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Table C-6: PBAPS Unit 3 Initial RTNOT Values for RPV Materials Girth Weld Materials Girth Weld.

Dollar Plate to Torus Ring 1 - AS 88E081 1 F920A27A 10 85 90 91 10 -50 S3986 138761 934 -20 123 92 158 -20 -50 CTY538 1NJ27A27A 10 94 ... 95 95 10 -50 CTY538 1 B012ft2.7A

,. .. " - ., " .. , ," . .. 10 n 81 .....8! 10 -50 432AB8711 B003A27~ . 40 04R976 1 C004A27A 10 76 79 81 10 -50 Torus Ring 1 to Torus Ring 2 - BC S3986 138761 934 -20 123 92 158 -20 -50 Torus Ring 1 to Shel'.1 - CD 78B743 1C727A27A 10 100 92 119 10 -50 S3986 138761934 -20 123 92 158 -20 -50 Shell 1 to Shell 2 - DE 3P4000 139321 989 Tandem 10 97 96 90 10 -50 3P4000 13932/989 Single 10 97 ,. 95 88 10 -50 071669 1 KOO4A27A 10 50 50 54 10 -50 Shell 2 to SheH 3 - EF 411 A3531 1 HOO4A27A 10 60 "eo 68 10 -50 421A6811 1 F023A27A 10 75 n 80 10 -50 1P4217/3929/989 Tandem

. ." . .., .. ....., . 10 62 68 63 10 -50 1P42171 39291 989 Single .10. .. 56 71 60 10 -50 Shell 3 to Shell 4 - FG 08R481 1 J908A27A 10 81 ... 81 ..82 10 -50

."'" 01R4'96! S925A27A'"

"4()'

S3986 138761 934 -20 123 92 158 -20 -50 432ZD471/BOO3A27A .... , . . . . . . . '.,--,- ., "

10 100 102 106 10 -50

~Ot3~21 S~~3~!~" . . . 19... n 78 . ,!~, 10 -50 Shell 4 to Shell 5 - GH ,..1F'4218 /3~2~J~a.~~lngl~ .. ,10 98 100 .102 10 -50 411A3531/H004A27A 10 60 "'eo 68 10 -50 Shellfito Shell Flange -HJ S3986/ 3876/934 -20 123 "92 158 ... ,...... ,'.

-20 -50

.... .... ..432ZD471/BOO3A27A 10 100 102 106 10 -50 05R938/ NJ20A27A 10 Head Flange to Top. Head Torus ,- JK CTY538/ NJ27A27A 10 94 95 95 10 -50 08R4818/S922A27A 10

. 401Z9711iNJ22A2iA ,."

10 98 99 104 10 -50 1P4217/3929/989 Tandem 10 62 68 63 10 -50 "tF'~?17..1 ~9~91989 Singlt:i 10 56 71 60 10 I**,**

-50

. ,.~t1A3.~3.1.r.HO()4J\?'7J\ .. . . ,....10, .60 ,fjO .".~ 1()... -50 421A6811/F023A27A 10 75 n 80 10 . ,.,:~O, 06l165/ F017A27A 10 60 61 62 10 -50

...... ,,91 ~33.~JF()25A27J\ " 10 50 53 56 .

, ,,, .. . .., 10 -50 Top l-ieadTorus toD~lIar Plate -KM 01 l333/ F025A27A 1..*. 1,<) 50 53 56 10 -50 JJ=>>4?1!J 3.92~/~89.Tandell1 10 62 68 0.' ,,,

63 ..,...........10 -50 1P421713929/989 SinglEt 10 56 71 60 10 -50 421A6811 1 F023A27A 10 75 n 80 10 ",,""

-50 402NJ41 1 B026A27A 10 86 87 95 10 -50 06l165/ F017A27A 10 60 61 62 10 -50 63

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEcrI'V~PATS]

Table C-7: PBAPS Unit 3 Initial RTNOT Values for RPV Materials Bolting Materials STUDS:

t.t<-61 6720443 10 35 37 40 70 6780382 10 43 43 43 70 5P3629 10 43 37 30 70 6788210 10 40 45 46 70 NUTS: 6780382 10 42 42 42 70 64

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by n[ In PBAPS Unit 2 and Unit 3 PTLR Rev. 0

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Table C-8: PBAPS Unit 3 Adjusted Reference Temperatures for up to 32 EFPY I~ermedlat. bll Plat.. and AJdaI Welda Thickness In Inches* 6.125 54 e:Pt' ~ak 1.0. fluance :I 9.54Et-17 n/cm 2 32 e:Pt' ~ak 1/4 T fluance :::I 3.91Et-17 nlcm 2 lA:Mw*lrtermedate bll Plat.. and AxIal Welda Thickness in Inches- 6.125 54 e:Pt' ~ak 1.0. fluance :I 1.53Et-18 n/cm 2 32 e:Pt' ~ak 1/4 T fluenoe ::I 6.28Et-17 n/cm2 L.a.wr hll Plat.., ara.mlerertlal Weld and AxIal Welda Thickness in Inchep 6.125 54 e:Pt' ~ak 1.0. fluance :I 9.48Et-17 n/cm 2 32 e:Pt' ~ak 1/4 T fluance :I 3.89Et-17 n/cm 2 Water lJtvel Il1Itrwnertatlon Narzte (Lower.lrt....,...at. hll)

Thickness in inches. 6.125 54 e:Pt' ~ak 1.0. fluence :::I 5.69Et-17 nlcm 2 32 e:Pt' ~ak 1/4 T fluence ::I 2.33Et-17 n/cm 2

..... (

. :: . /, ".':'. ~;lit

...... ' .. ).

i"" , }

.. '-.:r:;, ;','1; '.' .: ...

~H:.

".rfi)".:,. t*;;;'. _.jC, r_ _

'0 11"

.-*.*~.~i:'; *. .;.... :;. *;:';G~'~ tk ,. ~:>':

. .; .. ' .*.*:. ',O'

.:': .. "", Xi "': bi',,;':i"'i,* :ii:(,

'.'J'l;:::' .l r\,il.1 Il:'ii' ,. "'.

FlANT*SPB:IFlC otEMSI'RIEB '.

