ML021900580

License Amendment, Revise TS 5.6.5.b to Eliminate the Revision Number and Dates from the List of Topical Reports That Contain the Analytical Methods Used to Determine the Core Operating Limits

ML021900580
Person / Time
Site:	Oconee
Issue date:	07/09/2002
From:	Olshan L NRC/NRR/DLPM/LPD2
To:	Mccollum W Duke Energy Corp
Olshan L N, NRR/DLPM, 415-1419
References
TAC MB3713, TAC MB3714, TAC MB3715
Download: ML021900580 (14)

Text

July 9, 2002 Mr. William R. McCollum, Jr.

Vice President, Oconee Site Duke Energy Corporation 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MB3713, MB3714, AND MB3715)

Dear Mr. McCollum:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 326, 326, and 327 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, respectively, for the Oconee Nuclear Station, Units 1, 2, and 3. The amendments consist of changes to the Technical Specifications in response to your application dated December 20, 2001.

The amendments revise TS 5.6.5.b to eliminate the revision number and dates from the list of topical reports that contain the analytical methods used to determine the core operating limits.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Leonard N. Olshan, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 326 to DPR-38

2. Amendment No. 326 to DPR-47

3. Amendment No. 327 to DPR-55

4. Safety Evaluation cc w/encls: See next page

July 9, 2002 Mr. William R. McCollum, Jr.

Vice President, Oconee Site Duke Energy Corporation P. O. Box 1439 Seneca, SC 29679

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - ISSUANCE OF AMENDMENTS RE: (TAC NOS. MB3713, MB3714, AND MB3715)

Dear Mr. McCollum:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 326, 326, and 327 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, respectively, for the Oconee Nuclear Station, Units 1, 2, and 3. The amendments consist of changes to the Technical Specifications in response to your application dated December 20, 2001.

The amendments revise TS 5.6.5.b to eliminate the revision number and dates from the list of topical reports that contain the analytical methods used to determine the core operating limits.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

/RA/

Leonard N. Olshan, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 326 to DPR-38

2. Amendment No. 326 to DPR-47

3. Amendment No. 327 to DPR-55

4. Safety Evaluation cc w/encls: See next page DISTRIBUTION: OGC WBeckner PUBLIC ACRS T-6 E26 RHaag,RII PDII-1 R/F GHill(6)

Package No.: ML021970223 Accession No.: ML021900580 TSs: ML021970218 DOCUMENT NAME: C:\ADAMS\Cache\ML0219005800.wpd *See previous concurrence OFFICE PDII-1/PM PDII-1/PM PDII-1/LA OGC* PDII-1/SC NAME CPatel LOlshan CHawes SUttal JNakoski DATE 7/9/02 7/9/02 7/9/02 7/5/02 7/9/02 OFFICIAL RECORD COPY

DUKE ENERGY CORPORATION DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 326 Renewed 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)

Renewed Facility Operating License No. DPR-38 filed by the Duke Energy Corporation (the licensee) dated December 20, 2001, 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 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 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 Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 326, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: July 9, 2002

DUKE ENERGY CORPORATION DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 326 Renewed License No. DPR-47

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

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

Renewed Facility Operating License No. DPR-47 filed by the Duke Energy Corporation (the licensee) dated December 20, 2001, 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 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 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 Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 326, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: July 9, 2002

DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 327 Renewed 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)

Renewed Facility Operating License No. DPR-55 filed by the Duke Energy Corporation (the licensee) dated December 20, 2001, 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 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 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 Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 327, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

John A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: July 9, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 326 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 326 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 327 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 5.0-30 5.0-30 5.0-31 5.0-31

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 326 TO RENEWED FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO. 326 TO RENEWED FACILITY OPERATING LICENSE DPR-47 AND AMENDMENT NO. 327 TO RENEWED FACILITY OPERATING LICENSE DPR-55 DUKE ENERGY CORPORATION OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287

1.0 INTRODUCTION

By letter dated December 20, 2001, Duke Energy Corporation (the licensee) submitted a request for changes to the Oconee Nuclear Station, Units 1, 2, and 3, Technical Specifications (TS). The requested changes would revise TS 5.6.5 to incorporate the changes in Technical Specifications Task Force (TSTF)-363. In a letter from Mr. Stuart A. Richards (Nuclear Regulatory Commission (NRC)) to Mr. James F. Mallay (Siemens Power Corporation) dated December 15, 1999, the NRC staff stated that it is acceptable for the references to topical reports in improved Technical Specifications (ITS) Section 5.6.5, Core Operating Limits Report (COLR), to give the topical report title and number as long as the complete citation is given in the COLR.

