ML16246A095

Correction to 8/26/16 Request for Additional Information Enclosure, License Amendment Request to Revise Technical Specification 5.3.2 to Allow Operation with 56 Full-Length Control Rod Assemblies

ML16246A095
Person / Time
Site:	South Texas
Issue date:	09/15/2016
From:	Lisa Regner Plant Licensing Branch IV
To:	Gerry Powell South Texas
Regner L
References
CAC MF7577
Download: ML16246A095 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 15, 2016 Mr. G. T. Powell Executive Vice President and CNO STP Nuclear Operating Company South Texas Project P.O. Box 289 VVadsworth, TX 77483

SUBJECT:

SOUTH TEXAS PROJECT, UNIT 1 - CORRECTION TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO PERMANENT OPERATION OF UNIT 1 VVITH 56 CONTROL RODS (CAC NO. MF7577)

Dear Mr. Powell:

By letter dated April 7, 2016 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML16110A297), as supplemented by letter dated May 25, 2016 (ADAMS Accession No. ML16162A196), STP Nuclear Operating Company, the licensee for South Texas Project, Unit 1, submitted a license amendment request (LAR) to allow long-term operation of Unit 1 with 56 full-length control rod assemblies instead of the originally designed 57 control rods.

By letter dated August 26, 2016 (ADAMS Accession No. ML16214A291), the U.S. Nuclear Regulatory Commission (NRC) issued a request for additional information (RAI) to allow the NRC staff to complete its review of the LAR. Subsequently, the NRC staff identified an error in the RAI and notified the licensee by e-mail. The error involves an unrelated statement at the end of question 2.c.3. that should be deleted. The text below shows the sentence to be deleted.

Feedwater System Pipe Break: Table 7 identifies trip reactivity as impacted while the reload methodology does not identify trip reactivity as a key safety parameter.

The reload methodology identifies SOM as a key safety parameter while Table 7 does of the LAR does not identify SOM as impacted.

The other questions in the RAI are not impacted by the error.

G. T. Powell I regret any inconvenience this may have caused. If you have further concerns, please contact me at 301-415-1906 or via e-mail at Lisa.Regner@nrc.gov.

Sincere Lisa M. Regner, Senior Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-498 cc: Listserv

ML16246A095 OFFICE NRR/DORL/LPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DORL/LPL4-1 /BC NRR/DORL/LPL4-1 /PM NAME LRegner JBurkhardt RPascarelli LRegner DATE 9/8/16 9/8/16 9/15/16 9/15/16