ML13058A059

Licesne Amendment Request to Update Pressure-Temperature Limit Curves No. 2012-10

ML13058A059
Person / Time
Site:	Oconee
Issue date:	02/22/2013
From:	Gillespie T Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13058A059 (45)

Text

Duke Duker T. PRESTON GILLESPIE, Jr.

Vice President t'-VEnergy Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Hwy.

Seneca, SC 29672 864-873-4478 864-873-4208 fax 10 CFR 50.90 T.Gillespie@duke-energy.corn February 22, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Station (ONS), Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10 In accordance with 10 CFR 50.90, Duke Energy Carolinas, LLC (Duke Energy) proposes to amend Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55 for ONS Units 1, 2, and 3. This LAR proposes to replace the current ONS Units 1, 2, and 3 pressure-temperature (P-T) limit curves in Technical Specification (TS) 3.4.3 with new P-T limit curves applicable to 54 effective full power years (EFPY). Also, changes are proposed to the operational requirements for unit heatup and cooldown in TS Tables 3.4.3-1 and 3.4.3-2. The low temperature overpressure protection (LTOP) requirements, which are based on P-T limits, will also be applicable to 54 EFPY. No changes are required to LTOP requirements.

The P-T limits for ONS Units 1, 2, and 3 reactor pressure vessels were developed in accordance with the requirements of 10 CFR 50, Appendix G, using the analytical methods and flaw acceptance criteria of ASME Code Section Xl, Appendix G and AREVA Topical Report BAW-10046A, Revision 2. The reference temperature for nil-ductility transition (RTNDT) values of the reactor vessel beltline welds (Linde 80 welds) were determined using methods provided in Topical Report BAW-2308, "Initial RTNDT of Linde 80 Weld Materials," Revisions 1-A and 2-A, rather than the methodology described within Topical Report BAW-1 0046A, Revision 2, which was used to evaluate the other beltline components. Exemptions from 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," and 10 CFR 50, Appendix G, "Fracture Toughness Requirements" were required to allow use of the alternate initial RTNDT values provided in BAW-2308, Revisions 1-A and 2-A. The NRC approved exemptions for ONS from these requirements by letter dated April 26, 2012. The projected fluence values at 54 EFPY are based on Topical Report BAW-2241 P-A, Revision 2, which adheres to the guidance contained in NRC Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."

An evaluation of the proposed change is provided in the Enclosure 1. A No Significant Hazards Consideration Evaluation and the Environmental Impact Analysis are also included in the Enclosure. The marked up and revised TS pages are provided in Attachments 1 and 2, respectively. Enclosure 2, AREVA Topical Report ANP-3127, Revision 1, "Oconee Nuclear www. duke-energy. corn

Nuclear Regulatory Commission February 22, 2013 Page 2 Station Units 1, 2, & 3 Pressure-Temperature Limits at 54 EFPY, January 2013," provides the technical basis for the proposed change.

In accordance with Duke Energy administrative procedures and the Quality Assurance Program Topical Report, the proposed TS change has been reviewed and approved by the Plant Operations Review Committee. Additionally, a copy of this LAR is being sent to the State of South Carolina in accordance with 10 CFR 50.91 requirements.

The current 33 EFPY P-T limit curves are projected to expire in March 2014. Duke Energy requests approval of the proposed LAR by January 31, 2014, effective immediately on issuance with implementation within 60 days. Duke Energy will also update applicable sections of the ONS Updated Final Safety Analysis Report (UFSAR), as necessary, and submit these per 10 CFR 50.71(e). There are no new commitments being made as a result of this proposed.

change.

If there are any additional questions, please contact Boyd Shingleton, ONS Regulatory Affairs, at (864) 873-4716.

I declare under penalty of perjury.that the foregoing is true and correct. Executed on February 22, 2013.

Sincerely, T. Preston Gillespie, Jr., Vice President Oconee Nuclear Station

Enclosures:

1. Evaluation of Proposed Change

2. AREVA Topical Report ANP-3127, Revision 1, "Oconee Nuclear Station Units 1, 2, & 3 Pressure-Temperature Limits at 54 EFPY, January 2013 Attachments:

1. Marked up TS Pages

2. Revised TS Pages

Nuclear Regulatory Commission February 22, 2013 Page 3 cc w/Enclosures and Attachments:

Mr. Victor McCree, Regional Administrator U. S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Boska, Project Manager (by electronic mail only)

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852 Mr. Ed Crowe Senior Resident Inspector Oconee Nuclear Site Ms. Susan E. Jenkins, Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201

License Amendment Request No. 2012-10 February 22, 2013 ENCLOSURE 1 EVALUATION OF PROPOSED CHANGE

License Enclosure - Evaluation of Proposed Change Amendment Request No. 2012-10 February 22, 2013

Subject:

License Amendment Request to Update Pressure-Temperature Limit Curves License Amendment Request (LAR) No. 2012-10

1.

