GNRO-2016/00050, Correction to Safety Analysis Report for Constant Pressure Power Uprate

Correction to Safety Analysis Report for Constant Pressure Power Uprate

ML16307A136
Person / Time
Site:	Grand Gulf
Issue date:	11/02/2016
From:	Fallacara V Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2016/00050
Download: ML16307A136 (3)

Text

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~Entergy Entergy Operations, Inc.

P.O. Box 756 Port Gibson, MS 39150 Vincent Fallacara Vice President, Operations Grand Gulf Nuclear Station Tel. (601) 437-7500 GNRO-2016/00050 November 2, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Correction to Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. GE Hitachi Nuclear Energy, "Safety Analysis Report for Grand Gulf Nuclear Station constant Pressure Power Uprate," NEDC-33477P, dated March 2012

2. GEH Letter, "Correction to NEDC-33477P, Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate," dated June 13,2016

Dear Sir or Madam:

GE-Hitachi Nuclear Energy Americas LLC (GEH) developed and implemented Extended Power Uprate (EPU) at Grand Gulf Nuclear Station (GGNS). The Constant Pressure Power Uprate (CPPU) was approved by the Nuclear Regulatory Commission (NRC) in the Licensing Topical Report (LTR) NEDC-33004P-A, Revision 4, "Constant Pressure Power Uprate," referred to as the CLTR. The CLTR was approved for Boiling Water Reactor (BWR) plants containing General Electric (GE) fuel types and GEH accident analysis methods.

Section 2.2.2.3 of Reference 1, "Reactor Pressure Vessel Structural Evaluation," contains a review of all Reactor Pressure Vessel (RPV) components having a CLTP 40-year Cumulative Usage Factor (CUF) greater than 0.5. By Reference 2, GEH made a correction to Section 2.2.2.3 of Reference 1, stating that GGNS is a GE BWR/6-251-inch Mark III containment design which has no RPV stabilizer. The GEH investigation demonstrated that no RPV stabilizer existed in any of the dynamic Design Adequacy Evaluations (DAEs) performed for Grand Gulf Nuclear Station prior to, and including, Reference 1. The RPV stabilizer is not credited for RPV structural support and is not subjected to fatigue caused by EPU loadings.

GGNS will remove the RPV stabilizer from the EPU Safety Analysis Report.

This letter contains no new Regulatory Commitments.

If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.

GNRO-2016/00050 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on November 2, 2016.

cc: (See Next Page)

GNRO-20 16/00050 Page 3 of 3 cc: U.S. Nuclear Regulatory Commission ATTN: Mr. Jim Kim, NRR/DORL (w/2)

Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss M. Kennedy (w/2)

Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Mr. B. J. Smith (w/2)

Director, Division of Radiological Health Mississippi State Department of Health Division of Radiological Health 3150 Lawson Street Jackson, MS 39213 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150