ML15344A030
| ML15344A030 | |
| Person / Time | |
|---|---|
| Site: | Harris, Robinson  |
| Issue date: | 12/17/2015 |
| From: | Martha Barillas Plant Licensing Branch II |
| To: | Frisco J Duke Energy Corp |
| Barillas M | |
| References | |
| CAC MF5872, CAC MF5873 | |
| Download: ML15344A030 (5) | |
Text
Mr. Joseph M. Frisco, Jr.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 17, 2015 Vice President of Nuclear Engineering Duke Energy Corporation Mail Code EC07H P.O. Box 1006 Charlotte, NC 28201-1006
SUBJECT:
DUKE ENERGY PROGRESS, INC., FOR H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2, AND SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING APPLICATION TO REVISE TECHNICAL SPECIFICATIONS FOR METHODOLOGY REPORT DPC-NE-2005-P, REVISION 5, "THERMAL-HYDRAULIC STATISTICAL CORE DESIGN METHODOLOGY" (CAC NOS. MF5872 AND MF5873)
Dear Mr. Frisco:
By letter dated March 5, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15075A211 ), as supplemented by letter dated September 9, 2015 (ADAMS Accession No. ML15253A680), Duke Energy Progress, Inc. (Duke Energy, the licensee) submitted a request in accordance with Title 10 of the Code of Federal Regulations (10 CFR)
Section 50.90 for H.B. Robinson Steam Electric Plant, Unit No. 2 (Robinson), and Shearon Harris Nuclear Power Plant, Unit 1 (Harris), to amend its technical specifications to adopt the methodology report DPC-NE-2005-P, Revision 5, "Thermal-Hydraulic Statistical Core Design Methodology." During its proprietary determination review, the U.S. Nuclear Regulatory Commission (NRC) staff identified that ADAMS Accession No. ML15253A680 (supplement dated September 9, 2015), contains redaction errors made by the licensee. As such, the supplement is not publicly available at this time, but will be made publicly available once the errors are corrected by Duke Energy. The staff is currently working with the licensee to resolve the redaction errors and make the redacted document publicly available.
The NRC staff is reviewing the licensee's submittal and has determined that additional information is needed to complete its review. The enclosed document contains this request for additional information (RAI). The RAI was e-mailed to the licensee in draft form on November 9, 2015, and a clarification call was held on November 10, 2015. Following the call, the staff revised the draft RAI and e-mailed it on November 25, 2015. Attached is the RAI in its final form. Your staff determined no clarification call was needed and confirmed the RAI did not include proprietary or security-related information. You agreed to provide the RAI response by December 24, 2015.
The NRC staff considers that timely response to RAls helps ensure sufficient time is available for staff review and contributes toward the NRC's goal of efficient and effective use of staff resources. Please note that if you do not respond to this request by the agreed upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of 10 CFR 2.108.
If circumstances result in the need to revise the agreed upon response date, or if you have any questions, please contact me at 301-415-2760 or Martha.Barillas@nrc.gov.
Docket Nos. 50-261 and 50-400
Enclosure:
Request for Additional Information cc w/enclosure:
Mr. Benjamin C. Waldrep Site Vice President Shearon Harris Nuclear Power Plant 5413 Shearon Harris Road, M/C HNP01 New Hill, NC 27562-0165 Mr. Richard Michael Glover Site Vice President H. B. Robinson Steam Electric Plant Duke Energy 3581 West Entrance Road, RNPA01 Hartsville, SC 29550 Additional Distribution via Listserv Sincerely, Martha Barillas, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
REQUEST FOR ADDITIONAL INFORMATION DUKE ENERGY PROGRESS. INC. FOR H. B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO. 2. AND SHEARON HARRIS NUCLEAR POWER PLANT. UNIT 1.
PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS TO ADOPT METHODOLOGY REPORT DPC-NE-2005-P. REVISION 5.
"THERMAL-HYDRAULIC STATISTICAL CORE DESIGN METHODOLOGY."
DOCKET NOS. 50-261AND50-400 By letter dated March 5, 2015, 1 Duke Energy Progress, Inc. (Duke), the licensee for H. B.
Robinson Steam Electric Plant, Unit No. 2 (Robinson), and Shearon Harris Nuclear Power Plant, Unit 1 (Harris), requested U.S. Nuclear Regulatory Commission (NRC) review and approval of DPC-NE-2005-P, "Thermal-Hydraulic Statistical Core Design Methodology,"
Revision 5, for application to Robinson and Harris. In its submittal, Duke requested the adoption of DPC-NE-2005-P, Revision 5, into the Robinson and Harris Technical Specifications (TSs) Core Operating Limits Report (COLR) reference lists located in TS 5.6.5.b and TS 6.9.1.6.2, respectively. Duke supplemented the original submittal in a September 9, 2015, letter2 in response to an August 10, 2015, 3 NRC letter requesting additional information. The NRC staff determined additional information is needed to complete its review:
Nuclear Performance & Review Branch (SNPB)-Reguest for Additional lnformation-(RAll-6:
In its response to SNPB-RAl-4, Duke provided additional detail on the axial power peaking uncertainty, Fz, and axial peak location uncertainty, z, used in the Statistical Core Design (SCD) analysis for Robinson. These factors are intended to capture uncertainty in the performance of the nuclear design calculations and the uncertainty due to the axial nodalization of the nuclear design codes. The RAI response indicated that values provided in the original submittal were intended to bound the performance and nodalization of the CASM0-5/SIMULA TE-3 code system documented in DPC-NE-1008-P, "Nuclear Design Methodology Using CASM0-5/SIMULATE-3 for Westinghouse Reactors."
At this time, DPC-NE-1008-P has not been reviewed or approved by the NRC staff and is not in use at either Robinson or Harris. Since the neutronics code system currently in use at both Robinson and Harris has been approved with uncertainties on Fo and FllH and not Fz, explain how the uncertainty of the existing code system currently in use will be verified to be bounded 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML15075A211 2 ADAMS Accession No. ML15253A680 (non-proprietary) and ML15253A683 (proprietary) 3 ADAMS Accession No. ML15215A651 Enclosure by the uncertainties assumed in the Robinson and Harris SCD analysis, inclusive of the proposed Fz uncertainty being introduced, to assure General Design Criteria 10 requirements are met.
- by e-mail OFFICE DORL/LPLll-2/PM DORL/LPLI 1-2/LA NRR/DSS/SNPB*
DORL/LPLI 1-2/BC DORL/LPLll-2/PM NAME MBarillas BClayton JDean BBeasley MBarillas (LRonewicz for)
DATE 12/16/2015 12/16/2015 11/24/2015 12/17/2015 12/17/2015