PlATBt l.Dwer hll 6-148-1 C4689-2 0.12 0.56 822 -10 3.89Et-17 21.0 0 10.5 21.0 41.9 31.9 6-148-3 C'A684-2 0.13 0.58 90.4 -20 3.89Et-17 23.0 0 11.5 23.0 46.1 26.1 6-148-7 C'A627-1 0.12 0.57 82.4 -20 3.89Et-17 21.0 0 10.5 21.0 42.0 22.0 L.a.wr*lrtermedlat. hll 6-139-10 C2773-2 0.15 0.49 104.0 10 628Et-17 34.3 0 17.0 34.0 68.3 78.3 6-139-11 C2775-1 0.13 0.46 86B 10 628Et-17 28.7 0 14.3 28.7 57.3 67.3 6-139-12 C3103-1 0.14 0.6 100.0 10 628Et-17 33.0 0 16.5 33.0 66.1 76.1 I~ermedlate hll 6-148-5 C'A608-1 0.12 0.55 82.0 10 3.91Et-17 21.0 0 10.5 21.0 42.0 52.0 6-148-4 C'A689-1 0.12 0.56 822 10 3.91Et-17 21.0 0 10.5 21.0 42.1 52.1 6-146-2 C'A654-1 0.11 0.55 73.5 10 3.91Et-17 18.8 0 9.4 18.8 37.6 47.6 AXIAL WB.DS:

Lower Sletl 01,02.03 37CXl65 0.182 0.181 94.5 -45 3.89Et-17 24.1 16 12.0 40.1 64.1 19.1 lower-Int Slell E1,E2,E3 37CXl65 0.182 0.181 94.5 -45 628Et-17 312 16 15.6 44.7 75.9 30.9 Intermediate SleII F1 ,F2,f3 37CXl65 0.182 0.181 94.5 -45 3.91Et-17 242 16 12.1 40.1 64.3 19.3 aRCUPIRH:NTIAL waoa 3f14OOO Unde 124 lower to lower-nt DE lot 3932 0.020 0.934 27.0 -50 3.89Et-17 6.9 0 3.4 6.9 13B -362 1fl4217 Unde 124 lower-nt to intermediate s:- lot 3929 0.102 0.942 136.9 -50 3.91Et-17 35.0 0 17.5 35.0 70.0 20.0 NClZZl.BJ:

N16 [1] C'A689-1 0.12 0.56 822 10 2.33Et-17 15.5 0 7.8 15.5 31.1 41.1 BESr ESnMATE otEMSTRIEB frc:m BWRVIf'.135 RI DE [ ] 27.0 -50 3.89Et-17 6.9 0 3.4 6.9 13.8 -362 s= [ ] 139.3 -50 3.91Et-17 35.6 0 17.8 35.6 71.3 21.3 INTEGRATBl SUIM:lUANCE PRJGRAM (ElNRVlf'.135 R1): I I Rate [2] [ ] 11125 10 628Et-17 36.7 0 17.0 34.0 70.7 80.7 Weld [3] [ ] 82.0 -45 628Et-17 27.1 0 13.5 27.1 542 92 Weld [3] [ ] 108.0 -45 628Et-17 35.7 0 17.8 35.7 71.3 26.3 Notes:

[1] The N16 Water Level nstrumentatlon Nozzte occurs in the bettUne region. Because the forging is fabricated from ,AJ1oy 600 material, the ART is cala,dated using the plate heats where the no22tes occur. The weld connecting the forging to the vessel shell Is also ,AJ1oy 600 material, and is not required to be evaluated.

[2] The IS' plate material is not the vessel target material and does not OCQJr within the Unit 3 beltUne region. Therefore, this material is not considered in determining the limiting ART. The a= is determined using R31.99 for the Is:>> chemistry.

[3] The IS' weld material Is not the vessel target material and does not occur within the Unit 3 beltline region. Therefore, this material is not considered in determining the limiting ART: The a= is determined using R31.99 for the IS' chemistry.

[4] The IS' best estimate chemistry is used.

65

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PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFE.GTlVEipAcTRl Table e-9: PBAPS Unit 3 Adjusted Reference Temperatures for up to 54 EFPY Thlcknllla In incheP 6.125 54 8T'V RlIIk 1.0. ftUenaI " 9.54Et-17 54 8T'V Alek 1/4 T ftUenaI .. 6.61Et-17 ThIckne8a In IncheP 6.125 54 8T'V RlIIk 1.0. ftuence .. 1.53Et-16 54 8T'V Alek 1/4 T ftuence " 1.06Et-18 LcMw StwII "'..... a r ~ Weld and A1dIII Weldl Thlckneea In IncheP 6.125 54 8T'V RllIk ID. ftuence " 9.46Et-17 54 8T'V Alek 1/4 T ftuence " 6.56Et-17 W.w l.weI 1~1UtIon Naale (LcMw.lnternwdI... StwII)

ThIckne8a In InchelP 6.125 54 8T'V Peak 1.0. ftuence " 5.69Et-17 54 8T'V Alek 1/4 T ftuence " 3.94Et-17 PlANT*SPB:IFlC OtEMSnlIBI AAlIB:

LcMw StwII 6-146-1 C4689-2 0.12 0.56 822 -10 6.56Et-17 27.8 0 13.9 27.8 55.6 45.6 6-146-3 C4684-2 0.13 0.58 90.4 -20 6.58Et-17 30.6 0 15.3 30.8 61.1 41.1 6-146-7 C4627-1 0.12 0.57 82.4 -20 6.56E+17 27.9 0 13.9 27.9 55.7 35.7 LcMw*lrUmwcIrJIte StwII 6-139-10 C2773-2 0.15 0.49 104.0 10 1.06Et-18 44.6 0 17.0 34.0 78.6 88.8 6-139-11 C2n~l 0.13 0.46 88.8 10 1.06Et-18 372 0 17.0 34.0 712 812 6-139-12 C3103-1 0.14 0.8 100.0 10 1.06Et-16 42.9 0 17.0 34.0 76.9 88.9 111lerrrwcI... s.a 6-146-5 C48OlI-l 0.12 0.55 82.0 10 6.61Et-17 27.8 0 13.9 27.8 55.8 65.6 6-146-4 C4689-1 0.12 0.56 822 10 6.61Et-17 27.9 0 13.9 279 55.7 65.7 6-146-2 C4654-1 0.11 0.55 73.5 10 6.61Et-17 24.9 0 12.5 24.9 49.8 59.8 AlCIM. WB.DlI:

