ML032380468
| ML032380468 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/25/2003 |
| From: | Olshan L NRC/NRR/DLPM/LPD2 |
| To: | Rosalyn Jones Duke Energy Corp |
| Olshan L N, NRR/DLPM, 415-1419 | |
| References | |
| TAC MB8415, TAC MB8416, TAC MB8417 | |
| Download: ML032380468 (14) | |
Text
August 25, 2003 Mr. Ronald A. Jones Vice President, Oconee Site Duke Energy Corporation P. O. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MB8415, MB8416, AND MB8417)
Dear Mr. Jones:
The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 333, 333, and 334 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 April 10, 2003, as supplemented by letter dated July 1, 2003.
The amendments revise the frequencies associated with Surveillance Requirements 3.4.12.5 and 3.4.12.7 concerning the Low Temperature Overpressure Protection System.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions 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. 333 to DPR-38
- 2. Amendment No. 333 to DPR-47
- 3. Amendment No. 334 to DPR-55
- 4. Safety Evaluation cc w/encls: See next page
August 25, 2003 Mr. Ronald A. Jones Vice President, Oconee Site Duke Energy Corporation P. O. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MB8415, MB8416, AND MB8417)
Dear Mr. Jones:
The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 333, 333, and 334 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 April 10, 2003, as supplemented by letter dated July 1, 2003.
The amendments revise the frequencies associated with Surveillance Requirements 3.4.12.5 and 3.4.12.7 concerning the Low Temperature Overpressure Protection System.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commissions 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. 333 to DPR-38
- 2. Amendment No. 333 to DPR-47
- 3. Amendment No. 334 to DPR-55
- 4. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDII-1 R/F EHackett JNakoski LOlshan CHawes OGC ACRS GHill(6)
KKavanagh RHaag,RII RDennig LPlisco, RII ADAMS Accession Numbers:
Package: ML032380477 Amendment: ML032380468 TS(s): ML032400518
PDII-1/SC NAME LOlshan CHawes SCole JWermiel SMagruder JNakoski DATE 8/7/03 8/7/03 8/14/03 8/21/03 8/6/03 8/22/03 OFFICIAL RECORD COPY
DUKE ENERGY CORPORATION DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 333 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 April 10, 2003, as supplemented July 1, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commissions 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 Commissions 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 Commissions 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. 333, 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/
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: August 25, 2003
DUKE ENERGY CORPORATION DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 333 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 April 10, 2003, as supplemented July 1, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commissions 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 Commissions 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 Commissions 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. 333, 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/
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: August 25, 2003
DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 334 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 April 10, 2003, as supplemented July 1, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commissions 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 Commissions 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 Commissions 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. 334, 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/
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: August 25, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 333 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 333 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 334 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix A Technical Specifications and associated Bases with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert 3.4.12-4 3.4.12-4 3.4.12-5 3.4.12-5 B 3.4.12-11 B 3.4.12-11 B 3.4.12-12 B 3.4.12-12
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 333 TO RENEWED FACILITY OPERATING LICENSE DPR-38 AMENDMENT NO. 333 TO RENEWED FACILITY OPERATING LICENSE DPR-47 AND AMENDMENT NO. 334 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 April 10, 2003, as supplemented by letter dated July 1, 2003, Duke Energy Corporation, the licensee, submitted a request to revise Technical Specification (TS) 3.4.12, Low Temperature Overpressure Protection (LTOP) System," for the Oconee Nuclear Station, Units 1, 2 and 3. Specifically, the licensee requested to revise the frequencies associated with Surveillance Requirements (SR) 3.4.12.5 and 3.4.12.7. The supplemental letter dated July 1, 2003, provided clarifying information that did not change the scope of the April 10, 2003, application nor the initial proposed no significant hazards consideration determination.
2.0 REGULATORY EVALUATION
The LTOP system protects the reactor vessel from excessive pressure at low temperature conditions. The LTOP system TS requires the system to be operable with high pressure injection deactivated and the core flood tanks isolated and an operable pressurizer power operated relief valve (PORV) with a lift setpoint based on the low temperature overpressure limits. The TS also requires operator action, assisted by administrative controls and alarms.
TS 3.4.12 provides reactor coolant system (RCS) overpressure protection in MODE 3 when any RCS cold leg temperature is 325 degrees Fahrenheit, and MODES 4, 5, and 6 when an RCS vent path capable of mitigating the most limiting LTOP event is not open. When the reactor is in the applicable MODES, TS 3.4.12 ensures an adequate pressure relief capacity and a limit on coolant addition capability, and thus ensures that the RCS pressure boundary is not compromised by violating the pressure and temperature requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix G.
