ML070110314

License Amendment, Issuance of Amendments Regarding Steam Generator Tube Integrity

ML070110314
Person / Time
Site:	Oconee
Issue date:	04/02/2007
From:	Olshan L NRC/NRR/ADRO/DORL/LPLII-1
To:	Brandi Hamilton Duke Power Co
Olshan L, NRR/DLPM, 415-1419
Shared Package
ML070110302	List: ML070110314 ML070930372
References
TAC MC2043, TAC MD2038, TAC MD2039, TAC MD2040, TAC MD2044, TAC MD2045
Download: ML070110314 (16)

Text

April 2, 2007 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Power Company LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3, ISSUANCE OF AMENDMENTS REGARDING STEAM GENERATOR TUBE INTEGRITY, TSTF-449, AND AN ADMINISTRATIVE CHANGE (TAC NOS. MD0092, MD0093, MD0094, MD2038, MD2039, MD2040, MD2043, MD2044, AND MD2045)

Dear Mr. Hamilton:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos.

355, 357, and 356 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the licenses and Technical Specifications (TSs) in response to your application dated April 11, 2006, as supplemented by letter dated October 24, 2006.

These amendments revise the TS requirements related to steam generator tube integrity consistent with the NRC-approved Revision 4 to Technical Specification Task Force (TSTF)

Standard Technical Specification Change Traveler TSTF-449, Steam Generator Tube Integrity. As stated in your letter dated February 15, 2006, the amendment is also the modification of the steam generator portion of the TSs requested in NRC Generic Letter (GL) 2006-01, Steam Generator Tube Integrity and Associated Technical Specifications. The NRC staff considers the amendment to be an acceptable and complete response to GL 2006-01.

These amendments also remove license conditions that become outdated with these TS changes. In addition, the amendments revise the organizational description in TS 5.2.1, which is solely administrative and unrelated to steam generator tube integrity

B. Hamilton 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, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 355 to DPR-38

2. Amendment No. 357 to DPR-47

3. Amendment No. 356 to DPR-55

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

B. Hamilton April 2, 2007 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, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 355 to DPR-38

2. Amendment No. 357 to DPR-47

3. Amendment No. 356 to DPR-55

4. Safety Evaluation cc w/encls: See next page DISTRIBUTION: Public RidsAcrsAcnwMailCenter LPLII-1 R/F GHill (6 hard copies)

RidsNrrDorlLp2-1 (EMarinos) RidsNrrDirsItsb (TKobetz)

RidsNrrPMLOlshan (hard copy) RidsRgn2MailCenter (MErnstes)

RidsNrrLAMOBrien (hard copy) RidsNrrDorlDpr RidsOgcRp TWertz, NRR Package No.: ML070110302 License Amendment No.: ML070110314 Tech Spec No.: ML070930372 *Memo input provided OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/ITSB/BC OGC NRR/LPL2-1/BC NAME LOlshan:nc MOBrien TKobetz SHamrich EMarinos DATE 3/19/07 3/29/07 12/5/06* 3/26/07 3/29/07 OFFICIAL RECORD COPY

DUKE POWER COMPANY LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 355 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 Power Company LLC (the licensee), dated April 11, 2006, and supplemented October 24, 2006, 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. 355, 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

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-38 and the Technical Specifications Date of Issuance: April 2, 2007

DUKE POWER COMPANY LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 357 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 Power Company LLC (the licensee), dated April 11, 2006, and supplemented October 24, 2006, 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. 357, 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

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renwed Facility Operating License No. DPR-47 and the Technical Specifications Date of Issuance: April 2, 2007

DUKE POWER COMPANY LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 356 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 Power Company LLC (the licensee), dated April 11, 2006, and supplemented October 24, 2006, 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. 356, 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

/RA/

Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-55 and the Technical Specifications Date of Issuance: April 2, 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 355 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 357 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 356 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages Licenses Licenses License No. DPR-38, page 3 License No. DPR-38, page 3 License No. DPR-38, page 8a License No. DPR-38, page 8a License No. DPR-47, page 3 License No. DPR-47, page 3 License No. DPR-47, page 8a License No. DPR-47, page 8a License No. DPR-55, page 3 License No. DPR-55, page 3 License No. DPR-55, page 8a License No. DPR-55, page 8a TSs Tss Table of Contents, page iii Table of Contents, page iii Table of Contents, page v Table of Contents, page v Bases Table of Contents, page iii Bases Table of Contents, page iii 1.1-3 1.1-3 3.4.13-1 3.4.13-1 3.4.13-2 3.4.13-2

--- 3.4.13-3

--- 3.4.16-1

--- 3.4.16-2

5.0-2 5.0-2 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15 5.0-16 5.0-16 5.0-17 5.0-17 5.0-18 5.0-18 5.0-19 5.0-19 5.0-20 5.0-20 5.0-21 5.0-21 5.0-22 5.0-22 5.0-23 5.0-23 5.0-24 5.0-24 5.0-25 5.0-25 5.0-26 5.0-26 5.0-27 5.0-27 5.0-28 ---

