ML042820458
| ML042820458 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/02/2004 |
| From: | Olshan L NRC/NRR/DLPM/LPD2 |
| To: | Rosalyn Jones Duke Energy Corp |
| Olshan L N, NRR/DLPM, 415-1419 | |
| Shared Package | |
| ML042820468 | List: |
| References | |
| TAC MC1785, TAC MC1786, TAC MC1787 | |
| Download: ML042820458 (15) | |
Text
November 2, 2004 Mr. Ronald A. Jones 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. MC1785, MC1786, AND MC1787)
Dear Mr. Jones:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 341, 343, and 342 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 January 15, 2004, as supplemented by letter dated March 15, 2004.
The amendments revise the Technical Specifications associated with the control rod drive trip devices. These amendments are needed to support implementation of the reactor trip breaker replacement.
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, 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. 341 to DPR-38
- 2. Amendment No. 343 to DPR-47
- 3. Amendment No. 342 to DPR-55
- 4. Safety Evaluation cc w/encls: See next page
November 2, 2004 Mr. Ronald A. Jones 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 RE: (TAC NOS. MC1785, MC1786, AND MC1787)
Dear Mr. Jones:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 341, 343, and 342 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 January 15, 2004, as supplemented by letter dated March 15, 2004.
The amendments revise the Technical Specifications associated with the control rod drive trip devices. These amendments are needed to support implementation of the reactor trip breaker replacement.
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, 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. 341 to DPR-38
- 2. Amendment No. 343 to DPR-47
- 3. Amendment No. 342 to DPR-55
- 4. Safety Evaluation cc w/encls: See next page DISTRIBUTION: See next page ADAMS Accession Number: ML042820468 (Package)
ADAMS Accession Number: ML042820458 (Amendment)
ADAMS Accession Number: ML043080290 (Technical Specifications)
OFFICE PDII-1/PM PDII-1/LA (A)
EEIB/SC OGC PDII-1/SC (A)
DIPM/TSS NAME LOlshan DClarke EMarinos MWoods w/NLO MRoss-Lee TBoyce DATE 10/12/04 10/12/04 09/21/04 10/21/04 10/29/04 10/26/04 OFFICIAL RECORD COPY
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE: ISSUANCE OF AMENDMENTS RE: (TAC NOS. MC1785, MC1786, AND MC1787)
Date: November 2, 2004 DISTRIBUTION:
PUBLIC PDII-1 R/F EHackett JNakoski/MRoss-Lee LOlshan CHawes/DClarke OCG ACRS/ACNW GHill (6)
TBoyce RidsRgn2MailCenter DLPMDPR PRebstock
DUKE ENERGY CORPORATION DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 341 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 January 15, 2004, as supplemented by letter dated March 15, 2004, 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. 341, 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 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mary Jane Ross-Lee, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: November 2, 2004
DUKE ENERGY CORPORATION DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 343 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 January 15, 2004, as supplemented by letter dated March 15, 2004, 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. 343, 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 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mary Jane Ross-Lee, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: November 2, 2004
DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 342 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 January 15, 2004, as supplemented by letter dated March 15, 2004, 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. 342, 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 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Mary Jane Ross-Lee, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: November 2, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 341 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 343 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 342 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 3.3.4-1 3.3.4-1 3.3.4-2 3.3.4-2 3.3.4-3 3.3.4-3 B 3.3.4-1 B 3.3.4-1 B 3.3.4-2 B 3.3.4-2 B 3.3.4-3 B 3.3.4-3 B 3.3.4-4 B 3.3.4-4 B 3.3.4-5 B 3.3.4-5 B 3.3.4-6 B 3.3.4-6
B 3.3.4-7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 341 TO RENEWED FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO. 343 TO RENEWED FACILITY OPERATING LICENSE DPR-47 AND AMENDMENT NO. 342 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 to the U.S. Nuclear Regulatory Commission (NRC, Commission) dated January 15, 2004, as supplemented March 15, 2004, Duke Energy Corporation (the licensee) submitted a request for changes to the Oconee Nuclear Station (Oconee), Units 1, 2, and 3, Technical Specifications (TSs). The requested changes would revise the TSs associated with the control rod drive (CRD) trip devices. The requested changes are needed to support implementation of the reactor trip breaker (RTB) replacement.
The proposed changes would revise the TSs concerning the RTB to reflect a modified RTB configuration associated with the replacement of the CRD system. Specifically, the licensees January 15, 2004, submittal indicated that the replacement of the CRD/RTBs is part of the overall digital CRD control system (CRDCS) upgrade. The replacement of the RTBs, although included in the overall modification, is not a digital upgrade. The digital upgrade involves the CRDCS only. The portion of the modification requiring a TS change to allow implementation is the RTB replacement. The licensee is replacing the existing two AC RTBs and four DC RTBs with four AC RTBs. The licensee proposes to revise TS 3.3.4,"Control Rod Drive (CRD) Trip Devices," to address the new configuration. Since the Oconee TSs are common to all three units, Notes will be used to indicate the applicable requirement for each unit based on whether the modifications have been implemented. The proposed change to TS 3.3.4 adds a limiting condition for operation (LCO) and appropriate ACTIONS for the new configuration. After completion of the modification on all three units, the licensee plans to submit a TS change to remove the obsolete requirements related to the existing CRD trip devices.
