ML14157A077
| ML14157A077 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/13/2014 |
| From: | Martha Barillas Plant Licensing Branch II |
| To: | Kapopoulos E Duke Energy Progress |
| Barillas M DORL/LPL2-2 301-415-2760 | |
| References | |
| TAC MF4112 | |
| Download: ML14157A077 (3) | |
Text
Mr. Ernest Kapopolous Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 13, 2014 Shearon Harris Nuclear Power Plant Duke Energy Progress, Inc.
5413 Shearon Harris Road New Hill, NC 27562
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE-510-A, "REVISION TO STEAM GENERATOR PROGRAM INSPECTION FREQUENCIES AND TUBE SAMPLE SELECTION," USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (TAC NO. MF4112)
Dear Mr. Kapopolous:
By letter dated April24, 2014 (Agencywide Documents Access and Management System Accession No. ML14114A743), Duke Energy Progress, Inc., submitted a license amendment request for Shearon Harris Nuclear Power Plant, Unit 1. The proposed amendment request would revise the Technical Specifications requirements regarding steam generator tube inspections and reporting as described in Technical Specifications Task Force (TSTF) change TSTF-510-A, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (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.
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.
Docket No. 50-400 cc: Distribution via Listserv Sincerely, IRA!
Martha Barillas, Project Manager Plant Licensing Branch 2-11 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML14157A077 OFFICE DORULPL2-II/PM DORULPL2-II/LA NAME MBarillas BCiayton DATE 6/11/14 6/11/14 Sincerely, IRA/
Martha Barillas, Project Manager Plant Licensing Branch 2-11 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- Via e-mail NRR/DSS/STSB
- DORULPL2-II/BC (A} DORULPL2-II/PM REIIiott LRegner (RGrover for)
(FSaba for)
MBarillas 6/3/14 6/12/14 6/13/14