SUMMARY

DESCRIPTION

2. DETAILED DESCRIPTION 2.1 Background 2.2 Technical Specification Change Description

3. TECHNICAL EVALUATION

4. REGULATORY EVALUATION 4.1 Significant Hazards Consideration 4.2 Applicable Regulatory Requirements/Criteria 4.3 Precedence 4.4 Conclusions

5. ENVIRONMENTAL CONSIDERATION

6. REFERENCES

Enclosure 1 - Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2013 Page 1 1.0

SUMMARY

DESCRIPTION This License Amendment Request (LAR) proposes to replace the current Oconee Nuclear Station (ONS) Units 1, 2, and 3 pressure/temperature (P-T) limit curves in Technical Specification (TS) 3.4.3 with new P-T limit curves applicable to 54 effective full power years (EFPY). Also, changes are proposed to the operational requirements for unit heatup and cooldown in TS Tables 3.4.3-1 and 3.4.3-2. The low temperature overpressure protection (LTOP) requirements, which are based on P-T limits, will also be applicable to 54 EFPY. No changes are required to LTOP requirements.

The P-T limits for ONS Units 1, 2, and 3 reactor pressure vessels were developed in accordance with the requirements of 10 CFR 50, Appendix G, using the analytical methods and flaw acceptance criteria of ASME Code Section XI, Appendix G and AREVA Topical Report BAW-1 0046A, Revision 2. The reference temperature for nil-ductility transition (RTNDT) values of the reactor vessel beltline welds (Linde 80 welds) were determined using methods provided in Topical Report BAW-2308, "Initial RTNDT of Linde 80 Weld Materials," Revisions 1-A and 2-A, rather than the methodology described within Topical Report BAW-1 0046A, Revision 2, which was used to evaluate the other beltline components. Exemptions from 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," and 10 CFR 50, Appendix G, "Fracture Toughness Requirements" were required to allow use of the alternate initial RTNDT values provided in BAW-2308, Revisions 1-A and 2-A. The NRC approved exemptions for ONS from these requirements by letter dated April 26, 2012. The projected fluence values at 54 EFPY are based on Topical Report BAW-2241 P-A, Revision 2, which adheres to the guidance contained in NRC Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."

.An evaluation of the proposed change is provided in Section 3.0. The marked up and revised TS pages are provided in Attachments 1 and 2, respectively. Enclosure 2, AREVA Topical Report ANP-3127, "Oconee Nuclear Station Units 1, 2, & 3 Pressure-Temperature Limits at 54 EFPY, January 2013," provides the technical basis for the proposed change.

The current 33 EFPY P-T limit curves are projected to expire in March 2014. Duke Energy requests approval of the proposed LAR by January 31, 2014, effective immediately on issuance with implementation within 60 days. There are no new commitments being made as a result of this proposed change.

2.0 DETAILED DESCRIPTION 2.1 Background The proposed amendment extends the Reactor Coolant Pressure Boundary (RCPB) Technical Specification Pressure-Temperature (P-T) operating limits of Oconee Nuclear Station Units 1, 2, and 3 (ONS-1, ONS-2 and ONS-3) from 33 EFPY to 54 EFPY. The proposed P-T limits are established in accordance with the requirements of 10 CFR Part 50, Appendix G. These P-T limits are generated for normal operation heatup, normal operation cooldown, inservice leak and hydrostatic (ISLH) test conditions, and reactor core operations. These limits are expressed in the form of curves of allowable pressure versus temperature. The uncorrected P-T limits for the three

- Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2012 Page 2 ONS units were determined for 54 effective full power years (EFPY) of operation. Pressure correction factors were determined between the pressure sensor locations (pressure tap in the Decay Heat Removal System (DHRS) drop line and two pressure taps in the Reactor Coolant System (RCS) hot leg) and various regions of the reactor vessel. The TS pressure-temperature operating limits applicable to ONS-1, ONS-2, and ONS-3 are developed for 54 EFPY of reactor operation. In addition, the minimum temperature for core criticality is determined to satisfy the regulatory requirements of 10 CFR Part 50, Appendix G.

The ability of the reactor pressure vessel to resist fracture is the primary factor in ensuring the safety of the primary system in light water-cooled reactors. The three areas of the reactor pressure vessel addressed in the present report are the beltline shell region, the reactor coolant nozzles, and the closure head flange region.

A method for guarding against brittle fracture in reactor pressure vessels is described in Appendix G of the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components."

This method utilizes fracture mechanics concepts and the reference temperature for nil-ductility transition (RTNDT). The RTNDT is defined as the greater of the drop weight nil-ductility transition temperature (per American Society for Testing and Materials (ASTM) E208) or the temperature at which the material exhibits 50 ft-lbs absorbed energy and 35 mils lateral expansion minus 601F.

The RTNDT of a given material is used to index that material to a reference stress intensity factor curve (K1c). The Kjc curve appears in Appendix G of ASME Code Section XI. When a given material is indexed to the K1, curve, allowable stress intensity factors can be obtained for this material as a function of temperature. Plant operating limits can then be determined using these allowable stress intensity factors.

The beltline region of the reactor vessel is the most highly exposed to neutron irradiation. The general effects of fast neutron irradiation on the mechanical properties of low-alloy ferritic steels such as SA-302, Grade B, modified and SA-508, Class 2 forging material used in the fabrication of the ONS Units reactor vessels and inlet and outlet nozzles, are well characterized and documented in the literature. The effects of irradiation on these steels include an increase in the yield and ultimate strengths and a decrease in ductility. The most significant effect, however, is an increase in the temperature associated with the transition from brittle to ductile fracture and a reduction in the Charpy upper-shelf energy value.

