Letter Sequence Acceptance Review |
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Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. 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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 6, 2014 Mr. William G. Gideon, Vice President H. B. Robinson Steam Electric Plant Duke Energy Progress, Inc.
3581 West Entrance Road Hartsville, SC 29550
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT 2- ACCEPTANCE REVIEW CONCERNING LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.3.1, REACTOR PROTECTION SYSTEM INSTRUMENTATION TURBINE TRIP FUNCTION (TAC NO. MF3463)
Dear Mr. Gideon:
By letter dated February 10, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14052A065), Duke Energy Progress, Inc., submitted a license amendment request for H. B. Robinson Steam Electric Plant, Unit 2. The proposed amendment request would revise the Technical Specification for the Reactor Protection System Instrumentation Turbine Trip function on Low Auto Stop Oil Pressure to a Turbine Trip function on Low Fluid Oil Pressure. In addition, the Nominal Trip Setpoint will be changed from its current value of 45 psig to 800 psig and a corresponding change in the Allowable Value from 40.87 psig to 769 psig. The proposed change also revises the Technical Specifications by applying additional testing requirements listed in Technical Specifications Task Force Traveler 493-A Revision 4, "Clarify Application of Setpoint Methodology for Limiting Safety System Setting Functions," for Low Electro-Hydraulic Fluid Oil Pressure trip only. In a followup email dated March 24,2014 (ADAMS Accession No. ML14155A251), the U.S. Nuclear Regulatory Commission (NRC) staff requested the new setpoint calculation associated with this license amendment request. Duke Energy Progress, Inc., submitted a supplemental letter dated April 4, 2014 (ADAMS Accession No. ML14107A344) providing the new setpoint calculation.
The purpose of this letter is to provide the results of the NRC staff's acceptance review of this license amendment 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. 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.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following 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.
W. Gideon The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete 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. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified in requests for additional information despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact me at (301) 415-2760.
Sincerely, IRA/
Martha Barillas, Project Manager Plant Licensing Branch 2-11 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-261 cc: Distribution via Listserv
ML14156A274 OFFICE NRR/DORULPL2-II/PM NRR/DORULPL2-II/LA NRR/DORULPL2-II/BC NRR/DORULPL2-II/PM NAME MBarillas BCiayton LRegner MBarillas DATE 6/5/14 6/5/14 6/6/14 6/6/14