ML050910211
| ML050910211 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/05/2006 |
| From: | Olshan L Plant Licensing Branch III-2 |
| To: | Brandi Hamilton Duke Energy Corp |
| Olshan L N, NRR/DLPM, 415-1419 | |
| Shared Package | |
| ML061210178 | List: |
| References | |
| TAC MC5532, TAC MC5533, TAC MC5534 TS 5.5.19.b | |
| Download: ML050910211 (14) | |
Text
July 5, 2006 Mr. Bruce H. Hamilton 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 REGARDING LCT TESTING(TAC NOS. MC5532, MC5533, AND MC5534)
Dear Mr. Hamilton:
The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 352, 354, and 353 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 5, 2005, as supplemented November 21, 2005.
The amendments revise the Technical Specification (TS) 5.5.19 associated with the Lee Combustion Turbine (LCT) testing program. TS 5.5.19.b required verification that an LCT can supply the equivalent of one Units maximum safeguard loads, plus two Units Mode 3 loads when connected to the system grid every 12 months. In the enclosed amendments, this requirement is more clearly specified as verify an LCT can supply equivalent of one units Loss of Coolant Accident (LOCA) loads plus two units Loss of Offsite Power (LOOP) loads when connected to system grid every 12 months. The amendment also revises TS 5.5.19.c and TS Surveillance Requirement 3.8.1.9 for consistency.
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. 352 to DPR-38
- 2. Amendment No. 354 to DPR-47
- 3. Amendment No. 353 to DPR-55
- 4. Safety Evaluation cc w/encls: See next page
July 5, 2006 Mr. Bruce H. Hamilton 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 REGARDING LCT TESTING(TAC NOS. MC5532, MC5533, AND MC5534)
Dear Mr. Hamilton:
The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 352, 354, and 353 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 5, 2005, as supplemented November 21, 2005.
The amendments revise the Technical Specification (TS) 5.5.19 associated with the Lee Combustion Turbine (LCT) testing program. TS 5.5.19.b required verification that an LCT can supply the equivalent of one Units maximum safeguard loads, plus two Units Mode 3 loads when connected to the system grid every 12 months. In the enclosed amendments, this requirement is more clearly specified as verify an LCT can supply equivalent of one units Loss of Coolant Accident (LOCA) loads plus two units Loss of Offsite Power (LOOP) loads when connected to system grid every 12 months. The amendment also revises TS 5.5.19.c and TS Surveillance Requirement 3.8.1.9 for consistency.
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. 352 to DPR-38
- 2. Amendment No. 354 to DPR-47
- 3. Amendment No. 353 to DPR-55
- 4. Safety Evaluation DISTRIBUTION: See next page Package Number: ML061210178 Tech Spec Number: ML061860544 Amendment Number: ML050910211 NRR-058 OFFICE NRR/LPL2-1/PM PDII-1/LA OGC BBIB/SC IROB/SC NRR/LPL2-1/BC NAME LOlshan CHawes MYoung EBrown TBoyce EMarinos DATE 6/21/06 4/13/05 6/14/06 3/23/06 3/28/05 6/28/06 OFFICIAL RECORD COPY
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - ISSUANCE OF AMENDMENTS NOS., 352, 354, 353 RE: LCT TESTING (TAC NOS. MC5532, MC5533 AND MC5534)
Date: July 5, Distribution Public LPL2-1 r/f RidsNrrPMLOlshan RidsNrrPMRMartin RidsNrrLAMOBrien RidsNrrDorlLplc(EMarinos)
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DUKE ENERGY CORPORATION DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 352 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 5, 2005, as supplemented November 21, 2005, 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. 352, 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:
Technical Specification Changes Date of Issuance: July 5, 2006
DUKE ENERGY CORPORATION DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 354 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 5, 2005, as supplemented November 21, 2005, 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. 354, 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:
Technical Specification Changes Date of Issuance: July 5, 2006
DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 353 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 5, 2005, as supplemented November 21, 2005, 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. 353, 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:
Technical Specification Changes Date of Issuance: July 5, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 352 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 354 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 353 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Operating Licenses and 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 License Pages License Pages License No. DPR,-38, Page 3 License No. DPR,-38, Page 3 License No. DPR,-47, Page 3 License No. DPR,-47, Page 3 License No. DPR,-55, Page 3 License No. DPR,-55, Page 3 TS Pages TS Pages 3.8.1-15 3.8.1-15 5.0-25 5.0-25
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 352 TO RENEWED FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO. 354 TO RENEWED FACILITY OPERATING LICENSE DPR-47 AND AMENDMENT NO. 353 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 January 5, 2005, 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 5.5.19, which is associated with the Lee Combustion Turbine (LCT) testing program. TS 5.5.19.b currently requires verification that an LCT can supply the equivalent of one Units maximum safeguard loads, plus two Units Mode 3 loads when connected to the system grid every 12 months. In the proposed amendments, this requirement would be more clearly specified as verify an LCT can supply equivalent of one units Loss of Coolant Accident (LOCA) loads plus two units Loss of Offsite Power (LOOP) loads when connected to system grid every 12 months. The proposed amendments also would revise TS 5.5.19.c and TS Surveillance Requirements 3.8.19 for consistency.
2.0 REGULATORY EVALUATION
Section 3.1 of the Oconee Updated Final Safety Analysis Report (UFSAR) states, The principal design criteria for Oconee were developed in consideration of the seventy General Design Criteria for Nuclear Power Plant Construction Permits proposed by the Atomic Energy Commission in a proposed rule-making published for 10 CFR Part 50 in the Federal Register of July 11, 1967. The criterion that applies to this amendment request is Criterion 39, Emergency Power for Engineered Safety Features. Criterion 39 is discussed in Section 3.1.39 of the UFSAR; Criterion 39 states:
Alternate power systems shall be provided and designed with adequate independency, redundancy, capacity, and testability to permit functioning required of the engineered safety features. As a minimum, the on-site power system and the off-site power system shall each, independently, provide this capacity assuming a failure of a single active component in each power system.