Pressure-temperature limits for the ONS Units reactor vessels are developed in accordance with the requirements of 10 CFR Part 50, Appendix G, utilizing the analytical methods and flaw acceptance criteria of AREVA Topical Report BAW-10046A, Revision 2, "Methods of Compliance with Fracture Toughness and Operational Requirements of 10CFR Appendix G," dated June 1986, and ASME Code Section XI, Appendix G.

The ONS-1 reactor vessel contains both axially and circumferentially oriented welds. Therefore, the P-T limits for ONS-1 are based on the postulation of both axial and circumferential flaws in the most limiting axial and circumferential welds. Since ONS-2 and ONS-3 reactor vessels do not contain any axial welds in their beltline regions, axial flaws are postulated in the most limiting forging materials of these reactor vessels.

- Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2012 Page 3 2.2 Technical Specification Change Description The new proposed P-T limits will be applicable to 54 EFPY and will ensure that all RCS components will be able to withstand the effects of transient loads due to system temperature and pressure changes without their functions or performance being impaired. These loads are introduced by normal load transients, reactor trips, and startup and shutdown operations.

The Low Temperature Overpressurization Protection (LTOP) pressure limit (adjusted for location and instrument uncertainty) at 54 EFPY that bounds all three ONS Units is 540 psig (ONS-1).

The 54 EFPY LTOP limiting pressure remains above the current Pressurizer Power-Operated Relief Valve (PORV) setpoint of 535 psig. Therefore, the current PORV low-pressure setpoint (535 psig) remains acceptable for plant operation to 54 EFPY for all three ONS units.

The minimum 54 EFPY LTOP enable temperature that bounds all three ONS Units with instrument uncertainty is 276.81F (ONS-3). This value is lower than the current operationally imposed LTOP enable temperature of 3251F at 33 EFPY. Therefore, the current operationally imposed LTOP temperature of 3250 F remains acceptable for plant operation to 54 EFPY for all three ONS units.

The proposed change is as follows:

TS Limiting Condition for Operation (LCO) 3.4.3 currently provides the P-T limits for RCS Normal Operational Heatup Limitations, RCS Normal Operational Cooldown Limitations, and RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations applicable to the first 33 EFPY in Figures 3.4.3-1, 3.4.3-2 & 3.4.3-3 respectively for ONS-1, in Figures 3.4.3-4, 3.4.3-5, & 3.4.3-6 respectively for ONS-2, and in Figures 3.4.3-7, 3.4.3-8, & 3.4.3-9 respectively for ONS-3. The proposed change would replace the existing P-T limits for 33 EFPY with P-T limits for 54 EFPY.

Also, changes to the operational requirements for unit heatup and cooldown in TS Tables 3.4.3-1 and 3.4.3-2 are proposed. These changes are supported by the new 54 EFPY P-T limits. The proposed changes are depicted in the TS markup and retype provided in Attachments 1 and 2.

3.0 TECHNICAL EVALUATION

The current P-T limit curves will expire at 33 EFPY. AREVA NP was contracted to update the P-T Limit Curves and LTOP analysis to 54 EFPY based on current ASME methods and regulatory requirements. The new P-T limit curves have been adjusted based on pressure differential between point of system pressure measurement and the point in the reactor vessel that establishes the controlling unadjusted pressure limits. The P-T limit curves do not include margins for instrument error.

The basis for the proposed change is provided in AREVA Topical Report ANP-3127, Revision 1, "Oconee Nuclear Station Units 1, 2, & 3 Pressure-Temperature Limits at 54 EFPY," January 2013. The Topical Report, which is provided in Enclosure 2, provides the methodology for determining the new P-T limits, provides an evaluation of the adjusted reference temperatures for each ONS unit, describes the essential analytical parameters used in the preparation of ONS-1, 2, and 3 P-T limits, and provides the technical basis for the P-T limits. The P-T limits were developed in accordance with the requirements of 10 CFR 50, Appendix G, using the analytical methods and flaw acceptance criteria of ASME Code Section Xl, Appendix G and AREVA Topical

- Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2012 Page 4 Report BAW-10046A, Revision 2. The reference temperature for nil-ductility transition (RTNDT) values of the reactor vessel beltline welds (Linde 80 welds) were determined using methods provided in Topical Report BAW-2308, "Initial RTNDTmofLinde 80 Weld Materials," Revisions 1-A and 2-A, rather than the methodology described within Topical Report BAW-1 0046A, Revision 2, which was used to evaluate the other beltline components. Exemptions from 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events,"

and 10 CFR 50, Appendix G, "Fracture Toughness Requirements" were required to allow use of the alternate initial RTNDT values provided in BAW-2308, Revisions 1-A and 2-A. The NRC approved exemptions for ONS from these requirements by letter dated April 26, 2012. The projected fluence values at 54 EFPY are based on Topical Report BAW-2241 P-A, Revision 2, which adheres to the guidance contained in NRC Regulatory Guide 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence."

