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| number = ML092310476 | | number = ML092310476 | ||
| issue date = 08/20/2009 | | issue date = 08/20/2009 | ||
| title = | | title = Acceptance Review Regarding Amendment to Allow the Use of Thermal Hydraulic Analysis Code S-RELAP5 for Non Loss of Coolant Accident Transients | ||
| author name = Vaaler M | | author name = Vaaler M | ||
| author affiliation = NRC/NRR/DORL/LPLII-2 | | author affiliation = NRC/NRR/DORL/LPLII-2 | ||
| addressee name = Burton C | | addressee name = Burton C | ||
| addressee affiliation = Carolina Power & Light Co | | addressee affiliation = Carolina Power & Light Co | ||
| docket = 05000400 | | docket = 05000400 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: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) | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION 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:== | ==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] | 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. | Methodology for Pressurized Water Reactors," to the Core Operating Limits Report methodologies list. | ||
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. | 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. | ||
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. | 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. | ||
Section 50.34 of 10 CFR addresses the content of technical information required. | 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. | ||
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | 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 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. | ||
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. | -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. | 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. | ||
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 | ||
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 | |||
'.. ML092310476 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME MVaaler CSoia TBoyce DATE 08/20109 08/20109 08/20109}} | |||
Latest revision as of 03:05, 14 November 2019
| ML092310476 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/20/2009 |
| From: | Vaaler M Plant Licensing Branch II |
| To: | Burton C Carolina Power & Light Co |
| Vaaler, Marlayna, NRR/DORL 415-1998 | |
| References | |
| TAC ME1735 | |
| Download: ML092310476 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION 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
'.. ML092310476 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME MVaaler CSoia TBoyce DATE 08/20109 08/20109 08/20109