Section 8.2.1.4 of the UFSAR states:
Whenever there is inadequate power from the generating units, the 230 kV switching station and the hydro units, power is available to the standby buses either directly from the 100 kV Central Tie Substation or from Lee Steam Station via a 100 kV transmission line connected to 12/16/20 MVA Transformer CT5 located on the opposite side of the station from the 230 kV facilities. This section also states, located at Lee Steam Station are three 44.1 MVA combustion turbines. One of these three turbines can be started in one hour and connected to the 100 kV line.
Transformer CT5 is sized to carry all the engineered safeguards auxiliaries of one unit plus the shutdown loads of the other two units.
Table 8-1 of the UFSAR provides a list of loads that automatically start after a loss-of-coolant accident or loss of offsite power, and the loads required to mitigate the event.
The licensing basis for the LCTs is contained in the Safety Evaluation of the Duke Power Company Oconee Nuclear Power Station Unit 1, issued December 29, 1970. This safety evaluation refers to the LCTS as the gas turbines and, in Section 8.4, it states:
In evaluating these power sources, we have considered the gas turbine as a temporary substitute power source for use primarily during the periods when the hydro units are not available. The applicant has estimated these periods to be approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> each year plus 4 days once every 10 years when the common penstock will be drained for inspection and maintenance. During these periods the gas turbine will be run at rated speed, with no load, and will be directly connected, through the Oconee 100-kV switchyard over the isolated line, to the standby buses for automatic selection in the event that the 230-kV power source is lost.
Section 8.0 of the Safety Evaluation of the Oconee Nuclear Power Station Units 2 and 3, issued July 6, 1973, extends the Unit 1 evaluation to Units 2 and 3.
3.0 TECHNICAL EVALUATION
Prior to Amendment 232, 232, 231, issued September 4, 1998, TS 4.6.8 stated, Annually, it shall be demonstrated that a Lee station combustion turbine can be started and carry the equivalent of the maximum safeguards load of one Oconee unit plus the safe shutdown loads of two Oconee units on the system grid. Amendment 232, 232, 231 changed the terminology safe shutdown loads to hot shutdown loads.
Hot shutdown was defined as the reactor subcritical and the average reactor coolant temperature (TAVG) greater than 525 °F. In the conversion to the Improved Technical Specifications (ITS),
Amendment 300, 300, 300, issued December 16, 1998, MODE 3 was determined, in general, to best describe the characteristics for hot shutdown; MODE 3 in the ITS is defined as the reactor subcritical and TAVG equal to or greater than 250 °F. Therefore, the terminology hot shutdown loads was changed to MODE 3 loads in the ITS conversion, and the requirement was relocated from TS 4.6.8 to TS 5.5.19.b.
As the plant is heating up to full power and as TAVG is increasing above 250 °F, while still in MODE 3, additional loads are added that are not needed to safely shut down the plant, and therefore, are beyond the design basis for the LCTs. These loads include the condensate booster pumps and the reactor coolant pumps. The terminology MODE 3 loads in TS 5.5.19 could be misconstrued to include these additional loads. Therefore, the licensee has proposed to clarify TS 5.5.19 by using the terminology Loss of Offsite Power (LOOP) loads, instead of MODE 3 loads. To be consistent with the terminology used in the UFSAR, the licensee also proposed to replace one units maximum safeguards loads with one units Loss of Coolant Accident (LOCA) loads.
The licensees submittal contained a typographical error in the replacement TS pages. Where the TSs refer to Loop loads for the other two units, it stated two units Loop loads. This is singular and incorrect. The TS pages issued with these amendments corrected this error by stating two units.
The NRC staff finds these proposed changes to be acceptable since the terminology is consistent with the design and licensing basis for the LCTs.
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 (70 FR 7764). 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: L. Olshan Date: July 5, 2006
Oconee Nuclear Station, Units 1, 2, and 3 cc:
Ms. Lisa F. Vaughn Duke Power Company LLC 526 South Church Street P. O. Box 1006 Mail Code EC07H Charlotte, North Carolina 28201-1006 Manager, LIS NUS Corporation 2650 McCormick Dr., 3rd Floor Clearwater, FL 34619-1035 Senior Resident Inspector U.S. Nuclear Regulatory Commission 7812B Rochester Highway Seneca, SC 29672 Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Dept. of Health and Env. Control 2600 Bull St.
Columbia, SC 29201-1708 Mr. Michael A. Schoppman Framatome ANP 1911 North Ft. Myer Dr.
Suite 705 Rosslyn, VA 22209 Mr. B. G. Davenport Regulatory Compliance Manager Oconee Nuclear Site Duke Power Company LLC ON03RC 7800 Rochester Highway Seneca, SC 29672 Ms. Karen E. Long Assistant Attorney General NC Department of Justice P.O. Box 629 Raleigh, NC 27602 Mr. R. L. Gill, Jr.
Manager - Nuclear Regulatory Issues and Industry Affairs Duke Power Company LLC 526 S. Church St.
Mail Stop EC05P Charlotte, NC 28202 Division of Radiation Protection NC Dept of Environment, Health, & Natural Resources 3825 Barrett Dr.
Raleigh, NC 27609-7721 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, NC 28210 Mr. Henry Barron Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006