4.0 REGULATORY EVALUATION

4.1 Significant Hazards Consideration Duke Energy Carolinas, LLC, 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) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed amendment replaces the current Oconee Nuclear Station (ONS)

Units 1, 2, and 3 pressure/temperature'(P-T) limit curves applicable to 33 effective full power years (EFPY) in Technical Specification (TS) 3.4.3 with new P-T limit curves applicable to 54 EFPY. The proposed changes also revise the Reactor Coolant System heatup and cooldown rates and allowable reactor coolant pump combinations of TS Tables 3.4.3-1 and 3.4.3-2. The pressure-temperature (P-T) limit curves in the TSs were conservatively generated in accordance with fracture toughness requirements of ASME Code Section Xl, Appendix G, and the minimum pressure and temperature requirements as listed in Table 1 of 10 CFR 50, Appendix G. The proposed changes do not impact the capability of the reactor coolant pressure boundary (i.e., no change in operating pressure, materials, seismic loading, etc.).

Therefore, the proposed changes do not increase the potential for the occurrence of a loss of coolant accident (LOCA). The changes do not modify the reactor coolant system pressure boundary, nor make any physical changes to the facility design, material, or construction standards. The probability of any design basis accident (DBA) is not affected by this change, nor are the consequences of any DBA affected by this change. The proposed P-T limits, heatup and cooldown rates and allowable operating reactor coolant pump combinations are not considered to be an initiator or contributor to any accident analysis addressed in the ONS Updated Final Safety Analyses Report (UFSAR).

The proposed changes will not impact assumptions and conditions previously used in the radiological consequence evaluations nor affect the mitigation of these consequences due to an accident described in the UFSAR. Also, the proposed

- Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2012 Page 5 changes will not impact a plant system such that previously analyzed SSCs might be more likely to fail. The initiating conditions and assumptions for accidents described in the UFSAR r6main as analyzed.

Therefore, the probability or consequences of an accident previously evaluated is not significantly increased.

2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

No. The requirements for P-T limit curves have been in place since the beginning of plant operation. The revised curves are based on a later edition to Section Xl of the ASME Code that incorporates current industry standards for P-T curves. The revised curves are based on reactor vessel irradiation damage predictions using Regulatory Guide 1.99 methodology. No new failure modes are identified nor are any SSCs required to be operated outside the design bases. Therefore, the possibility of a new or different kind of accident from any kind of accident previously evaluated is not created.

3) Does the proposed amendment involve a significant reduction in a margin of safety?

No. The proposed P-T curves continue to maintain the safety margins of 10 CFR 50, Appendix G, by defining the limits of operation which prevent non-ductile failure of the reactor pressure vessel. Analyses have demonstrated that the fracture toughness requirements are satisfied and that conservative operating restrictions are maintained for the purpose of low temperature overpressure protection. The P-T limit curves provide assurance that the RCS pressure boundary will behave in a ductile manner and that the probability of a rapidly propagating fracture is minimized. Therefore, this request does not involve a significant reduction in a margin of safety.

4.2 Applicable Regulatory Requirements/Criteria 10 CFR 50, Appendix G, "FractureToughness Requirements" 10 CFR 50, Appendix G requires P-T limits and minimum temperature requirements be established for the reactor pressure vessel. These limits are defined by the various plant operating conditions, whether or not fuel is in the vessel, whether or not the core is critical, and the reactor vessel pressure. The operating conditions include, but are not limited to, hydrostatic pressure and leak testing and normal operation including anticipated operational occurrences. The regulation also requires the P-T limits be at least as conservative as the limits obtained by following the methods of analysis and margins contained in the ASME Code, Section Xl, Appendix G.

- Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2012 Page 6 Regulatory Guide 1.99, Revision 2, "RadiationEmbrittlement of Reactor Vessel Materials" Regulatory Guide (RG) 1.99, Revision 2, contains methodologies for determining the change in RTNDT resulting from neutron radiation. The use of the RG provides an acceptable means of ensuring the requirements of 10 CFR 50, Appendix G are satisfied.

The RG also indicates that other methodologies could be used for complying with the specified portions of the regulation.

American Society of MechanicalEngineers Boiler and Pressure Vessel Code, Section Xl, Appendix G, "FractureToughness Criteria for ProtectionAgainst Failure" As indicated in the description for 10 CFR 50, Appendix G, above, the proposed changes to the Technical Specifications and Operating License meet the requirements of the ASME Code, Section Xl, Appendix G as modified by the NRC-accepted ASME Code Cases N-588 and N-640.

4.3 Precedence

1. First Energy Nuclear Operating Company letter to Nuclear Regulatory Commission dated April 15, 2009, "License Amendment Request to Incorporate the Use of Alternate Methodology for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50 Appendix G."

2. First Energy Nuclear Operating Company letter to Nuclear Regulatory Commission dated December 18, 2009, "Supplemental Information Related to the License Amendment Request to Incorporate the Use of Alternate Methodology for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 CFR 50.61 and 10 CFR 50 Appendix G."

3. Nuclear Regulatory Commission Letter to First Energy Nuclear Operating Company dated January 18, 2011, "DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE: REQUEST TO INCORPORATE THE USE OF ALTERNATIVE METHODOLOGIES FOR THE DEVELOPMENT OF REACTOR PRESSURE VESSEL PRESSURE-TEMPERATURE LIMIT CURVES (TAC NO. ME1127)."