5.0-29 ---

5.0-30 ---

5.0-31 ---

5.0-32 ---

5.0-33 ---

5.0-38 ---

B 3.4.5-2 B 3.4.5-2 B 3.4.6-2 B 3.4.6-2 B 3.4.7-3 B 3.4.7-3 B 3.4.13-1 B 3.4.13-1 B 3.4.13-2 B 3.4.13-2 B 3.4.13-3 B 3.4.13-3 B 3.4.13-4 B 3.4.13-4 B 3.4.13-5 B 3.4.13-5

--- B 3.4.13-6

--- B 3.4.16-1

--- B 3.4.16-2

--- B 3.4.16-3

--- B 3.4.16-4

--- B 3.4.16-5

--- B 3.4.16-6

--- B 3.4.16-7

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 355 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 357 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND AMENDMENT NO. 356 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DUKE POWER COMPANY LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287

1.0 INTRODUCTION

By application dated April 11, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML061080500), as supplemented by letter dated October 24, 2006 (ADAMS Accession No. ML063040561), Duke Power Company LLC (Duke, the licensee),

requested changes to the licenses and Technical Specifications (TSs) for the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1/2/3). The supplement dated October 24, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on January 3, 2007 (72 FR 149).

The proposed changes would revise the TS requirements related to steam generator tube integrity consistent with the NRC-approved Revision 4 to Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-449, Steam Generator Tube Integrity. The proposed changes to the license would remove license conditions that become outdated with these TS changes. In addition, the proposed changes would revise the organizational description in TS 5.2.1, which is solely administrative and unrelated to steam generator tube integrity

2.0 REGULATORY EVALUATION

The background, description, and applicability of the proposed changes associated with the steam generator (SG) tube integrity issue and the applicable regulatory requirements were included in the Nuclear Regulatory Commission (NRC) staffs model safety evaluation (SE) published in the Federal Register on March 2, 2005 (70 FR 10298). The Notice of Availability

of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process, was published in the Federal Register on May 6, 2005 (70 FR 24126),

which made the model SE available for licensees to reference.

3.0 TECHNICAL EVALUATION

3.1 Overview In its April 11, 2006, application, and the October 24, 2006, supplement, the licensee proposed changes to the TSs that are modeled after Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-449, Steam Generator Tube Integrity. There were minor differences between TSTF-449 and the licensee's application. These included differences in the facility licensing basis (than that discussed in TSTF-449) and differences in TS numbering. These differences are discussed below.

With respect to the differences in the facility licensing basis, the differences did not invalidate the technical evaluation on TSTF-449; rather they resulted in the licensee having to slightly deviate from some of the modifications discussed in TSTF-449. For example, in the Limiting Condition for Operation (LCO) for Steam Generator Tube Integrity (in proposed Technical Specification 3.4.16), there is a requirement to be in MODE 3 within a specified time period. In TSTF-449, this time period is set at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> which is consistent with other LCOs for entry into MODE 3; however, the licensee proposed to set this time period at 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, which is consistent with the other LCOs in its TSs. Another example is contained in the Steam Generator (SG) Tube Integrity, Bases Section. In TSTF-449, it was indicated that the accident analysis for a SG tube rupture assumed the contaminated secondary fluid was only briefly released to the atmosphere via safety valves and the majority is discharged to the main condenser. Since the licensee has a different licensing basis than the one described in the standard technical specifications (i.e., TSTF-449), the licensee modified the TSTF-449 wording to accommodate the existing licensing Bases (namely that the accident analysis for a steam generator tube rupture assumes cooldown via the main steam atmospheric dump valves).

Since these differences were minor in nature, they were consistent with the plant's licensing basis, and they were consistent with the intent of TSTF-449, the NRC staff determined they were acceptable.

With respect to the differences in the numbering of the TSs, these differences were administrative in nature and did not affect the technical adequacy of the submittal. As a result, the NRC staff determined they were acceptable.

In addition to the above, the licensee also proposed a few changes that went beyond TSTF-449. For example, the licensee proposed to change the organizational description in TS 5.2.1.d to indicate that the Group Vice President (rather than the Senior Vice President) has corporate responsibility for overall nuclear safety. This change was made to conform to a previous application for the indirect transfer of control of the facility operating licenses that was approved by the NRC in a letter dated February 7, 2006. Since this change is administrative in nature and consistent with the previous approval, the NRC staff found it acceptable.

