ML101130511
| ML101130511 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/03/2010 |
| From: | Vaaler M Plant Licensing Branch II |
| To: | Burton C Carolina Power & Light Co |
| Vaaler, Marlayna, NRR/DORL 415-3178 | |
| References | |
| TAC ME3569 | |
| Download: ML101130511 (2) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 3,2010 Chris L Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165 SUB~IECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -ACCEPTANCE REVIEW REGARDING AMENDMENT TO INCORPORATE A REALISTIC LARGE-BREAK LOSS-OF-COOLANT ACCIDENT METHODOLOGY INTO THE CORE OPERATING LIMITS REPORT (TAC NO. ME3569)
Dear Mr. Burton:
By letter dated March 23, 2010 (Agencywide Documents Access and Management System Accession No. ML100890596), Carolina Power & Light Company, now doing business as Progress Energy Carolinas, Inc., submitted a proposed amendment for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment would revise Technical Specification Section 6.9.1.6 to add the U.S. Nuclear Regulatory Commission (NRC)-approved topical report (TR) EMF-21 03(P)(A), Revision 0, "Realistic Large-Break LOCA [Loss-of-Coolant Accident] Methodology for Pressurized Water Reactors," to the Core Operating Limits Report methodologies list.
This change will allow the use of the thermal-hydraulic computer analysis code S-RELAP5 for the Final Safety Analysis Report (FSAR) Chapter 15 realistic large-break LOCA in the HNP safety analyses. TR EMF-2103(P)(A), Revision 0, was approved by the NRC on April 9, 2003, for the application of the S-RELAP5 thermal-hydraulic analysis computer code to the FSAR Chapter 15 realistic large-break LOCA.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and follow, as far as applicable, the form prescribed for original applications.
Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The purpose of this letter is to provide the final results of the NRC staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed change. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
C. Burton
- 2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3178.
Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via ListServ
C.Burton
-2 The !\\IRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3178.
Sincerely, IRA!
Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via ListServ DISTRIBUTION:
PUBLIC RidsNrrLACSola LPL2-2 rtf RidsNrrPMHarris RidsNrrDorlLpl2-2 ADAMS Accession No' ML101130511 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC (A)
NAME MVaaler CSoia DBroaddus DATE 04/27/10 04/27/10 05/03/10 OFFICIAL RECORD COpy