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 Commission's regulations, and (3) the issuance of the amendment will not be adverse to the common defense and security or to the health and safety of the public.

- Evaluation of Proposed Change License Amendment Request No. 2012-10 February 22, 2012 Page 7

5.0 ENVIRONMENTAL CONSIDERATION

Duke Energy Carolinas, LLC, has evaluated this license amendment request against the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. Duke Energy Carolinas, LLC has determined that this license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9). This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50 that changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria:

(i) The amendment involves no significant hazards consideration.

As demonstrated in Section 4.1, the proposed Technical Specification change does not involve a significant hazards consideration.

(ii) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.

This LAR will not change the types or amounts of any effluents that may be released offsite.

(iii) There is no significant increase in individual or cumulative occupational radiation exposure.

This LAR will not increase the individual or cumulative occupational radiation exposure.

6.0 REFERENCES

1. AREVA Topical Report ANP-3127, Revision, "Oconee Nuclear Station Units 1, 2, &

3 Pressure-Temperature Limits at 54 EFPY," January 2013.

2. AREVA Topical Report BAW-1 0046A, Rev. 2, "Methods of Compliance with Fracture Toughness and Operational Requirements of 1 OCFR Appendix G," dated June 1986.

3. AREVA Document 43-2308-002, "Initial RT NDT of Linde 80 Weld Materials,"

(BAW-2308, Revision 1-A).

4. AREVA Document 43-2308-004, "Initial RT NDT of Linde 80 Weld Materials,"

(BAW-2308, Revision 2-A).

5. AREVA Topical Report BAW-2241 P-A, Revision 2, "Fluence and Uncertainty Methodologies," 2006.

License Amendment Request No. 2012-10 February 22, 2012 ATTACHMENT 1 TECHNICAL SPECIFICATION MARK UPS

RCS P/T Limits 3.4.3 Table 3.4.3-1 (page 1 of 1)

OpeatinalRequirements for Unit Heatu, :530OF in any 1/2 hr period CONTRIN R TMPE AUR~a MXI ALLOWED PUMP CONTRANT Re EMPRAUREa) HEATUP RT/COMBINATION RC Temperature(a) T <PROF 270-F/ NA T Ž __!JJ 1-00o,-hf NA 100 0 F < T < 300OF < 50°F in any % hr period RC Pumps T< 0 NA two pumps.__

no°F NA Any (a) RC Temperature is cold leg temperature if one or more RC pumps are in operation; otherwise it is the LPI cooler outlet temperature.

T < 100°F NA No pumps OCONEE UNITS 1, 2, & 3 3.4.3-3 Amendment Nos. 307, 307, & 307 I

RCS P/T Limits 3.4.3 Table 3.4.3-2 (page 1 of 1)

Operational Requirements for Unit Cooldown CONSTRAINT RC TEMPERATURE(a) MAXIMUM COOLDOWN RATE(b) ALLOWED PUMP COMBINATION RC Temperature(a) T> F 50'F in any 1/2 hour period NA 14 <OFF 50 < 25F in any 1/2 hour period NA T - in any one hour period NA RCS depressurized(c) < 50°F in any one hour period NA RC Pumps<300 T X NA Any 0

L <-26 °F NA _ two pumps W

(a) RC Temperature is cold leg temperature if one or more RC pumps are in operation or if on natural circulation cooldown; otherwise it is the LPI cooler outlet temperature.

(b) These rate limits must be applied to the change in temperature indication from cold leg temperature to LPI cooler outlet temperature per Note (a).

(c) When the RCS is depressurized such that all three of the following conditions exist:

a) RCS temperature < 2000 F, b) RCS pressure < 50 psig, c) All RC Pumps off, the maximum cooldown rate shall be relaxed to < 50°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

T < 100°F NA No pumps I

OCONEE UNITS 1, 2, & 3 3.4.3-4 Amendment Nos. 307, 307, & 307 I

RCS P/T Limits 3A4.3 The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-1 (page 1 of 1)

RCS Normal Operational Heatup Limitations Applicable for the First a*=EFPY - Oconee Nuclear Station Unit 1 OCONEE UNITS 1, 2, & 3 3.4.3-5 Amendment Nos. 307,3-,n-0 I

INSERT A 2400 2000 CL 1600 u)

I-CL 1200 800 400 4-0 0 50 100 150 200 250 300 350 Indicated RCS Inlet Temperature, OF

RCS P/T Limits 3.4.3 The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Marains for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump 7n combination restrictions during Heatup and Cooldown are required, as identified in text. z INSERT B Figure 3.4.3-2 (page 1 of 1)

RCS Normal Operational Cooldown Limitations Applicable for the First 3 EFPY - Oconee Nuclear Station Unit 1 OCONEE UNITS 1, 2, & 3 3.4.3-6 Amendment Nos. 7,I

INSERT B 2400 Normal Cooldown Temp. Press. -Composite CD Curve (rF) (psig) 2000 251 2231 246 2221

