ML20212G279

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Amends 306,306 & 306 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Revising Max Local Fuel Pin Centerline Temperature Safety Limit in TSs 2.1.1.1 from Limit Determined Using TACO2 Fuel Performance Computer Code
ML20212G279
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 09/24/1999
From: Emch R
NRC (Affiliation Not Assigned)
To:
Shared Package
ML16161A308 List:
References
NUDOCS 9909290186
Download: ML20212G279 (8)


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NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 206MH1001 4*****4 1

DUKE ENERGY CORPORATION DOCKET NO. 50-2.59 OCONEE NUCLEAR GTATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 306 License No. DPR-38

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility)

Facility Operating License No. DPR-38 filed by the Duke Energy Corporation (the licensee) dated May 24,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations ui the Commission; C. There is reasonable assurance (i) that the activiti. ' uthorized by this amendment can i

be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfind.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-38 is hereby amended to read as follows:

9909290186 990924 PDR ADOCK 05000269 P

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B. Technical Soecificationg The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 306, are hereby incorporated in the license. The licensee shall operate the facility in mcordance with the Technical Specifications.

3. This license amendment 11.,:thective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMM.SSION

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Richard L. Emch, Jr., Chief, Section 1 Project Directorate ll Division of Licensing Project Management j

Office of Nuclear Reactor Regulation l

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Attachment:

Technical Specification Changes Date of issuance: September 24, 1999 l

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20565 0001

.....,o DUKE ENERGY CORPORATION DOCKET NO. 50-270 OCONEE NUCLEAR STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 306 License No. DPR-47 l

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 2 (the facility)

Facility Operating Lice.se No. DPR-47 filed by the Duke Energy Corporation (the licensee) dated May 24,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulanons of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the putslic, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:

2-B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 306, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Richard L. Emch, Jr., Chief, Section 1 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Chas w Date of Issuance: September 24, 1999 I

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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20556-0001

  • * * * *,o DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 306 License No. DPR-55
1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility)

Facility Operating License No. DPR-55 filed by the Duke Energy Corporation (the licensee) dated May 24,1999, complies with the standards and requirements of the Atomic En< ay Act of 1954, as amended (the Act), and the Commission's rules and regulatior a set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defenso and security or to the health and safety of the public; and i

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as follows:

. B. Technical Specifications The Technical Specificatiors contained in Appendices A and B, as revised through Amendment No. 306

, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Richard L. Emch, Jr., Chief, Section 1 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation 1

Attachment:

l Technical Specification l

Changes l

p Date of issuance: September 24, 1999 i

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1

ATTACHMENT TO LICENSE AMENDMENT NO. 306 FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 '

AND TO LICENSE AMENDMENT NO. 306 FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO.306 FACILITY OPERATING LICENSE NO. DPR-55 i

DOCKET NO. 50-287 I

J Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 2.0-1 2.0-1 j

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i, SLs j

2.0

' 2.0 SAFETY LIMITS'(SLs) 2.1 SLs-2.1.1 -

Reactor Core SLs' 2.1.1.1 in MODES 1 and 2, the maximum local fuel pin centerline o

. temperature shall be s 4642 - (5.8 x 10'8 x (Burnup, MWD /MTU))* F.

l Operation within this limit is ensured by compliance with the Axial i

Power Imbalance Protective Limits as specified in the Core Operating -

Limits Report.

2.1.1.2 in MODES 1 and 2, the departure from nucleate boiling ratio shall be maintained greater than the limit of 1.18 for the BWC correlation.

Operation within this limit is ensured by compliance with the Axial Power imbalance Protective Limits and RCS Variable Low Pressure Protective Limits as specified in the Core Operating Limits Report.

2.1.2 RCS Pressure SL in MODES 1,2,3,4, and 5, the RCS pressure shall be maintained s 2750 psig.

2.2-SL Violations With any SL violation, the following actions shall be completed:

2.2.1 -

In MODE 1 or 2, if SL 2.1.1.1 or SL 2.1.1.2 is violated, be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 In MODE 1 or 2, if SL 2.1.2 is violated, restore compliance within limits and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.3 In MODES 3,4, and 5, if SL 2.1.2 is violated, restore RCS pressure to s 2750 psig within 5 minutes.

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OCONEE UNITS 1,2, & 3 2.0-1 Amendment Nos. 306, 306, & 306l 1

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