ML16012A139
| ML16012A139 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 02/04/2016 |
| From: | Martha Barillas Plant Licensing Branch II |
| To: | Glover R Duke Energy Corp |
| Barillas M, NRR/DORL/LPL2-2 | |
| References | |
| CAC MF7048 | |
| Download: ML16012A139 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Richard Michael Glover Site Vice President H. B. Robinson Steam Electric Plant Duke Energy 3581 West Entrance Road, RNPA01 Hartsville, SC 29550 February 4, 2016
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT REQUEST FOR TECHNICAL SPECIFICATION CHANGE TO REACTOR COOLANT SYSTEM PRESSURE AND TEMPERATURE LIMITS (CAC NO. MF7048)
Dear Mr. Glover:
By letter dated November 2, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15307A069), as supplemented by letter dated December 22, 2015 (ADAMS Accession No. ML15356A481 ), Duke Energy Progress, Inc. submitted a license amendment request for the H. B. Robinson Steam Electric Plant, Unit No. 2 (Robinson). The December 22, 2015, supplement was in response to a U.S. Nuclear Regulatory Commission (NRC) staff request dated December 8, 2015 (ADAMS Accession No. ML16019A027). The proposed amendment would revise the reactor coolant system (RCS) pressure and temperature limits by replacing Technical Specification Section 3.4.3, "RCS Pressure and Temperature (PIT)
Limits, Figures 3.4.3-1 and 3.4.3-2, with figures that are applicable up to 50 effective full power years. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this 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 1 O of the Code of Federal Regulations (1 O 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.
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 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 the Robinson Project Manager, Martha Barillas, at (301) 415-2760 or Martha.Barillas@nrc.gov.
Docket No. 50-261 cc: Distribution via Listserv Sincerely,
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Ba la~, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML16012A139 OFFICE NRR/DORL/LPLll-2/PM NRR/DORL/LPLll-2/LA NRR/DORL/LPLll-2/BC NRR/DORL/LPLll-2/PM NAME (PBuckberg for) MBarillas (LRonewicz for) BClayton BBeasley (PBuckberg for) MBarillas DATE 2/01/2016 2/01/2016 2/02/2016 2/04/2016