In addition, the licensee proposed to delete several license conditions (Conditions 5 and 6 on page 8a of Oconee 1/2/3 licenses), the inspection and repair criteria, and the repair methods that were applicable to their original SGs. The inspection and repair criteria and repair methods

applicable to the original SGs are contained in TS 5.5.21. The NRC staff concluded that deleting these requirements was acceptable since they were no longer applicable to the replacement SGs installed at Oconee 1/2/3. In addition, removal of the repair methods is acceptable since the licensee will be required to plug tubes that exceed the repair criteria and plugging is an acceptable method for removing tubes from service. The licensee also indicated that it would delete reference to the loss of load analysis in the Bases since the original loss of load analysis is no longer part of their licensing basis (i.e., it was replaced with the turbine trip analysis which was originally approved by the NRC in a letter dated October 1, 1998). Since this event is no longer part of their licensing basis, the NRC staff concluded that it was acceptable to delete reference to it.

In addition, there were some changes in the Bases Section of TSTF-449 that were not incorporated into the licensees submittal since the licensee did not have the corresponding paragraphs in its version of the Bases. For example, the licensee did not have several references to the SG tube surveillance program in the existing TSs so the licensee did not need to delete these changes in order to adopt TSTF-449. Since these differences were administrative in nature and did not affect the technical adequacy of the submittal, the NRC staff determined they were acceptable.

The remainder of the application was consistent with, or more limiting than, TSTF-449 with one exception, as discussed below. In TSTF-449, the limit on normal operating primary-to-secondary leakage rate through any one SG was less than that assumed in the safety analysis.

However, for Oconee 1/2/3, the normal operating primary-to-secondary leakage limit (150 gallons-per-day (gpd) per SG) is identical to the accident-induced primary-to-secondary leakage limit for design-basis accidents (DBAs) other than a SG tube rupture. Even though the normal operating primary-to-secondary leakage limit and the accident-induced leakage limit have a different technical basis, it is not uncommon that the two limits are the same (note, the normal operating primary-to-secondary leakage limit can not be greater than the accident-induced leakage limit). The normal operating primary-to-secondary leakage limit is intended to limit the frequency of SG tube ruptures (i.e., it is an early indicator of a potential loss of the structural integrity of a SG tube); whereas the accident-induced leakage limit ensures that the dose consequences associated with this leakage are acceptable. Given this situation, the NRC staff evaluated the acceptability of this difference between TSTF-449 and the licensees submittal.

Since the leakage rate observed during operation may increase during a DBA, it may be necessary to ensure that the operational leak rate is kept below its limit in order to meet the accident limit. An increase in leakage during a DBA can be a result of either: (1) the higher differential pressure between the primary coolant system and the secondary system associated with a DBA thus causing the leak rate from flaws that leak during normal operation to leak at higher rates; or (2) the higher stress loadings associated with a DBA causing a flaw that was not leaking during normal operation to leak during the DBA.

To address this issue the licensee indicated that the Oconee 1/2/3 procedures recognize this issue. In addition, the licensee indicated that its procedures require a prompt shutdown when the primary-to-secondary leakage rate is 100 gpd per SG. This administrative limit is intended to provide margin between the operating and accident-induced leakage limit consistent with TSTF-449. The NRC staff notes that although there may be margin between these limits, the NRC staffs approval of TSTF-449 (and this amendment) was not intended to ensure that satisfying the operating leakage limit would result in the accident-induced leakage limit being met. Rather, the NRC staff reviewed the adequacy of the proposed TS criteria for operational

and accident-induced leakage based on the technical basis associated with each limit. Namely, that the operating leakage limit is effective at limiting the frequency of tube ruptures and the accident-induced leakage limit is consistent with the plants design and licensing basis. Since the TS criteria on operational leakage at Oconee 1/2/3 is consistent with TSTF-449 and the accident-induced leakage limit is consistent with the licensees accident analysis, the NRC staff finds the licensees proposed TS criteria on these values acceptable.

With respect to the discussion in the licensees proposed Bases concerning the accident-induced leakage limit and the normal operating leakage limit, the NRC staff identified an apparent inconsistency. Specifically, in insert B 3.4.13A (which is an insert into the Bases) and on page B 3.4.16-2 of the proposed Bases, the licensee implies that the normal operating leakage limit is less than the conditions assumed in the safety analyses. Since the two limits are equal (as discussed above), this inconsistency has been corrected in the Bases pages that are being issued with these amendments. The changes to the Bases pages will be incorporated in accordance with the TS Bases Control Program.

In summary, the NRC staff determined that the model safety evaluation published in the FR on March 2, 2005, is applicable to this review and finds the proposed changes acceptable.

Consistent with TSTF-449, the proposed TS changes include: (1) a revised definition of LEAKAGE, (2) a revised TS 3.4.13, "Reactor Coolant System (RCS) Operational LEAKAGE,"

(3) a new TS 3.4.16, Steam Generator (SG) Tube Integrity, (4) a revised TS 5.5.10, Steam Generator (SG) Tube Surveillance Program, (5) a revised TS 5.6.8, Steam Generator (SG)

Tube Inspection Report, (6) a revised TS 5.2.1, "Onsite and Offsite Organizations," and (7) a revised Table of Content pages to reflect the proposed changes.

