ML021550412
| ML021550412 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/23/2002 |
| From: | Martin R NRC/NRR/DLPM/LPD2 |
| To: | Barron H Duke Energy Corp |
| Martin RE, NRR/DLPM, 415-1493 | |
| References | |
| TAC MB2679, TAC MB2680 | |
| Download: ML021550412 (11) | |
Text
May 23, 2002 Mr. H. B. Barron Vice President, McGuire Site Duke Energy Corporation 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
McGUIRE NUCLEAR STATION, UNITS 1AND 2 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MB2679 AND MB2680)
Dear Mr. Barron:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 202 to Facility Operating License NPF-9 and Amendment No. 183 to Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TS) in response to your application dated August 6, 2001.
The amendments revise the TS 3.3.1 allowable values for the reactor trip system instrumentation overtemperature delta temperature and overpower delta temperature setpoints.
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/
Robert E. Martin, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 202 to NPF-9
- 2. Amendment No. 183 to NPF-17
- 3. Safety Evaluation cc w/encl: See next page
May 23, 2002 Mr. H. B. Barron Vice President, McGuire Site Duke Energy Corporation 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
McGUIRE NUCLEAR STATION, UNITS 1AND 2 RE: ISSUANCE OF AMENDMENTS (TAC NOS. MB2679 AND MB2680)
Dear Mr. Barron:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 202 to Facility Operating License NPF-9 and Amendment No. 183 to Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TS) in response to your application dated August 6, 2001.
The amendments revise the TS 3.3.1 allowable values for the reactor trip system instrumentation overtemperature delta temperature and overpower delta temperature setpoints.
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/
Robert E. Martin, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 202 to NPF-9
- 2. Amendment No. 183 to NPF-17
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC RidsRgnh2MailCenter PDII-1 R/F GHill(4)
CHawes HBerkow RidsOgcRp RLaufer RidsAcrsAcnwMailCenter DOCUMENT NAME: G://PDII-1/McGuire/MB2679amd.wpd *See previous concurrence Accession Number: ML021550412 OFFICE PDII-1/PM PDII-1/LA OGC*
PDII-1/SC NAME RMartin CHawes RHoefling JNakoski DATE 05/23/02 05/23/02 01/22/02 05/23/02 OFFICIAL RECORD COPY
DUKE ENERGY CORPORATION DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. NPF-9
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility),
Facility Operating License No. NPF-9 filed by the Duke Energy Corporation (licensee) dated August 6, 2001, 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 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, are hereby incorporated into this 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: May 23, 2002
DUKE ENERGY CORPORATION DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 License No. NPF-17
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),
Facility Operating License No. NPF-17 filed by the Duke Energy Corporation (licensee) dated August 6, 2001, 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 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 183, are hereby incorporated into this 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: May 23, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 202 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 ATTACHMENT TO LICENSE AMENDMENT NO. 183 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 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 3.3.1-18 3.3.1-18 3.3.1-19 3.3.1-19
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 202 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 183 TO FACILITY OPERATING LICENSE NPF-17 REVISION TO TECHNICAL SPECIFICATIONS ASSOCIATED WITH THE OT T AND OP T ALLOWABLE VALUES FOR DUKE ENERGY CORPORATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By letter dated August 6, 2001, Duke Energy Corporation, et al. (DEC, the licensee), submitted a request for changes to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS). The licensee states that due to changes in reload reactor core designs since the 1.0F hot leg streaming uncertainty value was determined, it is now necessary to increase the uncertainty value to 1.21F. The requested changes revise the TS Table 3.3.1-1 overtemperature delta temperature (OT T) and overpressure delta temperature (OP T) allowable values.
2.0 EVALUATION In TS Table 3.3.1-1, the notes for the nominal trip setpoints that address allowable values are being changed for Items 6 and 7 in the table. It is proposed to decrease the OT T and the OP T Allowable Values. The TS Table 3.3.1-1 Allowable Value given in Note 1 will be decreased from 4.4 percent of rated thermal power (RTP) to 4.3 percent of RTP. The TS Table 3.3.1-1 Allowable Value given in Note 2 will be decreased from 3.0 percent of RTP to 2.6 percent of RTP. Each change is in the direction of increased conservatism. The TS Bases are unaffected by these changes.