Lower 91eII 01,02,03 37CXl65 0.182 0.181 94.5 45 6.58Et-17 319 16 18.0 452 n2 322 Lower-Int 91eII El,E2,E3 370J85 0.182 0.181 94.5 45 1.06Et-16 40.5 16 202 51.6 92.1 47.1 Intennedlate 91eII Fl.P2,F3 370J85 0.182 0.181 94.5 45 6.61Et-17 32.0 16 16.0 45.3 n.3 32.3 aRCUll CUlTlAL WB.DlI:

3fl4OOO Unde 124 Lower to Lower-n! DE Lot 3932 0.020 0934 . 27.0 -50 6.58Et-17 9.1 0 4.6 9.1 16.3 -31.7 1Fl4217 Unde 124 Lower-n! to Intennedlate e: Lot 3929 0.102 0.942 1369 -50 6.61Et-17 46.4 0 232 46.4 92.8 42.6 NaZ2LCt N16 (1) C4689-1 0.12 0.56 822 10 3.94Et-17 21.1 0 10.6 21.1 422 522 BEBr ESlllMlE CHMlJTRUt fran BWR\llJI'.l35 Rl DE [ 1 27.0 -50 6.58Et-17 9.1 0 4.6 9.1 16.3 -31.7 e: [ 1 139.3 -50 6.61Et-17 472 0 23.6 472 94.5 44.5 INTBlRAlID SJlMlUAHCE PRJGIWI (IIlIVfMJI'.135 Rl): I I Hate [2) [ 1 11125 10 1.06Et-18 47.7 0 17.0 34.0 81.7 91.7 WlIkI [3) [ 1 82.0 45 1.06Et-18 35.1 0 17.6 35.1 70.3 25.3 WlIkI 131 [ 1 108.0 45 1.06Et-18 46.3 0 23.1 46.3 92.6 47.8 Notes:

[1) The N16 Water Level Instrumentation NoZ2le oca.n in the belli,. region. Because the forging is fabricated from May 600 material, the !'RT is calculated using the plate heats where the noZ2les occur. The weld connecting the forging to the V8888I shell is also May 600 material, and is not required to be evaluated.

[2) The Il'P plate material is not the V8888I target material and does not occur w~hln the um 3 beIlllne region. Therefore, this material is not considered In detennining the Iim~lng !'RT. The a:: Is delennined using R3199 for the Il'P chemistry.

[3) The Il'P weld material is not the v8S881 target material and does not occur w~hln the Un~ 3 belliine region. Therefore, this material is not considered in delennining the Iim~ing ARr. The a:: is determined using R3199 for the Il'P chemistry.

[4) The Il'P best estimate chemistry is used.

66

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ l" PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECZTI\lE"DATq]

Table C-10: PBAPS Unit 3 RPV Beltline P-T Curve Input Values for 54 EFPY Adjusted RTNOT = Initial RTNOT + Shift A = =

10 + 78.6 88.6°F (Based on ART values)

Vessel Height H = 875.3125 inches Bottom of Active Fuel Height B = 216.3 inches Vessel Radius (to base metal) R = 125.7 inches Minimum Vessel Thickness (without clad) t = 6.125 inches 67

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ lit PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFEqJV~,DAr$]

Table C-11: PBAPS Unit 3 Definition of RPV Beltline Region[l]

Elevation Component (inches from RPV liD")

Shell # 2 - Top of Active Fuel (TAF) 366.31" Shell # 1- Bottom of Active Fuel (BAF) 216.31" Shell # 2 - Top of Extended Beltline Region (54 EFPY) 381.1" Shell # 1- Bottom of Extended Beltline Region (54 EFPY) 205.8" Circumferential Weld Between Shell #1 and Shell #2 258.69" Circumferential Weld Between Shell #2 and Shell #3 391.69" Centerline of Recirculation Outlet Nozzle in Shell # 1 161.5" Top of Recirculation Outlet Nozzle N1 in Shell # 1 188.0" Centerline of Recirculation Inlet Nozzle N2 in Shell # 1 181.0" Top of Recirculation Inlet Nozzle N2 in Shell # 1 193.5" Centerline of Water level Instrumentation Nozzle in Shell # 2 366.0" Bottom of Water level Instrumentation Nozzle in Shell # 2 364.6"

[1] The beltline region is defined as any location where the peak neutron fluence is expected 2

to exceed or equal1.0e17 n/cm

Based on the above, it is concluded that none of the PBAPS Unit 3 reactor vessel plates, nozzles, or welds, other than those included in the Adjusted Reference Temperature Table, are in the beltline region.

68

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFECTIVEOATE]

Appendix 0: PBAPS Unit 2 and Unit 3 Reactor Pressure Vessel P-T Curve Checklist 69

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by tI[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVEDATEj Table 0-1: PBAPS Unit 2 Checklist m

Initial RTNDT Initial RT NOT has been determined for Additional plant-specific information PBAPS Unit 2 for all vessel materials was located for girth welds, nozzle including plates, flanges, forgings, studs, welds, and appurtenance welds. This nuts, bolts, welds. information is included in Appendix B.

All other information remains Include explanation (including unchanged from previous submittals.

methods/sources) of any exceptions, resolution of discrepant data (e.g.,

deviation from originally reported values).

Appendix B contains tables of all Initial RT NOT values for PBAPS Unit 2 Has any non-PBAPS Unit 2 initial RTNOT Plate heat C2761-2 and weld heat PB2 information (e.g., ISP, comparison to other ESW information was obtained from the plant) been used? ISP database. These materials are not identical heats to the target vessel material and, in accordance with the ISP guidance, this data was not used in determining the limiting ART.

If deviation from the l TR process occurred, No deviations from the LTR process.

sufficient supporting information has been included (e.g., Charpy V-Notch data used to determine an Initial RT NOT).

All previously published Initial RTNOT values RVIO was reviewed; all initial RT NOT from sources such as the GL88-01, RVIO, values agree; no further review was FSAR, etc., have been reviewed. performed Adjusted Reference Temperature (ART)

Sigma I (standard deviation for Initial Sigma I for the electroslag weld (ESW)

RT NOT) is O°F unless the RTNOT was obtained axial shell welds is equal to 16°F, and is from a source other than CMTRs. If 0'1 is consistent with previous submittals and not equal to 0, reference/basis has been the PBAPS UFSAR.

provided.

