ML16029A172
| ML16029A172 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/01/2016 |
| From: | Perry Buckberg Plant Licensing Branch II |
| To: | Nazar M Nextera Energy |
| Saba F, NRR/DORL/LPL2-2 | |
| References | |
| CAC MF6980, CAC MF6981 | |
| Download: ML16029A172 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420 February 1, 2016
SUBJECT:
ST. LUCIE PLANT, UNIT NOS. 1 AND 2 -ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING THE USE OF A NEW COMPUTER CODE TO MODEL THE CONTAINMENT VACUUM ANALYSES (CAC NOS. MF6980 AND MF6981)
Dear Mr. Nazar:
By letter dated October 15, 2015 (Agencywide Documents Access and Management System Accession No. ML15301A765), Florida Power & Light Company submitted a license amendment request (LAR) for the St. Lucie Plant, Unit Nos. 1 and 2 (St. Lucie). The proposed amendment would update the St. Lucie technical specifications (TSs) to reflect the use of "Generation of Thermal-Hydraulic Information for Containments (GOTHIC Version 7.2b(QA)),"
containment vacuum analyses computer code. The proposed change will also update the St. Lucie licensing bases to credit the design-basis ability of the containment vessel to withstand a higher external pressure differential of 1.04 pounds per square inch (psi) (1.05 psi for Unit No. 2), and will update Technical Specification 3.6.1.4 for both units to revise the allowable containment operating pressure range. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. 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 (10 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 1 O 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 me at (301) 415-1383 or Perry.Buckberg@nrc.gov.
Docket Nos. 50-335 and 50-389 cc: Distribution via Listserv Sincerely, 41
/--~/-
Perry uckberg, Senior Project Manager Plant icensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
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) 415-1383 or Pery.Buckberg@nrc.gov.
Sincerely, IRA!
Perry H. Buckberg, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorl RidsNrrDorllpl2-2 RidsNrrDssScvb DWoodyatt, NRR LPL2-2 R/F RidsNrrDorlDpr RidsNrrPMStlucie RidsNrrDeEmcb RidsACRS_MailCTR RidsNrrLABClayton RidsRgn2MailCenter ADAMS A ccess1on N ML16029A172 o.:
- b 1yema1 OFFICE DORL/LPLll-2/PM DORL/LPLll-2/LA DSS/SCVB/BC*
DE/EM CB/BC*
NAME PBuckberg (LRonewicz for)
RDennig Tlupold BClayton DATE 12/07/2015 1/29/2016 11/19/2015 12/04/2015 OFFICE DORL/LPLI 1-2/BC DORL/LPLll-2/PM NAME BBeasley PBuckberg DATE 2/01/2016 2/01/2016 OFFICIAL RECORD COPY