The uncertainty analysis calculations for the OT T and OP T setpoint instrument channels include a process-measurement allowance to account for the variation in the measurement of the reactor coolant system hot leg temperature due to the temperature gradient that may exist in the hot leg (hot leg streaming phenomenon). The hot leg average temperature is determined by averaging the three hot leg resistance temperature device (RTD) indications. This hot leg temperature gradient may result in the hot leg average temperature indication being different from the actual bulk hot leg temperature. The present allowance of 1.0F was calculated by Westinghouse and incorporated into the uncertainty analyses for delta-temperature and average temperature (Tavg) related allowances at the time of the RTD bypass removal modification. The uncertainty value of 1.0oF resulted from the uncertainty calculations that used the approximately 9oF temperature gradient in the hot leg at the time of the RTD bypass removal modification. Westinghouse had determined the 1.0oF hot leg streaming allowance for both the McGuire and Catawba Stations from the interpretation of test data taken during hot leg temperature gradient testing performed earlier at McGuire Unit 1.
In the interval since the temperature gradient testing was performed, the licensee states that core designs have changed. These changes have resulted in higher core peaking and some indications of increases in the hot leg temperature gradient. Hot leg temperature gradients as large as 14oF have been seen at both McGuire and Catawba. The licensee performed an evaluation to determine whether the current hot leg streaming allowance of 1.0oF was adequate in view of the increases in the hot leg temperature gradients. A change in this streaming allowance has the potential to impact the following five uncertainty calculations:
OT T OP T Low Tavg (Feedwater Isolation)
Reactor Coolant Tavg (Rod Control)
Pressurizer Level Program The licensee used historical plant data from both McGuire and Catawba to directly calculate the changes in the hot leg streaming and determine a new streaming uncertainty. The calculation was performed using the Duke setpoint uncertainty methodology and the plant data spanning several operating cycles. The plant data were used to back-calculate a hot leg temperature, which was then compared to the average of the three hot leg RTDs. The licensee found that the existing allowances in each of the above five uncertainty calculations contained sufficient margin to accommodate the increase in the hot leg streaming allowance. However, the calculations indicate that a hot leg streaming uncertainty allowance used to account for the hot leg streaming phenomenon should be increased from 1.0 to 1.21o F. The increase in the hot leg streaming allowance in the uncertainty calculations results in a decrease in the Allowable Values for the OT T and OP T setpoints. The reduced Allowable Values are reflected in the changes to Table 3.3.1-1.
For the Reactor Coolant Tavg and Pressurizer Level Program, the uncertainty allowances continue to remain bounding as the channel statistical allowance for these functions continues to be within the total allowance assumed in the uncertainty analyses for these control systems.
The decrease in the Allowable Values is a change in the conservative direction and will not adversely affect the steady-state or transient analyses documented in Chapter 15 of the McGuire Nuclear Station Updated Final Safety Analysis Report (UFSAR). Since there is no increase in the total allowance applied to the setpoints used in the safety analyses, the applicable safety analyses remain bounding and valid. None of the analyses presented in UFSAR Chapters 3, 4, or 6 are affected by these changes. Therefore, the change in the Allowable Values for the OT T and OP T setpoints will not result in a reduction of safety margin for these analyses.
3.0 CONCLUSION
On the basis of the forgoing evaluations, the staff concludes that the proposed changes to TS Table 3.3.1-1 for McGuire Units 1 and 2 are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the North 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 (67 FR 2920). 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.
Principal Contributor: K. Mortensen, EEIB/DE Date: May 23, 2002
McGuire Nuclear Station cc:
Ms. Lisa F. Vaughn Legal Department (PBO5E)
Duke Energy Corporation 422 South Church Street Charlotte, North Carolina 28201-1006 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 Michael T. Cash Regulatory Compliance Manager Duke Energy Corporation McGuire Nuclear Site 12700 Hagers Ferry Road Huntersville, North Carolina 28078 Anne Cottingham, Esquire Winston and Strawn 1400 L Street, NW.
Washington, DC 20005 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission 12700 Hagers Ferry Road Huntersville, North Carolina 28078 Dr. John M. Barry Mecklenburg County Department of Environmental Protection 700 N. Tryon Street Charlotte, North Carolina 28202 Mr. Peter R. Harden, IV VP-Customer Relations and Sales Westinshouse Electric Company 6000 Fairview Road 12th Floor Charlotte, North Carolina 28210 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 Elaine Wathen, Lead REP Planner Division of Emergency Management 116 West Jones Street Raleigh, North Carolina 27603-1335 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. T. Richard Puryear Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, South Carolina 29745