Sigma ~ (standard deviation for ~RTNOT) is determined per RG 1.99, Rev. 2 70

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEc;TIV~ DATE]

Include explanation (including methods/sources) of any exceptions, resolution of discrepant data (e.g.,

deviation from originally reported values).

Non-PBAPS Unit 2 chemistry information Heat S3986 has been evaluated using (e.g., ISP, comparison to other plant) used best estimate chemistry from the ISP.

has been adequately defined and Chemistry information for heats C2761-described. 2 and PB2 ESW was obtained from the ISP database.

For any deviation from the LTR process, No deviations from the LTR process.

sufficient information has been included.

All previously published chemistry values RVID was reviewed; all initial RTNOT from sources such as the GL88-01, RVID, values agree; no further review was FSAR, etc., have been reviewed. performed 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 2

of 1.0e17 n/cm 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 The N16 nozzle forging is Alloy 600 and where the vessel experiences a fluence does not require evaluation for fracture

~1.0e17 n/cm have been included in the 2

toughness. Therefore, the initial RTNOT ART calculation. All initial RTNOT and and chemistry information of the shell chemistry information is available or that includes the N16 nozzle is used.

explained.

71

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ )"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE DAT.E)

. . :~ttt ~.'L_

'. ~.

I'

~ ".

"'Pa~met'-

,~... "

-,a.- .....

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 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 The thickness discontinuity evaluation process for considering a thickness demonstrated that no additional discontinuity, both beltline and non- adjustment is required; the curves beltline. If there is a discontinuity in the bound the discontinuity stresses.

PBAPS Unit 2 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 basis for the CRD Penetration curve discontinuity and the appropriate transient application.

The PBAPS Unit 2 evaluation bounds the requirements of Appendix H.

Appendix J of the LTR defines the basis for the Water Level Instrumentation Nozzle curve discontinuity and the appropriate transient application. The PBAPS Unit 2 evaluation bounds the requirements of Appendix J.

72

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFECTIVE DATE]

Table 0-2: PBAPS Unit 3 Checklist

¥ l -r.::.~. j~

tal'1l<

.'*tr~: .' .

.. ri*

Initial RTNDT Initial RTNOT has been determined for PBAPS Unit 3 for all vessel materials including plates, flanges, forgings, studs, nuts, bolts, welds.

Include explanation (including methods/sources) of any exceptions, resolution of discrepant data (e.g.,

deviation from originally reported values).

Appendix C contains tables of all Initial RTNOT values for PBAPS Unit 3 Has any non-PBAPS Unit 3 initial RTNOT Plate heat B0673-1 and weld heat information (e.g., ISP, comparison to other 5P6756 information was obtained from plant) been used? the ISP database. These materials are not identical heats to the target vessel material and, in accordance with the ISP guidance, this data was not used in determining the limiting ART.

If deviation from the LTR process occurred, No deviations from the LTR process.

sufficient supporting information has been included (e.g., Charpy V-Notch data used to determine an Initial RTNOT).

All previously published Initial RTNOT values RVIO was reviewed; all initial RTNOT from sources such as the GL88-01, RVIO, values agree; no further review was FSAR, etc., have been reviewed. performed Adjusted Reference Temperature (ART)

Sigma I (standard deviation for Initial Sigma I for the electroslag weld (ESW)

RTNOT) is O°F unless the RTNOT was obtained axial shell welds is equal to 16°F, and is from a source other than CMTRs. If (J', is consistent with previous submittals and not equal to 0, reference/basis has been the PBAPS UFSAR.

provided.

Sigma ~ (standard deviation for ~RTNOT) is determined per RG 1.99, Rev. 2 73

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTLR Rev. 0

[EFFEctlVE DATE]

Chemistry has been determined for all No deviations from previously reported vessel beltline materials including plates, values.

forgings (if applicable), and welds for PBAPS Unit 3 Include explanation (including methods/sources) of any exceptions, resolution of discrepant data (e.g.,

deviation from originally reported values).

Non- PBAPS Unit 3 chemistry information Heats 3P4000 and 1P4217 have been (e.g., ISP, comparison to other plant) used evaluated using best estimate chemistry has been adequately defined and from the ISP. Chemistry information for described. heats B0673-1 and 5P6756 was obtained from the ISP database.

For any deviation from the LTR process, No deviations from the LTR process.

sufficient information has been included.

All previously published chemistry values RVID was reviewed; all initial RTNOT from sources such as the GL88-01, RVID, values agree; no further review was FSAR, etc., have been reviewed. performed 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 flue nee 2

of 1.0e17 n/cm 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 The N16 nozzle forging is Alloy 600 and where the vessel experiences a fluence does not require evaluation for fracture

~1.0e17 n/cm 2 have been included in the toughness. Therefore, the initial RTNOT ART calculation. All initial RTNOT and and chemistry information of the shell chemistry information is available or that includes the N16 nozzle is used.

explained.

74

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

PBAPS Unit 2 and Unit 3 PTlR Rev. 0

[EFFECTI\)~

DATE]

. ., ~.' ,,'

Discontinuities The discontinuity comparison has been performed as described in Section 4.3.2.1 of the l TR. Any deviations have been explained.

Discontinuities requiring additional 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 l TR describes the The thickness discontinuity evaluation process for considering a thickness demonstrated that no additional discontinuity, both beltline and non- adjustment is required; the curves beltline. If there is a discontinuity in the bound the discontinuity stresses.

PBAPS Unit 3 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 l TR defines the basis for the CRD Penetration curve discontinuity and the appropriate transient application.

The PBAPS Unit 3 evaluation bounds the requirements of Appendix H.

Appendix J of the lTR defines the basis for the Water level Instrumentation Nozzle curve discontinuity and the appropriate transient application. The PBAPS Unit 3 evaluation bounds the requirements of Appendixl 75

ATTACHMENT 6 Non-Proprietary Version - Responses to Requests for Additional Information

Attachment 2

~~11 e- , -*..-

eLECTRIC POWER RESEARCH INSTITUTE NIIL WILMSHUUT Vice Pre.ident and Chief Nuclear Officer April 17, 2012 Document Control Desk Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Attention: Andrew Han

Subject:

Request for Withholding of the following Proprietary Information Included in:

Enclosure 1 7491-1-2S83W9-HEO-1 Peach Bottom RAI Response - Proprietary To Whom It May Concern:

This is a request under 10 C.F.R. §2.390(a)(4) that the U.S. Nuclear Regulatory Commission ("NRC")

withhold from public disclosure the report identified in the enclosed Affidavit consisting of the proprietary information owned by Electric Power Research Institute, Inc. ("EPRI") identified in the attached report.