0. 231 1779 211 1363 1600 191 1083 4 -~ I 190 1053 C. 186 1029 181 981 n,

"0 171 166 837 824 161 765 155 710 C, S 800 146 636 04 135 611 110 531 105 527 100 513

'400 70 513 65 512 60 506 0

0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, *F

RCS P/T Limits 3.4.3 The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressui measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-3 (page 1 of 1)

RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for the First 3 EFPY - Oconee Nuclear Station Unit 1 OCONEE UNITS 1, 2, & 3 3.4.3-7 Amendment Nos. 307, 307, & 207 I

INSERT C 2400 ISLH Composite - ISLH Composite (HUICD) Curve 2000 Temp. Press. __

(1F) (psig) 60 553 CL 105 553 S1600 110 610 In115 752 W120 774 170 774

(. 170 1002 1200 175 1103

(,) 190 1235 V 210 1483 S80 230 1852 800 0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, *F

RCS P/T Limits 3.4.3 The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Mar-gins for instrument error are not included.

Figure 3.4.3-4 (page 1 of 1)

RCS Normal Operational Heatup Limitations Applicable for the First 33 EFPY - Oconee Nuclear Station Unit 2 OCONEE UNITS 1, 2, & 3 3.4.3-8 Amendment Nos. 307, 307, . 30.7 I

INSERT D 2400 4-..

- Composite HU Curve I'

- - Criticality Limit P-T Limit Curve U 2000 1 Normal Heatup Criticality Limit Temp. Press.

r Temp. Press. I (IF) (psig) (I) (psig) 60o S27 243 0 I 1600 105 527 243 1126 1215 543 265 1446 120 550 280 .1764 4

/

cc 170 550 300 2365 /

1200 ... 1 7o 776 ......

IQ 185 914 V.

205 1145 9 r-225 1446 800 .*. 240 1764 - _ _ _

260 2365 I.

400 0

0 50 100 150 200 250 300 350 Indicated RCS Inlet Temperature, OF

RCS P/T Limits

,3.4.3 The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressur measurement and the pressure on the reactor vessel region controlling the limit curve. Marains for instrument error are not included_

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-5 (page 1 of 1)

RCS Normal Operational Cooldown Limitations Applicable for the First

• EFPY - Oconee Nuclear Station Unit 2.

OCONEE UNITS 1, 2, & 3 3.4.3-9 Amendment Nos. 07, 3-7, &307 I

INSERT E 2400 ----------

Normal Cooldown Temp. Press. -Composite CD Curve

(*F) (psig) 2000 251 2365 241 2365 C. 231 2039 211 1539 I- 1600 191 1203

'a 190 1166 186 1138 176 1021 U) 1200 171 907 166 907 0

161 871 "0 155 802

• ~800 146 708

.2 135 670 110 557 105 557 100 544 400 75 544 70 534 60 518 0

0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF

RCS P/T Limits 3.4.3 2600 2400 ISLH Lim Temp. ress.

/ '7 / / /A /

(F) (psig) 2200 - 6* 588.

0 588 2000- 150 875 U)1800 155 175 896 1026

7. ___ ___

200 1314 0.

E 1600 215 1575 225 11 (44) 240 3653

,245 2328 251 2373 2500 0o C.

/ / / /

4000 x

200 A liz_

~0 50 100 150 200 250 300 350 400 450 Indicated ReactoCoolant Inlet Temperature,:

'Y The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit Tn curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

L-1 INSERT F Figure 3.4.3-6 (page 1 of 1)

RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for the First 33 EFPY - Oconee Nuclear Station Unit 2 OCONEE UNITS 1, 2, & 3 3.4.3-10 Amendment Nos. 307, 307, - - I

INSERT F 2400  ! . i

- ISLH Composite (HUICD) Curve 2000 ........... ... ------ --- --.... ..........

ISLH Composite

" Temp. Press.

0 (OF) (psig) 1600 .......-- o----

60 557 105 557 U)110 614 W 115 753 120 763 1200 170 763 Q170 1065 Ix190 1316 210 1643 CU 800 225 1958 240 2382 4 00 .. ...... . .. ... ....... ..........--....-i. ............ ....... ....... . ......... .. ... .. . .. . . . ...

0 5 0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, *F

RCS P/T Limits 3.4.3

( 2400 Normal Heatup LIilt Temp. Pr*ss.

Criticality Limit Temp. Pres

/r 7 1 9

2200 (F) ,sig) (F) (ps 60 588 287 70 iA

_IZ

, 2000 18 588 287 1860 0

785 295 2077 1800 190 886 3 2250 200 968 2 1.600 210 1093 220 1246 230 1434 240 186 o 12400 :245 98 -Ai 255 2077

.280/2250 J l/

'1000 SLimit 287F S800

- 0

'2600

_I _A 0

50 1 160o 20 / 250 30O 350 400 450. 500 Indicated React Coolant Inlet Tempeature,

/F

'Y The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressu measurement and the pressure on the reactor vessel region controlling the limit curve. Maraqins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

INSERT G Figure 3.4.3-7 (page 1 of 1)

RCS Normal Operational Heatup Limitations Applicable for the First EFPY - Oconee Nuclear Station Unit 3 OCONEE UNITS 1, 2, & 3 3.4.3-1 1 Amendment Nos. 7 7, W-7. 307-

INSERT G 2400

-Composite HU Curve

- - Criticality Limit P-T Limit Curve 2000 i

" Normal Heatup Criticality Limit 160 _('F)

Temp. (psi)

Press, ('F) (psig)'

Temp. Press. /

• 60 528 243 0

0) 105 528 243 1128 115 544 250 1215 1J*

120 552 260 1366 CO 1200 .- 170 552 270 1548 ......

