ML18256A027

Traveler TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec

ML18256A027
Person / Time
Site:	Technical Specifications Task Force
Issue date:	10/31/2018
From:	Victor Cusumano NRC/NRR/DSS/STSB
To:
Honcharik M, NRR/DSS, 301-415-1774
References
Download: ML18256A027 (3)

Text

October 31, 2018 Technical Specifications Task Force 11921 Rockville Pike, Suite 100 Rockville, MD 20852

SUBJECT:

TRAVELER TSTF-490, REVISION 0, DELETION OF E BAR DEFINITION AND REVISION TO RCS SPECIFIC ACTIVITY TECH SPEC

Dear Members of the Technical Specifications Task Force:

The Technical Specifications Task Force (TSTF) submitted Traveler TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS [Reactor Coolant System] Specific Activity Tech Spec [Technical Specification], on September 13, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052630462). Traveler TSTF-490, Revision 0, was approved on March 8, 2007 (ADAMS Accession No. ML070250176). The U.S. Nuclear Regulatory Commission (NRC) staff published a Notice of Availability in the Federal Register (FR) on March 19, 2007 (72 FR 12838).

Subsequently, during plant-specific reviews to adopt TSTF-490, the NRC identified a need for additional information related to increasing the completion time for dose equivalent Xenon-133 (DEX). By letter dated April 27, 2016 (ADAMS Accession No. ML16113A402), the NRC staff notified the TSTF of additional information that licensees adopting TSTF-490 would need to provide.

The additional information and its basis were discussed with the TSTF during several meetings.

Upon further review of plant-specific submittals, the NRC staff has determined that additional information is not necessary. The TSTF-490 traveler justification was supported by the plant-specific reviews. The NRC staff position is that the additional information requested in the NRCs letter dated April 27, 2016, is not needed from licensees adopting TSTF-490, Revision 0, and that the model safety evaluation Section 3.1.6 is still valid.

If you have any questions, please contact Michelle Honcharik at 301-415-1774 or via e-mail at Michelle.Honcharik@nrc.gov.

Sincerely,

/RA/

Victor G. Cusumano, Chief Technical Specifications Branch Division of Safety Systems Office of Nuclear Reactor Regulation Project No. 753 cc: See next page

ML18256A027 *concurred via e-mail NRR-106 OFFICE NRR/DRA/ARCB/BC* NRR/DORL/LSPB/LA* NRR/DSS/STSB/PM* NRR/DSS/STSB/BC NAME KHsueh JBurkhardt MHoncharik VCusumano DATE 10/15/18 10/11/18 10/29/18 10/31/18 Technical Specifications Task Force Project No. 753 cc:

Technical Specifications Task Force c/o EXCEL Services Corporation 11921 Rockville Pike, Suite 100 Rockville, MD 20852 Attention: Brian D. Mann E-mail: brian.mann@excelservices.com James P. Miksa Entergy Nuclear Operations, Inc.

Palisades Nuclear Power Plant 27780 Blue Star Memorial Highway Covert, MI 49043 E-mail: jmiksa@entergy.com Jordan L. Vaughan Duke Energy EC2ZF / P.O. Box 1006 Charlotte, NC 28202 E-mail: jordan.vaughan@duke-energy.com Ryan M. Joyce Southern Nuclear Operating Company 3535 Colonnade Parkway / Bin N-274-EC Birmingham, AL 35243 E-mail: rmjoyce@southernco.com David M. Gullott Exelon Generation 4300 Winfield Road Warrenville, IL 60555 E-mail: David.Gullott@exeloncorp.com Wesley Sparkman Southern Nuclear Operating Company 42 Inverness Center Parkway / Bin B237 Birmingham, AL 35242 E-mail: wasparkm@southernco.com