Proprietary and non-proprietary versions of the Report and the Affidavit in support of this request are enclosed.

EPRI desires to disclose the Proprietary Information in confidence for informational purposes regarding a submittal to the NRC by Exelon Corporation. The Proprietary Information is not to be divulged to anyone outside of the NRC or to any of its contractors, nor shall any copies be made of the Proprietary Information prOVided herein. EPRI welcomes any discussions and/or questions relating to the information enclosed.

If you have any questions about the legal aspects of this request for withholding, please do not hesitate to contact me at (704) 704-595-2732. Questions on the content of the Proprietary Information should be directed to Randy Stark of EPRI at (650) 855-2122.

Sincerely, c: Sheldon Stuchell, NRC (Sheldon.stuchell@nrc.gov)

Together ... Shaping the Future of Electricity 1300 West W.T. Harris Boulevard, Charlotte, NC 28262-8550 USA

704.59.5.2732

Mobile 704.490.2653

nwilmshurstOepri.com

e ~~III!LECTRIC POWER

-I-I~ RESEARCH INSTITUTE AFFIDAVIT RE: Request for Withholding of the Following Proprietary Information Included In::

Enclosure 1 7491-1-2S83W9-HEO-1 Peach Bottom RAI Response - Proprietary I, Neil Wilmshurst, being dUly sworn, depose and state as follows:

I am the Vice President and Chief Nuclear Officer at Electric Power Research Institute, Inc. whose principal office is located at 3420 Hillview Avenue, Palo Alto, California ("EPRI1 and I have been specifically delegated responsibility for the above-listed report that contains EPRI Proprietary Information that is sought under this Affidavit to be withheld "Proprietary Information". I am authorized to apply to the U.S. Nuclear Regulatory Commission ("NRC") for the wHhholding of the Proprietary Information on behalf of EPRI.

EPRI requests that the Proprietary Information be withheld from the public on the following bases:

Withholding Based Upon Privileged And Confidential Trade Secrets Or Commercial Or Financial Information:

a. The Proprietary Information is owned by EPRI and has been held in confidence by EPRI. All entities accepting copies of the Proprietary Information do so subject to written agreements imposing an obligation upon the recipient to maintain the confidentiality of the Proprietary Information. The Proprietary Information is disclosed only to parties who agree, in writing, to preserve the confidentiality thereof.

b. EPRI considers the Proprietary Information contained therein to constitute trade secrets of EPRI. As such, EPRI holds the Information in confidence and disclosure thereof is strictly limited to individuals and entities who have agreed, in writing, to maintain the confidentiality of the Information.

EPRI made a substantial economic investment to develop the Proprietary Information and, by prohibiting public disclosure, EPRI derives an economic benefit in the form of licensing royalties and other additional fees from the confidential nature of the Proprietary Information. If the Proprietary Information were pUblicly available to consultants and/or other businesses providing services in the electric and/or nuclear power industry, they would be able to use the Proprietary Information for their own commercial benefit and profit and without expending the substantial economic resources required of EPRI to develop the Proprietary Information.

c. EPRI's classification of the Proprietary Information as trade secrets is justified by the Uniform Trade Secrets Act which California adopted in 1984 and a version of which has been adopted by over forty states. The California Uniform Trade Secrets Act. California Civil Code §§3426 - 3426.11, defines a "trade secret" as follows:

"'Trade secref means information, including a formula, pattern, compilation, program device, method, technique, or process, that:

(1) Derives independent economic value, actual or potential, from not being generally known to the public or to other persons who can obtain economic value from its disclosure or use; and (2) Is the subject of efforts that are reasonable under the circumstances to maintain its secrecy."

d. The Proprietary Information contained therein are ,not generally known or available to the public. EPRI developed the Information only after making a determination that the Proprietary Information was not available from public sources. EPRI made a substantial investment of both money and employee hours in the development of the Proprietary Information. EPRI was required to devote these resources and effort to derive the Proprietary Information. As a result of such effort and cost, both in terms of dollars spent and dedicated employee time, the Proprietary Information is highly valuable to EPRI.

e. A public disclosure of the Proprietary Information would be highly likely to cause substantial harm to EPRI's competitive position and the ability of EPRI to license the Proprietary Information both domestically and internationally. The Proprietary Information can only be acquired and/or duplicated by others using an equivalent investment of time and effort.

I have. read the foregoing and the matters stated herein are true and correct to the best of my knowledge, information and belief. I make this affidavit under penalty of pe~ury under the laws of the United States of America and under the laws of the State of California.

Executed at 1300 WWT Harris Blvd being the premises and place of business of Electric Power Research Institute, Inc.

(State of North Carolina)

(County of Mecklenburg)

Subscribed ~~~ SW9m 1> (or affirmed) before me on this JJ3Jay of tkJJJ. . 20./6 by

~ ~ , proved to me on the basis of satisbIY evidence to be the person(s) who appeared before me.

Signature ~ ". fl. (Seal)

My Commission Expires A.~ay of IIpil ,20,",

GE-Hitachi Nuclear Energy Americas LLC AFFIDAVIT I, Louis M. Quintana, state as follows:

(1) I am the Program Manager, EHS, GE-Hitachi Nuclear Energy Americas LLC (GEH). I have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.

(2) The information sought to be withheld is contained in GEH letter, 7491-1-2S83W9-HEO-l, Larry Beese (GEH) to Jeremy Searer (Exelon), "GEH Responses to Potential RAls," dated April 4, 2012. The proprietary information in Enclosure 1 entitled, "Peach Bottom RAJ Response-Proprietary," is identified by a dotted underline inside double square brackets.

((Th.i.~ .. ~.~.l}J.t;n.~~.j~ ...'Jn... ~~p:mRI~~:~!J]. In each case, the superscript notation {J} refers to Paragraph (3) of this affidavit that provides the basis for the proprietary determination (3) In making this application for withholding of proprietary information of which it is the owner or licensee, GEH relies upon the exemption from disclosure set forth in the Freedom of Information Act (FOIA), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9. 17(a)(4), and 2.390(a)(4) for trade secrets (Exemption 4). The material for which exemption from disclosure is here sought also qualifies under the narrower definition of trade secret, within the meanings assigned to those tenns for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975 F2d 871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704 F2d 1280 (DC Cir. 1983).