() 170 778 280 1770 Z 190 970 290 2041 210 1215 300 2372 0 230 1548 80 25 2041

.2 '260 2372

" I:

400 _- _

0 &

0 50 100 150 200 250 300 350 Indicated RCS Inlet Temperature, 'F

RCS P/T Limits 3.4.3 The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

V Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump /

combination restrictions during Heatup and Cooldown are required, as identified in text. -7 INSERT H Figure 3.4.3-8 (page 1 of 1)

RCS Normal Operational Cooldown Limitations Applicable for the First 33 EFPY - Oconee Nuclear Station Unit 3 OCONEE UNITS 1, 2, & 3 3.4.3-12 Amendment Nos. 307, I

INSERT H 2400 Normal Cooldown Temp. Press. -Composite CD Curve 2000 ('F) (psig) 01251 2365

.2*241 2365 231 2051 211 1547 1600 191 1209 -

190 1172 186 1143

• 176 1026

(. 171 910 U) to1200 166 z~~61 910 876! )

tY' ~155 806 ' ' P 146 711 80

'*105 557 1347 100 545 75 544 400- 70 535 -

60 519 0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF

RCS P/T Limits 3.4.3 2600 24000.

2200 L 2000

, 1800 8

0.

/6

• ~~

1:58 8717 ' '

ix 1200 E 1800 60

.0 0 50 100 150 200 300 350 400 450 00 Indicated Reactor olant Inlet Temperature, F m

The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit /

curve. Margins for instrument error are not included.

/ /

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

LU I INSERTI I Figure 3.4.3-9 (page 1 of 1)

RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for the First a3=EFPY - Oconee Nuclear Station Unit 3 OCONEE UNITS 1, 2, & 3 3.4.3-13 Amendment Nos. ,-0, 7, -*n'-0 I

INSERT I 2400 ISLH Composite (HUICD) Curve 2000 . ISLH Composite .. /......

Temp. Press.

C' (OF) (psig) 60 557

3) 115 75516 n ~ 120 ~170766 766 -*i i .=i Cl)200 170 1067 180 1192 V200 1483 4),220 1850 M 800 240 2390 4O00 0 0100 t50 200 250 300 0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, *F

License Amendment Request No. 2012-10 February 22, 2012 ATTACHMENT 2 TECHNICAL SPECIFICATION RETYPE

RCS P/T Limits 3.4.3 Table 3.4.3-1 (page 1 of 1)

Operational Requirements for Unit Heatup CONSTRAINT RC TEMPERATURE(a) HEATUP RATE ALLOWED PUMP COMBINATION RC Temperature(a) T < 270°F < 30'F in any 1/2 hr period NA T > 270°F < 50'F in any 1/2 hr period NA RC Pumps T < 1000 F. N/A No pumps 100°F < T < 300OF NA < two pumps T>300OF NA Any (a) RC Temperature is cold leg temperature if one or more RC pumps are in operation; otherwise it is the LPI cooler outlet temperature.

OCONEE UNITS 1, 2, & 3 3.4.3-3 Amendment Nos.

RCS P/T Limits 3.4.3 Table 3.4.3-2 (page 1 of 1)

Operational Requirements for Unit Cooldown CONSTRAINT 'RC TEMPERATUREa) COOLDOWN RATE(b) ALLOWED PUMP COMBINATION RC Temperature(a) T > 270°F < 50°F in any 1/2 hour period NA 140°F < T < 270°F < 250F in any 1/2 hour period NA T< 140OF < 50°F in any one hour period NA RCS depressurized(c) < 50°F in any one hour period NA RC Pumps T > 300°F NA Any 0 NA < two pumps 100 F < T < 300OF T < 1001F NA No pumps (a) RC Temperature is cold leg temperature if one or more RC pumps are in operation or if on natural circulation cooldown; otherwise it is the LPI cooler outlet temperature..

(b) These rate limits must be applied to the change in temperature indication from cold leg temperature to LPI cooler outlet temperature per Note (a).

(c) When the RCS is depressurized such that all three of the following conditions exist:

a) RCS temperature < 2000 F, b) RCS pressure < 50 psig, c) All RC Pumps off, the maximum cooldown rate shall be relaxed to < 501F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

OCONEE UNITS 1, 21 & 3 3.4.3-4 Amendment Nos. I

RCS P/T Limits 3.4.3 2400 -

2-Composite HU Curve -*

-0t 1

- - Criticality Limit P-T Limit Curve i 20NormalHeatup Criticality Limit -

m ~(°F)

Temp. (psig)

Press, (oF)(psig)

Temp. Press. i!*i "W 60 528 253 0 k 1"105 528 253 1124 120 553 290 1771

)135 557 310 2374 /

170 s7 1'7

& 1200

0. 2001175S 170 729 /

804

.190 903 210 1089 230 1364 800 cc 250 270 17712 2374 i.