2.0 BACKGROUND

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TS as part of the operating license. On July 22, 1993, the Commission issued its Final Policy Statement (58 FR 39132) that described the safety benefits of the improved Standard Technical Specifications (iSTS). This Final Policy Statement encouraged licensees to use the iSTS as the basis for plant-specific TS amendments and for complete conversions to ITS based on the iSTS.

The industry and the NRC staff have worked to improve the new iSTS, and many generic changes have been proposed by the Nuclear Energy Institute TSTF to the NRC. After NRC approval, these TSTF changes are available for adoption by plants.

3.0 EVALUATION (1) Description of Changes In NUREG-1430, Revision 2, Standard Technical Specification - Babcock and Wilcox Plants Technical Specification 5.6.5.b, CORE OPERATING LIMITS REPORTS (COLR), currently states:

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

[Identify the Topical Report(s) by number and title or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date. The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).]

The above NUREG-1430, Revision 2, iSTS 5.6.5.b has incorporated the approved TS 5.6.5.b changes in TSTF-363, Revision 0.

The current TS 5.6.5.b of the Oconee Nuclear Station, Units 1, 2, and 3 are based on the old NUREG-1430, Revision 1, which states:

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

[Identify the topical report(s) by number, title, date, and NRC staff approval document, or identifies the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date.]

For example, the current Oconee Nuclear Station, Units 1, 2, and 3 TS 5.6.5.b identifies the topical report as:

DPC-NE-1002-A, Reload Design Methodology II, Rev. 1, (SER dated October 1, 1985)

After incorporation of TSTF-363, Revision 0, and consistent with NUREG-1430, Revision 2, the above TS identifies the topical report as:

DPC-NE-1002-A, Reload Design Methodology II.

In addition, the topical report listed as item 4 in Oconee TS 5.6.5.b is currently shown as DPC-NE-1004P-A. This should be DPC-NE-1004-A. There is no proprietary version of this topical report. The NRC review and approval of new or revised topical reports will continue to be obtained in the same manner. Changes to the COLRs will be controlled by the Administrative Controls of the TS 5.6.5.

(2) Justification The need for the Oconee Nuclear Station, Units 1, 2, and 3 to adopt TSTF-363, Rev. 0 is that its approved method of referencing topical reports would allow the licensee to use current topical reports to support limits in the COLR without having to submit an amendment to the facility operating license every time the topical report is revised. The COLR would provide specific information identifying the particular approved topical reports used to determine the core limits for the particular cycle in the COLR report. The NRC approval process of topical reports, along with an adequate change control process for changing the COLR, continues to exist. Adequate safety is maintained.

Based on the above evaluation, the staff finds the proposed changes for TS 5.6.5.b listings of topical reports for Oconee Nuclear Station, Units 1, 2, and 3 are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded based on the considerations discussed above that: (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 amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Angela T. Chu Date: July 9, 2002

Oconee Nuclear Station cc:

Ms. Lisa F. Vaughn Mr. L. E. Nicholson Legal Department (PBO5E) Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28201-1006 7800 Rochester Highway Seneca, South Carolina 29672 Anne W. Cottingham, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Manager, LIS P. O. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. C. Jeffrey Thomas Manager - Nuclear Regulatory Senior Resident Inspector Licensing U. S. Nuclear Regulatory Duke Energy Corporation Commission 526 South Church Street 7812B Rochester Highway Charlotte, North Carolina 28201-1006 Seneca, South Carolina 29672 Mr. Richard M. Fry, Director Mr. Henry Porter, Director Division of Radiation Protection Division of Radioactive Waste Management North Carolina Department of Bureau of Land and Waste Management Environment, Health, and Department of Health and Environmental Natural Resources Control 3825 Barrett Drive 2600 Bull Street Raleigh, North Carolina 27609-7721 Columbia, South Carolina 29201-1708 Mr. Peter R. Harden, IV Mr. Michael A. Schoppman VP-Customer Relations and Sales Framatome ANP Westinghouse Electric Company 1911 North Ft. Myer Drive 6000 Fairview Road Suite 705 12th Floor Rosslyn, VA 22209 Charlotte, North Carolina 28210