(4) The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. Some examples of categories of information that fit into the definition of proprietary information are:

a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by GEH's competitors without license from GEH constitutes a competitive economic advantage over GEH and/or other companies.

b. Information that, if used by a competitor, would reduce their expenditure of resources or improve their competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product.

c. Information that reveals aspects of past, present, or future GEH customer-funded development plans and programs, that may include potential products of GEH.

d. Information that discloses trade secret and/or potentially patentable subject matter for which it may be desirable to obtain patent protection.

Affidavit for 7491-1-2S83W9-HEO-l Affidavit Page 1 of 3

(5) To address 10 CFR 2.390(b)(4), the information sought to be withheld is being submitted to the NRC in confidence. The information is of a sort customarily held in confidence by GEH, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GEH, not been disclosed publicly, and not been made available in public sources. All disclosures to third parties, including any required transmittals to the NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary and/or confidentiality agreements that provide for maintaining the information in confidence. The initial designation of this information as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure are as set forth in the following paragraphs (6) and (7).

(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, who is the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or who is the person most likely to be subject to the terms under which it was licensed to GEH. Access to such documents within GEH is limited to a "need to know" basis.

(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist, or other equivalent authority for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GEH are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary and/or confidentiality agreements.

(8) The information identified in paragraph (2) above is classified as proprietary because it contains results of an analysis performed by GEH to support the Peach Bottom Pressure and Temperature Limits Report (PTLR) Technical Specification 5.6.7 changes. This analysis is part of the GEH PTLR methodology. Development of the PTLR methodology and the supporting analysis techniques and information, and their application to the design, modification, and processes were achieved at a significant cost to GEH.

The development of the evaluation methodology along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GEH asset.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GEH's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GEH's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.

The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.

Affidavit for 7491-1-2S83W9-HEO-I Affidavit Page 2 of 3

The research, development, engineering. analytical and .NRC review costs comprise a substantial investment of time and money by GEH. The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify. but it clearly is substantial. GEH's competitive advantage will be lost if its competitors are able to use the results of the GEH experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can anive at the same or similar conclusions.

The value of this information to GEH would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall. and deprive GEH of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.

I declare under penalty of perjury that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, infonnation, and belief.

Executed on this 4 th day of April 2012.

Louis M. Quintana.

Program Manager, EHS GE-Hitachi. Nuclear Energy Americas LLC 3901 Castle Hayne Rd.

Wilmington, NC 28401 Louis.Quintana@ ge.com Affidavit for 7491-1-2S83W9-HEO-l Affidavit Page 3 of 3

7491-1-2S83W9-HEO-l GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 2 of 13 GGNS RAI #4 Do the PT limit curves include a hydrostatic pressure adjustment for the column of water in a full RPV? If so, provide the pressure head used in the PT limit curve analysis.

Response

Yes, the pressure head for PBAPS is 24 psig. This is determined using the height of the vessel and the elevation of the bottom of active fuel. Similarly, the full vessel pressure head is 30 psig.

This value and the equation used can be found in Development of Reactor Pressure Vessel Pressure-Temperature Curves, NEDC-33178P-A, Revision 1, Sections 4.3.2.1.1 and 4.3.2.2.2, respectively.

7491-1-2S83W9-HEO-l GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 3 of 13 GGNS RAI #5 Address inconsistencies between the statement that "the PT curves are beltline (A1224-1 plate) limited above 1330 psig for Curve A for 35 EFPY..." and the NRC staff determination that the PT curves are beltline (A1224-1 plate) limited "'1360 psig from data in Table 1 of GNRO-2010/00056.

Response

This RAI is not applicable to PBAPS as it addresses a plant-specific GGNS statement.

7491-1-2S83W9-HEO-I GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 4 of 13 GGNS RAI #6 Provide the surveillance data and the analysis of the surveillance data used to determine ART from Reference 6.3 (BWRVIP-135, Revision 1 "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 1 provides the surveillance data considered in determining the chemistry and any adjusted Chemistry Factors' (CF) for the beltline materials.

Excerpt from BWRVIP-135, Revision 1 (used by permission)

For PBAPS Unit 2, the Integrated Surveillance Program (ISP) representative plate, heat

[ ], is not the target plate, but is a plate heat in the beltline region. This heat was contained in one (1) PBAPS Unit 2 capsule that has been tested and analyzed. Data was obtained from two (2) specimens from the capsule and one data set from the plant-specific Certified Material Test Report (CMTR). The resultant chemistry is [ ] Cu and [ ] Ni.

The CF from Regulatory Guide 1.99, Revision 2 (RG1.99) is 65°F. No fitted CF has been determined as there has only been one (1) capsule tested. Therefore, the Adjusted Reference Temperature (ART) table evaluated the ISP plate material using the RG1.99 CF. This material was considered in determining the limiting ART for the PT curves; however, this is not the limiting material.

Excerpt from BWRVIP-135, Revision 1 (used by permission)

7491-1-2S83W9-HEO-l GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by U[ ]U Page 5 of 13 For PBAPS Unit 2, the ISP representative weld, heat [ ], is not the target weld. This heat was contained in one (1) PBAPS Unit 2 capsule that has been tested and analyzed. Data was obtained from two (2) specimens from the capsule. The resultant chemistry is [ ] Cu and

[ ] Ni. The CF from RG1.99 is 84.2°F. No fitted CF has been determined as there has only been one (1) capsule tested. Therefore, the ART table evaluated the ISP weld material using the RG1.99 CF. This material was not considered in determining the limiting ART for the PT curves.

Excerpt from BWRVIP-135, Revision 1 (used by permission)

For PBAPS Unit 3, the ISP representative plate, heat [ ], is not the target plate. This heat was contained in two (2) Duane Arnold capsules that have been tested and analyzed. Data was obtained from five (5) specimens from the capsules and one (1) data set from the plant-specific Certified Material Test Report (CMTR). The resultant chemistry is [ ] Cu and [ ] Ni.