The proposed TS change removes a number of pages from Section 5.5.10, and all of Section 5.5.10 will now be contained on page 5.0-15 and Sections 5.5.11 through 5.6.8 will now begin on page 5.0-16. The contents of pages 5.0-16 through 5.0-27 are not being changed, but these pages are included with the issuance of the amendments because the page numbers are changing. In addition, Table of Contents page v, which was inadvertently not submitted with the original application, is being changed to show that Section 5.6.8 now begins on page 5.0-23.

3.2 Conclusion The proposed TS changes establish a programmatic, largely performance-based regulatory framework for ensuring SG tube integrity is maintained. The NRC staff finds that it addresses key shortcomings of the current framework by ensuring that SG programs are focused on accomplishing the overall objective of maintaining tube integrity. It incorporates performance criteria for evaluating tube integrity that the NRC staff finds consistent with the structural margins and the degree of leak tightness assumed in the current plant licensing basis. The NRC staff finds that maintaining these performance criteria provides reasonable assurance that the SGs can be operated safely without increase in risk.

The revised TSs will contain limited specific details concerning how the SG Program is to achieve the required objective of maintaining tube integrity; the intent being that the licensee will have the flexibility to determine the specific strategy for meeting this objective. However, the NRC staff finds that the revised TSs include sufficient regulatory constraints on the

establishment and implementation of the SG Program such as to provide reasonable assurance that tube integrity will be maintained.

Failure to meet the performance criteria will be reportable pursuant to the requirements in 10 CFR Parts 50.72 and 50.73. The NRC reactor oversight process provides a process by which the NRC staff can verify that the licensee has identified any SG Program deficiencies that may have contributed to such an occurrence and that appropriate corrective actions have been implemented.

In conclusion, the NRC staff finds that the TS changes proposed by the licensee in its April 11, 2006, application and October 24, 2006, supplement conform to the requirements of 10 CFR 50.36 and establish a TS framework that will provide reasonable assurance that SG tube integrity is maintained without undue risk to public health and safety.

The licensee included in its application the revised TS Bases to be implemented with the TS change. The NRC staff finds that the TS Bases Control Program is the appropriate process for updating the affected TS Bases pages and has, therefore, not included the affected Bases pages with this amendment.

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 change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (72 FR 149, January 3, 2007). The amendments also 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)(9) and (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: T. Wertz Date: April 2, 2007 Oconee Nuclear Station, Units 1, 2, and 3 cc:

Mr. Bruce H. Hamilton Duke Power Company LLC Vice President, Oconee Site 7800 Rochester Highway

Seneca, SC 29672 Manager - Nuclear Regulatory Issues and Industry Affairs Ms. Lisa F. Vaughn Duke Power Company LLC Associate General Counsel and Managing 526 S. Church St.

Attorney Mail Stop EC05P Duke Energy Carolinas, LLC Charlotte, NC 28202 526 South Church Street - EC07H Charlotte, North Carolina 28202 Division of Radiation Protection NC Dept of Environment, Health, & Natural Manager, LIS Resources NUS Corporation 3825 Barrett Dr.

2650 McCormick Dr., 3rd Floor Raleigh, NC 27609-7721 Clearwater, FL 34619-1035 Mr. Peter R. Harden, IV Senior Resident Inspector VP-Customer Relations and Sales U.S. Nuclear Regulatory Commission Westinghouse Electric Company 7812B Rochester Highway 6000 Fairview Road Seneca, SC 29672 12th Floor Charlotte, NC 28210 Mr. Henry Porter, Director Division of Radioactive Waste Management Mr. Henry Barron Bureau of Land and Waste Management Group Vice President, Nuclear Generation Dept. of Health and Env. Control and Chief Nuclear Officer 2600 Bull St. P.O. Box 1006-EC07H Columbia, SC 29201-1708 Charlotte, NC 28201-1006 Mr. Michael A. Schoppman Mr. Charles Brinkman Framatome ANP Director, Washington Operations 1911 North Ft. Myer Dr. Westinghouse Electric Company Suite 705 12300 Twinbrook Parkway, Suite 330 Rosslyn, VA 22209 Rockville, MD 20852 Mr. B. G. Davenport Ms. Kathryn B. Nolan Regulatory Compliance Manager Senior Counsel Oconee Nuclear Site Duke Energy Carolinas, LLC Duke Energy Corporation 526 South Church Street - EC07H ON03RC Charlotte, NC 28202 7800 Rochester Highway Seneca, SC 29672 Mr. Leonard G. Green Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R. L. Gill, Jr.