400 I Indicated RCS Inlet Temperature, IF The regions of acceptable operation are below and to the right of the limit curves.

Margins Iare included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.371 (page 1 of 1)

RCS Normal Operational Heatup Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 1 OCONEE UNITS 1, 2, & 3 3.4.3-5 Amendment Nos.

RCS P/T Limits 3.4.3 2400 Normal Cootdown Temp. Press. - Composite CD Curve

('F) (psig) 2000 251 246 231 211 2231 2221 1779 1363 1600 191 1083 190 1053 186 1029 181 981 171 837

.12 1200 166 824 161 765 155 710 146 636 800 135 611 110 S531 105 527 100 513 400 70 513

65. 512 60 506 A

0 0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, *F The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement *andthe pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-2 (page 1 of 1)

RCS Normal Operational Cooldown Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 1 OCONEE UNITS 1, 2, & 3 3.4.3-6 Amendment Nos.

RCS P/T Limits 3.4.3 2400 2000 C) 1600 (n

1P a..

1200 V~

800 400 0O 0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-3 (page 1 of 1)

RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 1 OCONEE UNITS 1, 2, & 3 3.4.3-7 Amendment Nos.

RCS P/T Limits

.3.4.3 2400  !

-Composite HU Curve

-- - Criticality Limit P-T Limit Curve 2000 Normal Heatup Criticality Limit

0) Temp. Press. Temp. Press. I

) )(°F) (psig) ('F) (psig) i 60 527 243 0 /

1600 105 527 243 1126/

115 543 265 1446 4 U) 120 550 280 1764 1 /

170 550 300 2365 1 1200 0.tJ)185 170 776 914

• 205 1145 i 22S 1446 80 240 1764 . I 80 0 i . ....... . ...........

400 II 0 50 100 150 200 250 300 350 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-4 (page 1 of 1)

RCS Normal Operational Heatup Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 2 OCONEE UNITS 1, 2, & 3 3.4.3-8 Amendment Nos.

RCS P/T Limits 3.4.3 2400 I Normal Cooldown Temp. Press. -Composite CD Curve

('F) (psig) 2000 251 2365 241. 2365 231 2039 I.0 211 1539 1600 191 1203

.i-i.........

190 1166 186 1138 CL 176 1021 0: 1200 171 166 161 155 146 907 907 871 802 708

./

800 135 670 110 557 105 557 100 544 400 75 544 70 534 60 518 0

0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. MarQins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-5 (page 1 of 1)

RCS Normal Operational Cooldown Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 2 OCONEE UNITS 1, 2, & 3 3.4.3-9 Amendment Nos.

RCS P/T Limits 3.4.3 2400 2000 1600 0.

C-)

1200 V) 800 400 0

0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-6 (page 1 of 1)

RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 2 I OCONEE UNITS 1, 2, & 3 3.4.3-10 Amendment Nos.

RCS P/T Limits 3.4.3 2400 2000 a.

L. 1600 (h

en 0

1~

0.

Co 1200 C.,

0 4-.

Cu 800 C.)

400 0

0 50 100 150 200 250 300 350 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-7 (page 1.of 1)

RCS Normal Operational Heatup Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 3 I OCONEE UNITS 1, 2, & 3 3.4.3-11 Amendment Nos.

RCS P/T Limits 3.4.3 2400 Normal Cooldown Temp. Press. -Composite CD Curve (1F) (psig) 2000 ,251 2365 0) 241 2365

£0 231 2051

0. ..

211 1547 G)

I- 1600 191 1209

£0 190 1172

£0 186 1143 0 176 1026

0. 171 910 (0 1200 166 910 0 161 876 155 806 146 711 a) 135 672 (U 800 U 110 557

• 0 105 557 C 100 545

75 544 400 70 535 60 519 0

0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup-and Cooldown rate restrictions and Reactor Coolant Pump*

combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-8 (page 1 of 1)

RCS Normal Operational Cooldown Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 3 OCONEE UNITS 1, 2, & 3 3.4.3-i2 Amendment Nos.

RCS P/T Limits 3.4.3 9AAfl a- -

- ISLH Composite (HUICD) Curve 2000 ISLH Composite Temp. Press.

(OF) (psig)

C) 60 557 1600 105 557 110 614 115 755 120 766 cc 170 766 e 1200 170 1067

• 180 1192 r-2 10 1850 800 240 2390 400 0

0 50 100 150 200 250 300 Indicated RCS Inlet Temperature, OF The regions of acceptable operation are below and to the right of the limit curves.

Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve. Margins for instrument error are not included.

Note: Heatup and Cooldown rate restrictions and Reactor Coolant Pump combination restrictions during Heatup and Cooldown are required, as identified in text.

Figure 3.4.3-9 (page 1 of 1)

RCS Leak and Hydrostatic Test Heatup and Cooldown Limitations Applicable for the First 54 EFPY - Oconee Nuclear Station Unit 3 I OCONEE UNITS 1, 2, & 3 3.4.3-13 Amendment Nos.