The CF from RG1.99 is 111.25°F; the fitted CF is 148.71°F. The fitted CF for the plate material is not applicable for the PBAPS Unit 3 ART evaluation because the ISP plate heat, [ ], is not the target vessel plate. Therefore, the ART table evaluated the ISP plate material using the RG1.99 CF. This material was not considered in determining the limiting ART for the PT curves.

7491-1-2S83W9-HEO-I GEH Proprietary Infonnation- Class III (Confidential)

EPRI Non-Proprietary Infonnation In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 6 of 13 Excerpt from BWRVIP-135, Revision 1 (used by permission)

For PBAPS Unit 3, the ISP representative weld, heat [ ], is not the target weld. This heat was contained in one (1) River Bend and two (2) Supplemental Surveillance Program (SSP) capsules that have been tested and analyzed. Data was obtained from three (3) specimens from the capsules. The resultant chemistry is [ ] Cu and [ ] Ni. The CF from RG1.99 is 82°F; the fitted CF is 116.9°F. An adjusted CF for the weld material is not applicable for the PBAPS Unit 3 ART evaluation because the ISP weld heat, [ ], is not the target vessel weld.

Therefore, the ART table evaluated the ISP weld material using the RG1.99 CF. This material was not considered in determining the limiting ART for the PT curves.

Excerpt from BWRVIP-135, Revision 1 (used by permission)

7491-1-2S83W9-HEO-l GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 7 of 13 GGNS RAI #7 Provide additional detail for the non-beltline analysis conducted in the following areas in order for the NRC staff to complete independent verification of the proposed PT limits:

a. Identify limiting materials for the Reference Temperature for Nil Ductility Transition (RTNOT) values used to shift the generic Bottom Head and Upper Vessel PT curves when applying NEDC-33178P-A.

b. The NRC staff identified a limiting RTNOT of 10°F for the Bottom Head Torus Plates, while GGNS assumed a RTNOT of 24.6°F for the Bottom Head Curve B. Support all RTNOT values reported by providing details of any plant-specific analysis conducted.

c. Explain minor differences in assumed RTNOT values for the Bottom Head. Specifically Curves A and C assume a limiting RTNOT of 19°F, while Curve B assumes a limiting RTNOT of 24.6°F.

d. Which region of the RPV is limiting for Curve C < 312 psig.

Response

In order to determine how much to shift the Pressure-Temperature (PT) curves, an evaluation is performed using Tables 4-4a and 4-Sa from NEDC-33178P-A. These tables define the required Temperature minus Reference Temperature of Nil Ductility Transition (T-RTNOT) that is used to adjust the non-shifted curves. Each component listed in these tables is evaluated using the plant-specific initial RTNOT for each component. The required temperature is then determined by adding the T-RTNOT to the plant-specific RTNOT, thereby resulting in the required T for the curve. As the upper vessel curve is initially based on the non-shifted feedwater (FW) nozzle T-RTNOT, all resulting T values are compared to the FW nozzle T. The difference between the maximum T and the FW nozzle T-RTNOT is used to shift the upper vessel curve. The same method is applied for the Control Rod Drive (CRD) curve. In this manner, it is assured that each curve bounds the maximum discontinuity that is represented.

For the PBAPS Unit 2 upper vessel curve, the maximum T value from the method described above is (( )). The initial required T-RTNOT for the ((

)); this is then adjusted by the PBAPS Unit 2-specific maximum ((

)), resulting in (( )). Comparing this to the next limiting value, the (( )), the required T-RTNOT is (( )), which is added to the (( )). It is seen that the

7491-1-2S83W9-HEO-I GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 8 of 13 resulting T required for the (( )). As (( )) is limiting, the PBAPS Unit 2 upper vessel curve is based on an RTNOT of (( )).

As noted above, this calculation was performed for each component shown in Table 4-4a; only the limiting case is presented here.

For the PBAPS Unit 2 bottom head or CRD ((

)), respectively), the maximum T value from the method described above is ((

)). The required T-RTNOT for the ((

)); this is adjusted by the PBAPS Unit 2-specific maximum

(( )), resulting in (( )). Comparing this to the CRD values, the required T-RTNOT is (( )), which is added to the ((

)). It is seen that the resulting T required for the bottom head is

(( )). As (( )) than (( )), the PBAPS Unit 2 bottom head (CRD) curve is based on an (( )). As noted above, this calculation was performed for each component shown in Table 4-5a; only the limiting case is presented here.

Appendix H of NEDC-33178P-A contains the details of an analysis performed to determine the baseline requirement (non-shifted) for the ((

)). It can be seen in Section H.5 of Appendix H that the stresses developed in this finite element analysis demonstrated that the ((

)),

resulting in a baseline non-shifted required T-RTNOT of (( )).

Therefore, considering the determination of the required shift from the paragraph above for ((

)), calculations for all components listed in Table 4-5a were compared to the CRD T, which is (( )) (where

(( )) materials). Therefore, the shift for the bottom head (( )).

For Curve C, the upper vessel and beltline regions are bounding at pressures up to 40 psig. For pressures between 40 psig and 312.5 psig, the upper vessel is bounding; this is true for both 32 and 54 EFPY.

For the PBAPS Unit 3 upper vessel curve, the maximum T value from the method described above is (( )). The initial required T-RTNOT for the

(( )); this is then adjusted by the PBAPS Unit 3-specific maximum (( )), resulting in (( )). Comparing this to the (( )), the required T-RTNOT is (( )), which is added to the ((

7491-1-2S83W9-HEO-I GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 9 of 13

)). It is seen that the resulting T required for the ((

)) is (( )). As (( )) is limiting, the PBAPS Unit 3 upper vessel curve is based on an RTNOT of (( )). As noted above, this calculation was performed for each component shown in Table 4-4a; only the limiting case is presented here.

For the PBAPS Unit 3 bottom head or CRD ((

)), respectively), the maximum T value from the method described above is ((

)). The required T-RTNOT for the (( )); this is adjusted by the PBAPS Unit 3-specific maximum (( )), resulting in ((

)). Comparing this to the next limiting value, the ((

)), the required T-RTNOT is (( )), which is added to the ((

)). It is seen that the resulting T required for the bottom head is

(( )). As (( )) than (( )), the PBAPS Unit 3 bottom head (CRD) curve is based on an (( )). As noted above, this calculation was performed for each component shown in Table 4-Sa; only the limiting case is presented here.