The proposed TS changes would:
modify existing LCO 3.3.4 to apply only when the CRD/RTB upgrade has not yet been completed add a requirement to LCO 3.3.4 that four AC CRD trip breakers must be operable if the CRD/RTB upgrade has been completed modify LCO 3.3.4 Conditions A and B to accommodate both the upgraded and the non-upgraded configuration modify LCO 3.3.4 Condition C to accommodate the fact that electronic trip assembly relays may no longer be required (they are used only in the present plant condition, and are eliminated in the upgrade)
This safety evaluation addresses the acceptability of the proposed TS changes for this modification.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(h)(2) requires that, for plants with construction permits issued prior to January 1, 1971, the design of protection systems must meet the original licensing bases or may meet the Institute of Electrical and Electronics Engineers (IEEE) Standard 603-1991, Criteria for Safety Systems for Nuclear Power Generating Stations, with correction sheet dated January 30, 1995. The construction permits for the three Oconee units were issued in 1967. In its March 15, 2004, submittal, the licensee identified the applicable regulatory criteria as:
IEEE-279, Criteria for Protection Systems for Nuclear Power Plants IEEE-379, Standard Application of the Single Failure Criterion to Nuclear Power Generating Class 1E Systems Regulatory Guide 1.53, Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems Regulatory Guide 1.75, Physical Independence of Electric Systems
3.0 TECHNICAL EVALUATION
The NRC staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment, which are described in Attachment 3 to the licensees submittal.
The detailed evaluation described in this section supports the conclusion 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 Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
The proposed change is requested in connection with the replacement of the CRDCS. The CRDCS itself is not safety-related, and NRC concurrence is not required for modifications to it.
But the CRDCS does interface with the reactor protection system (RPS) by way of the RTBs.
Since the RTBs are safety-related components of the RPS, changes to them do require NRC concurrence. In the present case, the RTBs are not altered functionally, but they are replaced with upgraded hardware and the configuration of the RTBs is simplified to accommodate the new CRDCS.
The licensee indicates that, in the new configuration:
The existing channelization, separation, and independence of the RTBs are retained.
The diverse trip system (DTS) retains its ability to interrupt power to the CRD mechanisms independently of the RTBs.
The new RTBs are seismically qualified, and they are located in areas not subject to harsh environments.
The new RTBs are an updated version of a type of hardware used widely and successfully in this application. They replace the original RTBs, which have become obsolete and increasingly difficult to maintain.
The new design is simpler and therefore more reliable than the existing design, and utilizes a smaller number of components.
The new design is similar to the design currently in use at Davis Besse Nuclear Power Station (Davis Besse). The Davis Besse design has been shown to be more reliable than the Oconee design.
The information provided by the licensee confirms that failure of any one RTB will not inhibit the trip function. The DTS is not altered in the proposed TS changes. The interface of the DTS with the CRDCS is altered as a result of the change in the CRDCS modifications, but the interface functions remain unchanged.
It is, therefore, reasonable to expect that the modified configuration will retain the level of reliability credited in the original design.
The present TSs address the present plant configuration. The planned modification will alter the configuration in such a manner as to render the present TSs no longer applicable. The proposed TS changes address the planned changes in system configuration. The proposed TS changes do not alter the intent of the TS requirements, and are, therefore, acceptable.
Based upon the above evaluation, there is reasonable assurance that the licensee will continue to meet the criteria described in the foregoing regulatory evaluation.
On the basis of the above regulatory and technical evaluations of the licensees justifications for TS changes, the NRC staff concludes that the licensees proposed TS changes 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 change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. 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 (69 FR 19566). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). 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: P. Rebstock Date: November 2, 2004
Oconee Nuclear Station, Units 1, 2, and 3 cc:
Ms. Lisa F. Vaughn Duke Energy Corporation Mail Code - PB05E 422 South Church Street Post Office Box 1244 Charlotte, North Carolina 28201-1244 Ms. Anne W. Cottingham, Esquire Winston and Strawn 1400 L Street, NW Washington, DC 20005 Manager, LIS NUS Corporation 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Senior Resident Inspector U.S. Nuclear Regulatory Commission 7812B Rochester Highway Seneca, South Carolina 29672 Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Dept. of Health and Env. Control 2600 Bull Street Columbia, South Carolina 29201-1708 Mr. Michael A. Schoppman Framatome ANP 1911 North Ft. Myer Drive Suite 705 Rosslyn, Virginia 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Energy Corporation ON03RC 7800 Rochester Highway Seneca, South Carolina 29672 Ms. Karen E. Long Assistant Attorney General North Carolina Department of Justice Post Office Box 629 Raleigh, North Carolina 27602 Mr. R. L. Gill, Jr.
Manager - Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 South Church Street Mail Stop EC05P Charlotte, North Carolina 28202 Mr. Richard M. Fry, Director Division of Radiation Protection North Carolina Department of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, North Carolina 28210 Mr. Henry Barron Group Vice President, Nuclear Generation and Chief Nuclear Officer Post Office Box 1006-EC07H Charlotte, North Carolina 28201-1006