The Commissions regulatory requirements related to the content of Technical Specifications are set forth in 10 CFR 50.36. This regulation requires that the TS include items in five specific categories. These categories include 1) safety limits, limiting safety system settings and limiting control settings, 2) limiting conditions for operation, 3) surveillance requirements,
- 4) design features, and 5) administrative controls.
In particular, 10 CFR 50.36(c)(3) sets forth the criteria for SRs TS; it states:
- 3) Surveillance requirements. Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
The Commission has concluded that the timing of the frequency of a required surveillance is material to the performance of the surveillance. This is supported by the Final Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, 58 FR 39132 (July 22, 1993). Therefore, a frequency for surveillance requirement can be deleted as long as it is not required to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.
3.0 EVALUATION 3.1 Revision of SR 3.4.12.5 Surveillance Requirement 3.4.12.5 currently requires the performance of a CHANNEL FUNCTIONAL TEST for PORV within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS temperature to 325 degrees Fahrenheit AND 31 days thereafter. Since TS 3.4.12 is not required to be met in MODES 1, 2, and 3 when any RCS cold leg temperature is > 325 degrees Fahrenheit, SR 3.4.12.5 is not performed during these modes. However, SR 3.0.4 requires that entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unless the LCOs Surveillances have been met within their specified Frequency. Therefore, the licensee is required to perform SR 3.4.12.5 prior to reaching MODE 3 when any RCS cold leg temperature is 325 degrees Fahrenheit and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS temperature to 325 degrees Fahrenheit.
The licensee has proposed to delete the surveillance frequency that requires the performance of the CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS temperature to
325 degrees Fahrenheit. As proposed, the revised SR 3.4.12.5 FREQUENCY for the CHANNEL FUNCTIONAL TEST would be 31 days.
The NRC staff has reviewed the licensees proposed change to SR 3.4.12.5. As discussed in the Use and Application section of the Babcock and Wilcox Standard Technical Specifications (NUREG-1430, Revision 2, dated June 2001), the revised SR 3.4.12.5 Frequency specifies an interval (31 days) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 31 days, an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO).
If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4. Therefore, the NRC staff has concluded that the deletion of within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after decreasing RCS temperature to 325 F is acceptable because of the requirements of SR 3.0.4 to perform the surveillance prior to entry into the MODE of Applicability. For this reason, the deleted requirement is not needed to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCO will be met and is not required by 50.36 to remain in the TSs.
3.2 Revision of SR 3.4.12.7 Surveillance Requirement 3.4.12.7 currently requires the performance of a CHANNEL CALIBRATION for the PORV every 18 months. The licensee has proposed to reduce the current SR 3.4.12.7 Frequency from 18 months to 6 months. The licensee stated that the proposed reduction in the frequency time is necessary to reflect values in the supporting calculations. In particular, the supporting calculations for the RCS Low Range Pressure Transmitter have shown that a recalibration interval of 6 months results in a single-sided 95/95 probability confidence of 9.4 psig. The uncertainty used in the LTOP evaluation analysis bounds the 6-month 9.4 psig instrument uncertainty. The NRC staff has reviewed the proposed change. The NRC staff considers the proposed change to be more restrictive due to the reduction in frequency time for SR 3.4.12.7. Based on the above, the NRC staff has concluded that the proposed more restrictive change from 18 months to 6 months is acceptable.
3.3 Summary The NRC staff has reviewed the licensees submittal and supporting documentation. Based on its review, the NRC staff finds the proposed revision to the FREQUENCY of SR 3.4.12.5 and the proposed revision to the FREQUENCY of SR 3.4.12.7 to be acceptable for Oconee, Units 1, 2, and 3.
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 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 (68 FR 28850). 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 Commissions 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.
7.0 REFERENCES
Principal Contributor: K. Kavanagh Date: August 25, 2003
Oconee Nuclear Station cc:
Ms. Lisa F. Vaughn Legal Department (ECIIX)
Duke Energy Corporation 422 South Church Street Charlotte, North Carolina 28201-1006 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 Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201-1708 Mr. Michael A. Schoppman Framatome ANP 1911 North Ft. Myer Drive Suite 705 Rosslyn, VA 22209 Mr. L. E. Nicholson Compliance Manager Duke Energy Corporation Oconee Nuclear Site 7800 Rochester Highway Seneca, South Carolina 29672 Ms. Karen E. Long Assistant Attorney General North Carolina Department of Justice P. O. Box 629 Raleigh, North Carolina 27602 Mr. C. Jeffrey Thomas Manager - Nuclear Regulatory Licensing Duke Energy Corporation 526 South Church Street Charlotte, North Carolina 28201-1006 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