Appendix H of NEDC-33178P-A contains the details of an analysis performed to determine the baseline requirement (non-shifted) for the ((

)). It can be seen in Section H.S of Appendix H that the stresses developed in this finite element analysis demonstrated that the ((

)), resulting in a baseline non-shifted required T-RTNOT of (( )). Therefore, considering the determination of the required shift from the paragraph above for ((

)), calculations for all components listed in Table 4-5a were compared to the CRD T, which is (( )) (where ((

)) materials). Therefore, the shift for the bottom head ((

)).

For Curve C, the upper vessel and beltline regions are bounding at pressures up to 40 psig. For pressures between 40 psig and 312.5 psig, the upper vessel is bounding; this is true for both 32 and 54 EFPY.

7491-1-2S83W9-HEO-l GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 10 of 13 GGNS RAI #8 identifies nozzle N12 as a beltline water level instrument nozzle and notes that an evaluation was conducted using the limiting material properties for the adjoining shell ring, which appears to be appropriate as nozzle N12 is identified as austenitic. Provide details of this evaluation which demonstrates that the drill hole for the beltline water level instrument nozzle is not limiting.

Response

The PBAPS Unit 2 and Unit 3 N12 nozzle is fabricated from Alloy 600 material. Appendix J of NEDC-33178P-A provides detailed results of an analysis performed for the water level instrumentation nozzle that provides the required stresses for the drill hole in the shell plate.

These stresses were used to generate a specific curve applicable for the water level instrumentation nozzle to assure that this location is bounded in the PT curves. For PBAPS Unit 2 and Unit 3, the water level instrumentation nozzles are ((

)) for 32 and 54 EFPY.

7491-1-2S83W9-HEO-l GEH Proprietary Information- Class III (Confidential)

EPRI Non-Proprietary Information In Accordance with 10 CFR 2.390 As identified by "[ ]"

Page 11 of 13 GGNS RAI #9 Provide details on any plant-specific feedwater nozzle evaluation conducted in support of the proposed PT limits or explain why plant-specific evaluation was not required.

Response

An evaluation was performed for the feedwater nozzle as described in Section 4.3.2.1.3 of NEDC-33178P-A. This evaluation confirmed that the feedwater discontinuity bounds the other discontinuities defined in Table 4-4a of NEDC-33178P-A. The first part of the evaluation is as described in the response to RAI #7, where it is assured that the limiting component that is represented by the upper vessel nozzle curve is bounded. A second evaluation was performed using the PBAPS-specific feedwater nozzle dimensions; this evaluation is shown below to demonstrate that the (( )) curve is applicable to PBAPS Unit 2:

Vessel radius to base metal, Rv ((

Vessel thickness, tv Vessel pressure, Pv Pressure stress PR/t = =(( ))

Dead Weight + Thermal Restricted Free End stress Total Stress =(( )) ))

The factor F (a/r n ) from Figure A5-1 of "PVRC Recommendations on Toughness Requirements for Ferritic Materials", Welding Research Council Bulletin 175, August 1972 (WRC-175) is determined where:

a = % (t n 2 + tv2) ~ ((

t n = thickness of nozzle

=

tv thickness of vessel

r n apparent radius of nozzle rl + O.29*rc

=

rj actual inner radius of nozzle

=

rc nozzle radius (nozzle corner radius) ))

Therefore, a/r n =(( )). The value F (a/r n ), taken from Figure A5-1 of WRC-175 for an (( )). Including the safety factor of 1.5, the, stress intensity factor, K is 1.5 cr (1ta)1/2

F(a/r n ):

Nominal K, =1.5 * (( ))

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Page 12 of 13 A detailed upper vessel example calculation for core not critical conditions is provided in Section 4.3.2.1.4 of NEDC-33178P-A. Section 4.3.2.1.3 of NEDC-33178P-A, presents the

(( )) FW nozzle evaluation upon which the baseline non-shifted upper vessel PT curve is based. It can be seen that the nominal K, from this evaluation is

(( )). Therefore, it has been shown that the nominal K, for the PBAPS Unit 2-specific FW nozzle is equal to the (( )) K demonstrating applicability of the FW nozzle curve for PBAPS Unit 2.

The same evaluation is shown below to demonstrate that the (( )) curve is applicable to PBAPS Unit 3:

Vessel radius to base metal, Rv ((

Vessel thickness, tv Vessel pressure, Pv Pressure stress = PR/t = (( ))

Dead Weight + Thermal Restricted Free End stress Total Stress = (( )) ))

The factor F (a/r n) from Figure A5-1 of "PVRC Recommendations on Toughness Requirements for Ferritic Materialsl l , Welding Research Council Bulletin 175, August 1972 (WRC-175) is determined where:

a = ~ (t n2 + tv 2 ) % ((

t n = thickness of nozzle tv = thickness of vessel r n = apparent radius of nozzle = ri+ O.29*rc rj = actual inner radius of nozzle r c = nozzle radius (nozzle corner radius) ))

Therefore, air n =(( )). The value F (a/r n ), taken from Figure A5-1 of WRC-175 for an (( )). Including the safety factor of 1.5, the stress intensity factor, K" is 1.5 0' (1ta}1/2

F(a/r n):

Nominal K, = 1.5 * (( ))

A detailed upper vessel example calculation for core not critical conditions is provided in Section 4.3.2.1.4 of NEDC-33178P-A. Section 4.3.2.1.3 of NEDC-33178P-A, presents the

(( )) FW nozzle evaluation upon which the baseline non-shifted upper vessel PT curve is based. It can be seen that the nominal K, from this evaluation is

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Page 13 of 13

(( )). Therefore, it has been shown that the nominal K, for the PBAPS Unit 3-specific FW nozzle is bounded by the (( )) K demonstrating applicability of the FW nozzle curve for PBAPS Unit 3.

v t e Letter Sequence Request
TAC:ME8535, Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR, Revise Topical Report References in ITS 5.6.5, Colr, Relocation of Ltop Enabletemperature and PORV Lift Setting to the PTLR - CE NPSD-683 (Approved, Closed)
Initiation Request Acceptance Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Questions 22 August 2012 Answers 15 October 2012 Results Approval Other:
MONTHYEAR2012-05-29 [Table View]

ML121230354

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Subject:

SUBJECT:

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

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