Letter Sequence Acceptance Review |
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MONTHYEARML0921500542009-05-31031 May 2009
ANP-2693(NP), Revision 0, Loss of Forced Reactor Coolant Flow Analysis for Harris Nuclear Plant, Unit 1, Enclosure 4 to Serial: HNP-09-068
Project stage: Request
ML0923104762009-08-20020 August 2009
Acceptance Review Regarding Amendment to Allow the Use of Thermal Hydraulic Analysis Code S-RELAP5 for Non Loss of Coolant Accident Transients
Project stage: Acceptance Review
ML0923103432009-08-28028 August 2009
Request for Withholding of Proprietary Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML1003213342010-02-0202 February 2010
Request for Additional Information Regarding Amendment to Allow the Use of Thermal Hydraulic Analysis Code S-RELAP5 for Non Loss of Coolant Accident Transients (Tac ME1736)
Project stage: RAI
ML1023103612010-12-23023 December 2010
Issuance of Amendment 135 to Allow the Use of Thermal Hydraulic Analysis Code S-Relap5 for Non Loss of Coolant Accident Transients
Project stage: Approval
2009-08-28
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Category:Letter
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Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 August 20, 2009 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 ALLOW THE USE OF THE THERMAL-HYDRAULIC COMPUTER ANALYSIS CODE, S-RELAP5 FOR NON-LOSS-OF-COOLANT ACCIDENT TRANSIENTS (TAC NO. ME1735)
Dear Mr. Burton:
By letter dated July 21, 2009 (Agencywide Documents Access and Management System Accession No. ML092150228), 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
(!\IRC)-approved Topical Report (TR) EMF-23 10(P)(A), "SRP Chapter 15 Non-LOCA [Loss-of-Coolant]
Methodology for Pressurized Water Reactors," to the Core Operating Limits Report methodologies list. This change will allow the use of thermal-hydraulic computer analysis code, S-RELAP5 for Final Safety Analysis Report (FSAR) Chapter 15 non-LOCA transients in the HNP safety analyses.
Topical Report EMF-23 10(P)(A), Revision 0, was approved by the NRC on May 11, 2001, for the application of the S-RELAP5 thermal-hydraulic computer analysis code to FSAR Chapter 15 non-LOCA transients.
Revision 1 of TR EMF-23 10(P)(A), approved by the NRC on May 19, 2004, updated Section 5.6 of the topical report. 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.
-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.
arlayna 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
-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.
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 rlf RidsNrrPMHarris RidsNrrDorlLpl2-2 ADAMS Accession No' ML092310476
.. NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME MVaaler CSoia TBoyce DATE 08/20109 08/20109 08/20109 OFFICIAL RECORD
